FOIA REQUEST
The following public document, NEDO 33262, written by General Electric Company and its foreign affiliate, references dozens of documents from INPO and/or NSAC. NRC likely has these documents in its files. Under this FOIA I am requesting that NRC place these documents into its PDR for access by the public. The public needs these documents in order to assess NEDO-33262.
Submittal of ESBWR Licensing Topical Report NEDO-33262, ESBWR Human Factors Engineering Operating Experience Review Implementation Plan (OER), Revision 2.
ML081560316
2008-05-31
The following list of INPO, NSAC and NSAC/INPO documents is compiled from NEDO-33262. These documents must be placed in NRC’s PDR under this FOIA.
INPO SOER 88-3
INPO SOER 85-4
INPO SOER 87-2
INPO SOER 84-7
INPO Significant Operating Experience Reports
INPO Significant Operating Experience Report 84-7, Pressure Locking and Thermal Binding ofGate Valves, December 14, 1984.
INPO Significant Event Reports
INPO Significant Event Report xx-9 1, - In Preparation - Inventory Drain Down, 1991.
INPO Significant Event Report 26-89, Loss of Residual Heat Removal Capability Due ToCommon Mode Failure of Flow Control Valves, October 4, 1989.
INPO Significant Event Report 11-89, Inadvertent Introduction of Hydrogen Into The Instrumentand Station Air Systems, April 11, 1989.
INPO Significant Event Report 5-89, Lack of Control of Testing Disables or Challenges SafetySystems, March 3, 1989.
INPO Significant Event Report 36-88, Loss of Residual Heat Removal Due to Misleading VisualIndication of Water Level, November 30, 1988.
INPO Significant Event Report 35-87, Non-lsolable Reactor Coolant System Leak, November12,1987.
INPO Significant Event Report 3 5-86, Extended Loss of Shutdown Cooling due to Steam Bindingof Shutdown Cooling Pumps, October 24, 1986.
INPO Significant Event Report 31-86, Loss of Residual Heat Removal Flow Due To InadvertentDraining Of The Reactor Coolant System, September 3, 1986.
INPO Significant Event Report 23-86, Loss of Decay Heat Removal Due To Inadequate ReactorCoolant System Level Control, July 3, 1986.
INPO Significant Event Report 17-86, Loss Of Shutdown Co. , Flow, May 27, 1986.
INPO Significant Event Report 79-84, Loss Of Shutdown Cooling Due to Inaccurate Level Indication, November 14, 1984.
INPO Significant Event Report 71-84, Residual Heat Removal Pump Damage Caused ByOperation With Suction Valve Closed, October 2, 1984.
INPO Significant Event Report 60-83, Loss of Residual Heat Removal (RHR) Cooling DuringReactor Vessel Drain Down, August 30, 1983.
INPO Significant Event Report 59-83, Residual Heat Removal (RHR) Pump Suction ValveClosure Due To Control Circuitry Design, August 18, 1983.
INPO Significant Event Report 13-83, Unplanned Radioactive Release and Loss of ShutdownCooling, February 25, 1983.
NSAC/INPO Significant Event Report 95-81, Automatic Valve Closure Causing Loss ofShutdown Decay Heat Removal, November 25, 1981.
NSAC/1NPO Significant Event Report 91-81, Steam Voiding in the Reactor Coolant SystemDuring Decay Heat Removal Cooldown, October 6, 1981.
NSAC/INPO Significant Event Report 89-81, Level Instrumentation Oscillations Due ToReference Leg Flashing, October 23, 1981.
NSAC/INPO Significant Event Report 87-81, Inadequate Reactor Coolant System (RCS) WaterLevel Indication, October 19, 1981.
NSAC/INPO Significant Event Report 78-81, Erroneous Indication. Reactor Vessel LevelCauses Loss of RHR, October 1, 1981.
INPO Nuclear Network, WE 655 ENR PAR 90-061, Residual Removal Flow FluctuationsDuring Drawing of Vacuum in the Reactor Coolant System, September 19, 1990.
INPO SERS 42-81 and 5-89.
INPO SERS 17-88 and 36-87
NSAC Report. 146.
INPO/NSAC Significant Operating Experience Report 80-5, Potential Loss of Coolant Accident(LOCA) From A Single Electrical Failure, September 23, 1980.
INPO Significant Experience Report 11-88, Inadvertent Disablement of The Automatic StartCapability For All Site Diesel Generators, May 6, 1988.
