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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20115H7681996-07-17017 July 1996 Special Rept:On 960603,Unit 2 Vent Stack Wide Range Gas Radiation Monitor Sys Removed from Svc for Planned Mod.Sys Subsequently Returned to Svc on 960701.Mod Replaced ML20115H0111996-07-17017 July 1996 Special Rept:On 960703,main Stack Wide Range Gas Radiation Monitor Sys Removed from Svc for Planned Mod.Sys Expected to Be Returned to Svc by 960830 After Mod Work Completed ML20111B4751996-05-10010 May 1996 Special Rept:On 960422,vent Stack Wide Range Gas Radiation Monitor Sys Was Removed from Svc for Planned Mod.Field Survey Teams Would Be Dispatched to Monitor Radioactive Effluents as Defined in Plant Emergency Plan ML20092M1751995-09-22022 September 1995 Special Rept:On 950726,valid Failure of E-3 EDG Occurred Due to Dead Spot on Potentiometer Which Affected E-3 EDG Controller Output signal.E-3 EDG Returned to Operable Status Following Motor Operated Potentiometer Replacement ML20087H2511995-08-14014 August 1995 Special Rept:On 950726,non-valid Failure of E-3 EDG Occurred Due to Dead Spot on E-3 EDG Motor Operated Potentiometer (MOP).E-1 & E-3 EDG Mops Will Be Replaced W/New Type Mop During Future Mod Outages ML20086R5171995-07-25025 July 1995 Special Rept:On 950630,determined That Number 12 Cylinder on E-1 D/G Had Lower than Normal Operating Temps During Surveillance Test.Caused by Failure of Fuel Oil Injector Pump.Injector Pump Replaced & Satisfactorily Tested ML20078C1701994-10-24024 October 1994 Special Rept:On 940924,valid Failure of E-2 EDG Occurred. Caused by Problem w/4 Kv Breaker.Breaker Incorporated Into Preventive Maint Program to Replace Grease ML20071Q5771994-08-0202 August 1994 Special Rept:On 940706,valid Failure of E-4 Emergency Diesel Generator Occurred.Caused by Solenoid Valve Spuriously Sticking.Valves Replaced ML20064C3011994-02-28028 February 1994 Special Rept:On 940211,non Valid Failure of EDG E-4 Occurred When Voltage Shutdown Button Inadvertently Bumped.Maint Insp Initiated to Determine If Generator Damage May Have Occurred Due to Event.Remaining EDGs Were Operable ML20059A8271993-10-22022 October 1993 Special Rept:On 931012,valid Failure of EDG E-2 Occurred During Routine Monthly Test.Edg E-2 Declared Inoperable Due to High Fuel Oil Differential Pressure Condition.Edg E-2 Fuel Oil Filters Replaced ML20056G8701993-08-27027 August 1993 Special Rept:On 930803,discovered That Cylinder on 2-EDG Lower than Normal Operating Temps.Caused by Fuel Pin on Cylinder Injector Pump Not Fully Engaged ML20079L6291991-10-30030 October 1991 Special Rept:On 910916 & 23,cable Spreading & Computer Room CO2 Fire Protection Sys Out for Svc for More than 14 Days. Caused by Need to Provide for Worker Safety During Mod Work. Fire Detectors Verified Operable & Firewatch Stationed ML20077P9701991-08-15015 August 1991 Special Rept:On 910714,diesel Driven Fire Pump Out of Svc for More than Seven Days Due to Annual Preventative Maint Activities.Preventative Maint Completed & Pump Returned to Svc.Operability Testing Completed Satisfactorily on 910723 ML20064A4651990-08-27027 August 1990 Special Rept:On 900802,diesel-driven Fire Pump Declared Inoperable During Testing Due to Engine Overheating.Caused by Silt & Marine Biotic Life Plugging Y Strainer in Cooling Line.Strainer Cleaned & Retested ML20059B8991990-08-21021 August 1990 Special Rept:On 900802,diesel Driven Fire Pump Declared Inoperable During Testing Due to Engine Overheating.Diesel Generator E-2 Returned to Operable Status & motor-driven Fire Pump Declared Operable on 900807 ML20058N6651990-08-0808 August 1990 Special Rept:On 900802 & 07,diesel Driven & Motor Driven Fire Pumps,Respectively,Declared Administratively Out of Svc.Caused by Engine Overheating & Diesel Generator (DG) E-2 Out of Svc.Local Fire Depts Notified & DG E-2 Repaired ML20245H4461989-08-10010 August 1989 Ro:On 890710,diesel Driven Fire Pump Out of Svc for More than 7 Days.Caused by Disconnected Coolant Hose from Engine Block During Test,Draining Coolant from Engine & Heat Exchanger.Insp & Repair of Engine Performed ML20245J5571989-05-0101 May 1989 Ro:On 890331,motor Driven Fire Pump Out of Svc in Excess of 7 Days.Caused by Removal of Pump from Svc on 890324 to Allow Implementation of Electrical Mods.Diesel Driven Fire Pump Verified Operable & Tested Every 72 H ML20245B3391989-04-14014 April 1989 Special Rept:On 890303,seismic Monitoring Instruments Inoperable for More than 30 Days.Caused by Triaxial Accelerometer Cables Picking Up Electrical Noise Which Caused Spurious Alarms.Noise Filters Will Be Installed ML20195E5011988-11-0303 November 1988 Special Rept:On 881020,diesel Driven Fire Pump Failed to Start Automatically During Surveillance Test.Caused by Inadequate Test.Diesel Driven Fire Pump & auto-start Feature Tested & Rev of Fire Pumps Surveillance Tests in Process ML20205H2561988-10-21021 October 1988 Ro:On 881020,diesel Driven Fire Pump Failed to Start Automatically During Performance of Surveillance Test.Cause Under Investigation.Diesel Driven Fire Pump Subsequently Tested Successfully & Returned to Svc ML20154A7261988-09-0202 September 1988 Special Rept:On 880726,motor-driven Fire Pump Out of Svc for More than 7 Days.Caused by Action Taken to Allow Cleaning & Insp of of E-42 4 Kv bus.Motor-driven Fire Pump Restored to Operable Status on 880821 ML20154A9611988-09-0101 September 1988 Special Rept:On 880822,discharge Pressure Lost While Motor Driven Fire Pump in Operation.Caused by Crack That Formed in Column Pipe Flange Area Where It Bolts to Pump.Motor Driven Pump Removed from Pump Structure,Disassembled & Inspected ML20195B8501988-06-15015 June 1988 Special Rept:On 870215,packing Leak from RCIC Outboard Isolation Valve Reported to Operating Shift.Caused by Steam Leak.New Grease Replaced.On 870915,degradation to Motor Operator & Field Wiring Discovered.Components Replaced ML20154P3591988-05-