INPO Significant Experience Report 25-85, Emergency Diesel Generator Failed To SupplyEmergency Bus Due To Non-emergency Trip, June 3, 1985.
INPO Significant Experience Report 73-83, Loss of All AC Power (Blackout), October 27, 1983.
NSAC/INPO Significant Event Report 56-81, Loss of Station and Reserve Auxiliary Power,August 56, 1981.
INPO SOERs 87-2 and 85-1
NSAC Reports 52 and 43
INPO SOER 82-4, and SER 31-81 and SER 5-90.
INPO SER 38-85
INPO SER 72-84
INPO SOER 85-1.
INPO SOER 82-2
NSAC REPORT 88
INPO SER 63-84 and 2-82
INPO Significant Operating Experience Report 87-2, Inadvertent Draining of Reactor Vessel toSuppression Pool at B WRs, March 19, 1987.
INPO Significant Operating, Experience Report 82-4, Improper Alignment of Spray System ToResidual Heat Removal System, May 19, 1982.
INPO Significant Operating Experience Report 82-2, Inadvertent Reactor Pressure VesselPressurization, Apr. 28, 1982.
INPO Significant Event Report 7-91, Failure to Control Valve Lineup Status Resulting in aReactor Vessel Coolant Drain Down, April 2, 1991.
INPO Significant Event Report 19-90, Monitoring Plant Evolutions Using Inoperable ControlBoard Indications, November 21, 1990.
INPO Significant Event Report 5-90, Premature Lifting and Excessive Blowdown of ResidualHeat Removal Relief Valves, February 3, 1990.
INPO Significant Event Report 39-87, Undetected Loss of Reactor Coolant Due To Release ofDissolved Gases, December 29, 1
INPO Significant Event Report 4-86, Internal Flooding of An Emergency Core Cooling System(ECCS) Pump Room, January 6, 1986.
INPO Significant Event Report 37-83, Supplement 2, Inadvertent Draining of Reactor PressureVessel To Suppression Pool, October 9, 1985.
INPO Significant Event Report 37-83, Inadvertent Draining of Reactor Vessel to SuppressionPool, June 9, 1983.
NSAC/INPO Significant Event Report 85-81, Inadvertent Discharge From Reactor CoolantSystem to Containment Sump, September 25, 1981.
NSAC/INPO Significant Event Report 64-81, Reactor Coolant Leak Due To Technician's Error,August 14, 1981.
NSAC/INPO Significant Event Report 31-81, Inadvertent Containment Spray, April 29, 1981.
NSAC/INPO Significant Event Report 1-81, January 16,1981.
INPO Nuclear Network Entry WE 496, EAR TYO 90-005, RPV Was Pressurized at Low VesselMetal Temperature Condition During Refueling Outage, March 1, 1990.
NSAC Report 129
INPO SOER 85-1
INPO SER 9-86, 51-81, 72-84, 92-84, 9-86, 31-88
INPO Significant Operating Experience Reports
INPO Significant Operating Experience Report 87-2, Inadvertent Draining of Reactor Vessel ToSuppression Pool at BWRs, March 19, 1987.
INPO Significant Operating 'Experience Report 85-1, Reactor Cavity Seal Failure, January 10,1985.
INPO Significant Event Report 1-91, Spent Fuel Pool Overflow Events. January 4, 1991.
INPO Significant Event Report 17-90, Reactor Coolant System Temperature Below AnalyzedLimit for an Extended Time Period, October 24, 1990.
INPO Significant Event Report 15-89, Internal Flooding Resulting From Freeze Plug Failures,June 9, 1989.
INPO Significant Event Report 31-88, Reactor Cavity Seal Failure From Deflation andInadequate Design, October 27, 1988.
INPO Significant Event Report 3-88, Inadvertent Draining of Reactor Vessels Due ToProcedural Content and Usage Deficiencies, February 12, 1988.
INPO Significant Event Report 7-87, Pressurization of Vessel During Cold Shutdown, March 19,1987.
INPO Significant Event Report 4-87, Pipe Break and Condensate Storage Tank Draining, March9, 1987.
INPO Significant Event Report 40-86, Spent Fuel Pool Leakage, December 24, 1986.
INPO Significant Event Report 8-86, Inadvertent Drainage of Refueling Shield Tank, February24, 1986.
INPO Significant Event Report 41-85, Containment Spraying Events, September 19, 1985.
INPO Significant Event Report 38-85, Reactor Vessel Partially Drained Due To InadvertentActuation of the Automatic Depressurization System (ADS) While in Shutdown, August 12, 1985.
INPO Significant Event Report 92-84, Partial Drain of Spent Fuel Storage Pool To Spent FuelShipping Cask Pit Due To Deflated Seal, December 27, 1984.
INPO Significant Event Report 72-84, Reactor Cavity Seal Ring Failure, October 3, 1984.
INPO Significant Event Report 72-84, Supplement 1, Reactor Cavity Seal Ring Failure, April18, 1985.
INPO Significant Event Report 72-84, Supplement 2, Reactor Cavity Seal Failure, February 13,1986.
INPO Significant Event Report 63-84, Over pressurization of Reactor Vessel During ColdShutdown, Aug. 30, 1984.
INPO Significant Event Report 46-83, Inadvertent Initiation of Low Pressure Coolant Injection(LPCI), July 1, 1983.
INPO Significant Event Report 2-82, Cold Pressurization of Reactor Coolant System, January 7,1982.
NSAC/INPO Significant Event Report 76-81, Loss of Primary Coolant To reactor BuildingSump, September 25, 1981.
NSAC/INPO Significant Event Report 61-81, Inadvertent Spent Fuel Pool Overflow, August 12,1981.
NSAC/INPO Significant Event Report 51-81, Spent Fuel Pool Watertight Gate Seals, July 28,1981
INPO Nuclear Network Entry OE 4629, Low Level in Spent Fuel Pool due to Loss of Air toTransfer Canal Weir Gate Bladder, June 4, 1991.
INPO SER 17-90.
INPO SER 15-83
NSAC Report 129
INPO Significant Event Report 1-88
INPO Significant Event Report 21-86
INPO Significant Event Report 59-81
INPO Significant Event Report 31-83
INPO Significant Event Report 31-83
INPO Significant Event Report 5-86
INPO Significant Event Report 15-91, Fuel Mispositioning Events DL3 to Fuel Bundle SelectionErrors, June 11, 1991.
INPO Significant Event Report 10-88, Fuel Assembly Lifted With Upper InteMal, April 21,1988.
INPO Significant Event Report 5-86, Dropped New Fuel Assembly, January 15, 1986.
INPO Significant Event Rep~rt 21-86, Dropped Fuel Assembly, June 16, 1986.
INPO Significant Event Report 31-85, Inadvertent Fuel Bundle Movement, June 27, 1985.
INPO Significant Event Report 31-83, Irradiated Fuel Assembly Dropped From Fuel HandlingCrane, June 6, 1983.
INPO Significant Event Report 15-83, Fuel Handling Error, March 11, 1983.
INPO Significant Event Report 43-82, Fractured Fuel Assembly Guide Tubes, July 19, 1982.
INPO Significant Event Report 59-81, Dropped Fuel Assembly, August 11, 1981.
INPO Nuclear Network Entry OE 4167, Fuel Assemblies Withdrawn With Upper Intenals,October 5, 1990.
INPO Nuclear Network Entry OE 4112, Fuel Assemblies Withdrawn With Upper Internals -Update to OE's 4167, 4177, and 4187, October 26, 1990.
INPO Nuclear Network Entry OE 4113, Fuel Assemblies Withdrawn With Upper lnteMals -Update to OE4167(message replaced OE 4177), October 27, 1990.
INPO Nuclear Network Entry OE 4114, Fuel Assemblies Withdrawn With Upper Internals -Update to OE4167 and 4177(message replaced OE 4187), October 27, 1990.
The following public document, NEDO 33262, written by General Electric Company and its foreign affiliate, references dozens of documents from INPO and/or NSAC. NRC likely has these documents in its files. Under this FOIA I am requesting that NRC place these documents into its PDR for access by the public. The public needs these documents in order to assess NEDO-33262.
Submittal of ESBWR Licensing Topical Report NEDO-33262, ESBWR Human Factors Engineering Operating Experience Review Implementation Plan (OER), Revision 2.
ML081560316
2008-05-31
The following list of INPO, NSAC and NSAC/INPO documents is compiled from NEDO-33262. These documents must be placed in NRC’s PDR under this FOIA.
INPO SOER 88-3
INPO SOER 85-4
INPO SOER 87-2
INPO SOER 84-7
INPO Significant Operating Experience Reports
INPO Significant Operating Experience Report 84-7, Pressure Locking and Thermal Binding ofGate Valves, December 14, 1984.
INPO Significant Event Reports
INPO Significant Event Report xx-9 1, - In Preparation - Inventory Drain Down, 1991.
INPO Significant Event Report 26-89, Loss of Residual Heat Removal Capability Due ToCommon Mode Failure of Flow Control Valves, October 4, 1989.
INPO Significant Event Report 11-89, Inadvertent Introduction of Hydrogen Into The Instrumentand Station Air Systems, April 11, 1989.
INPO Significant Event Report 5-89, Lack of Control of Testing Disables or Challenges SafetySystems, March 3, 1989.
INPO Significant Event Report 36-88, Loss of Residual Heat Removal Due to Misleading VisualIndication of Water Level, November 30, 1988.
INPO Significant Event Report 35-87, Non-lsolable Reactor Coolant System Leak, November12,1987.
INPO Significant Event Report 3 5-86, Extended Loss of Shutdown Cooling due to Steam Bindingof Shutdown Cooling Pumps, October 24, 1986.
INPO Significant Event Report 31-86, Loss of Residual Heat Removal Flow Due To InadvertentDraining Of The Reactor Coolant System, September 3, 1986.
INPO Significant Event Report 23-86, Loss of Decay Heat Removal Due To Inadequate ReactorCoolant System Level Control, July 3, 1986.
INPO Significant Event Report 17-86, Loss Of Shutdown Co. , Flow, May 27, 1986.
INPO Significant Event Report 79-84, Loss Of Shutdown Cooling Due to Inaccurate Level Indication, November 14, 1984.
INPO Significant Event Report 71-84, Residual Heat Removal Pump Damage Caused ByOperation With Suction Valve Closed, October 2, 1984.
INPO Significant Event Report 60-83, Loss of Residual Heat Removal (RHR) Cooling DuringReactor Vessel Drain Down, August 30, 1983.
INPO Significant Event Report 59-83, Residual Heat Removal (RHR) Pump Suction ValveClosure Due To Control Circuitry Design, August 18, 1983.
INPO Significant Event Report 13-83, Unplanned Radioactive Release and Loss of ShutdownCooling, February 25, 1983.
NSAC/INPO Significant Event Report 95-81, Automatic Valve Closure Causing Loss ofShutdown Decay Heat Removal, November 25, 1981.
NSAC/1NPO Significant Event Report 91-81, Steam Voiding in the Reactor Coolant SystemDuring Decay Heat Removal Cooldown, October 6, 1981.
NSAC/INPO Significant Event Report 89-81, Level Instrumentation Oscillations Due ToReference Leg Flashing, October 23, 1981.
NSAC/INPO Significant Event Report 87-81, Inadequate Reactor Coolant System (RCS) WaterLevel Indication, October 19, 1981.
NSAC/INPO Significant Event Report 78-81, Erroneous Indication. Reactor Vessel LevelCauses Loss of RHR, October 1, 1981.
INPO Nuclear Network, WE 655 ENR PAR 90-061, Residual Removal Flow FluctuationsDuring Drawing of Vacuum in the Reactor Coolant System, September 19, 1990.
INPO SERS 42-81 and 5-89.
INPO SERS 17-88 and 36-87
NSAC Report. 146.
INPO/NSAC Significant Operating Experience Report 80-5, Potential Loss of Coolant Accident(LOCA) From A Single Electrical Failure, September 23, 1980.
INPO Significant Experience Report 11-88, Inadvertent Disablement of The Automatic StartCapability For All Site Diesel Generators, May 6, 1988.
INPO Significant Experience Report 25-85, Emergency Diesel Generator Failed To SupplyEmergency Bus Due To Non-emergency Trip, June 3, 1985.
INPO Significant Experience Report 73-83, Loss of All AC Power (Blackout), October 27, 1983.
NSAC/INPO Significant Event Report 56-81, Loss of Station and Reserve Auxiliary Power,August 56, 1981.
INPO SOERs 87-2 and 85-1
NSAC Reports 52 and 43
INPO SOER 82-4, and SER 31-81 and SER 5-90.
INPO SER 38-85
INPO SER 72-84
INPO SOER 85-1.
INPO SOER 82-2
NSAC REPORT 88
INPO SER 63-84 and 2-82
INPO Significant Operating Experience Report 87-2, Inadvertent Draining of Reactor Vessel toSuppression Pool at B WRs, March 19, 1987.
INPO Significant Operating, Experience Report 82-4, Improper Alignment of Spray System ToResidual Heat Removal System, May 19, 1982.
INPO Significant Operating Experience Report 82-2, Inadvertent Reactor Pressure VesselPressurization, Apr. 28, 1982.
INPO Significant Event Report 7-91, Failure to Control Valve Lineup Status Resulting in aReactor Vessel Coolant Drain Down, April 2, 1991.
INPO Significant Event Report 19-90, Monitoring Plant Evolutions Using Inoperable ControlBoard Indications, November 21, 1990.
INPO Significant Event Report 5-90, Premature Lifting and Excessive Blowdown of ResidualHeat Removal Relief Valves, February 3, 1990.
INPO Significant Event Report 39-87, Undetected Loss of Reactor Coolant Due To Release ofDissolved Gases, December 29, 1
INPO Significant Event Report 4-86, Internal Flooding of An Emergency Core Cooling System(ECCS) Pump Room, January 6, 1986.
INPO Significant Event Report 37-83, Supplement 2, Inadvertent Draining of Reactor PressureVessel To Suppression Pool, October 9, 1985.
INPO Significant Event Report 37-83, Inadvertent Draining of Reactor Vessel to SuppressionPool, June 9, 1983.
NSAC/INPO Significant Event Report 85-81, Inadvertent Discharge From Reactor CoolantSystem to Containment Sump, September 25, 1981.
NSAC/INPO Significant Event Report 64-81, Reactor Coolant Leak Due To Technician's Error,August 14, 1981.
NSAC/INPO Significant Event Report 31-81, Inadvertent Containment Spray, April 29, 1981.
NSAC/INPO Significant Event Report 1-81, January 16,1981.
INPO Nuclear Network Entry WE 496, EAR TYO 90-005, RPV Was Pressurized at Low VesselMetal Temperature Condition During Refueling Outage, March 1, 1990.
NSAC Report 129
INPO SOER 85-1
INPO SER 9-86, 51-81, 72-84, 92-84, 9-86, 31-88
INPO Significant Operating Experience Reports
INPO Significant Operating Experience Report 87-2, Inadvertent Draining of Reactor Vessel ToSuppression Pool at BWRs, March 19, 1987.
INPO Significant Operating 'Experience Report 85-1, Reactor Cavity Seal Failure, January 10,1985.
INPO Significant Event Report 1-91, Spent Fuel Pool Overflow Events. January 4, 1991.
INPO Significant Event Report 17-90, Reactor Coolant System Temperature Below AnalyzedLimit for an Extended Time Period, October 24, 1990.
INPO Significant Event Report 15-89, Internal Flooding Resulting From Freeze Plug Failures,June 9, 1989.
INPO Significant Event Report 31-88, Reactor Cavity Seal Failure From Deflation andInadequate Design, October 27, 1988.
INPO Significant Event Report 3-88, Inadvertent Draining of Reactor Vessels Due ToProcedural Content and Usage Deficiencies, February 12, 1988.
INPO Significant Event Report 7-87, Pressurization of Vessel During Cold Shutdown, March 19,1987.
INPO Significant Event Report 4-87, Pipe Break and Condensate Storage Tank Draining, March9, 1987.
INPO Significant Event Report 40-86, Spent Fuel Pool Leakage, December 24, 1986.
INPO Significant Event Report 8-86, Inadvertent Drainage of Refueling Shield Tank, February24, 1986.
INPO Significant Event Report 41-85, Containment Spraying Events, September 19, 1985.
INPO Significant Event Report 38-85, Reactor Vessel Partially Drained Due To InadvertentActuation of the Automatic Depressurization System (ADS) While in Shutdown, August 12, 1985.
INPO Significant Event Report 92-84, Partial Drain of Spent Fuel Storage Pool To Spent FuelShipping Cask Pit Due To Deflated Seal, December 27, 1984.
INPO Significant Event Report 72-84, Reactor Cavity Seal Ring Failure, October 3, 1984.
INPO Significant Event Report 72-84, Supplement 1, Reactor Cavity Seal Ring Failure, April18, 1985.
INPO Significant Event Report 72-84, Supplement 2, Reactor Cavity Seal Failure, February 13,1986.
INPO Significant Event Report 63-84, Over pressurization of Reactor Vessel During ColdShutdown, Aug. 30, 1984.
INPO Significant Event Report 46-83, Inadvertent Initiation of Low Pressure Coolant Injection(LPCI), July 1, 1983.
INPO Significant Event Report 2-82, Cold Pressurization of Reactor Coolant System, January 7,1982.
NSAC/INPO Significant Event Report 76-81, Loss of Primary Coolant To reactor BuildingSump, September 25, 1981.
NSAC/INPO Significant Event Report 61-81, Inadvertent Spent Fuel Pool Overflow, August 12,1981.
NSAC/INPO Significant Event Report 51-81, Spent Fuel Pool Watertight Gate Seals, July 28,1981
INPO Nuclear Network Entry OE 4629, Low Level in Spent Fuel Pool due to Loss of Air toTransfer Canal Weir Gate Bladder, June 4, 1991.
INPO SER 17-90.
INPO SER 15-83
NSAC Report 129
INPO Significant Event Report 1-88
INPO Significant Event Report 21-86
INPO Significant Event Report 59-81
INPO Significant Event Report 31-83
INPO Significant Event Report 31-83
INPO Significant Event Report 5-86
INPO Significant Event Report 15-91, Fuel Mispositioning Events DL3 to Fuel Bundle SelectionErrors, June 11, 1991.
INPO Significant Event Report 10-88, Fuel Assembly Lifted With Upper InteMal, April 21,1988.
INPO Significant Event Report 5-86, Dropped New Fuel Assembly, January 15, 1986.
INPO Significant Event Rep~rt 21-86, Dropped Fuel Assembly, June 16, 1986.
INPO Significant Event Report 31-85, Inadvertent Fuel Bundle Movement, June 27, 1985.
INPO Significant Event Report 31-83, Irradiated Fuel Assembly Dropped From Fuel HandlingCrane, June 6, 1983.
INPO Significant Event Report 15-83, Fuel Handling Error, March 11, 1983.
INPO Significant Event Report 43-82, Fractured Fuel Assembly Guide Tubes, July 19, 1982.
INPO Significant Event Report 59-81, Dropped Fuel Assembly, August 11, 1981.
INPO Nuclear Network Entry OE 4167, Fuel Assemblies Withdrawn With Upper Intenals,October 5, 1990.
INPO Nuclear Network Entry OE 4112, Fuel Assemblies Withdrawn With Upper Internals -Update to OE's 4167, 4177, and 4187, October 26, 1990.
INPO Nuclear Network Entry OE 4113, Fuel Assemblies Withdrawn With Upper lnteMals -Update to OE4167(message replaced OE 4177), October 27, 1990.
INPO Nuclear Network Entry OE 4114, Fuel Assemblies Withdrawn With Upper Internals -Update to OE4167 and 4177(message replaced OE 4187), October 27, 1990.
For your information, following is a letter that I sent INPO about eleven years ago; a letter that discloses an INPO practice of openly disclosing results of an INPO inspection of one of its members.
Robert H. Leyse
P. O. Box 2850
Sun Valley, ID 83353
August 29, 2008
Ronn K. Smith
INPO
Suite 100
700 Galleria Parkway, SE
Atlanta, GA 30339-5943
Dear Ronn:
In your letter of August 4, 2008, responding to my request for INPO SER 76-84, you refer to the confidentiality between INPO and it members as essential to allow the kind of extensive plant performance analysis that INPO provides.
On August 17, 2008, I agreed that the long-standing INPO policy is OK; however I suggested that your board should consider releasing documents that are aged and insensitive. I also suggested that when NRC references a specific INPO SER in its public documents, the specific INPO SER should then be released to the public.
Please refer to page 121 of Levy’s book, 50 years in Nuclear Power, published during 2007 by ANS. Maybe Levy is wrong, but he describes in some detail how INPO went to Chairman NRC in disclosing its relations with PECO. “INPO finally decided to issue a very strong letter recounting past and current failures by PECO … When the INPO letter was published, it had a great impact on PECO and its top level officers.”
If the NRC does not give me INPO SER 76-84 under FOIA, I’ll remind the Chairman NRC that INPO, according to Levy, does not consistently regard
confidentiality between INPO and it members as essential to allow the kind of extensive plant performance analysis that INPO provides.
Robert H. Leyse
P. O. Box 2850
Sun Valley, ID 83353
P. O. Box 2850
Sun Valley, ID 83353
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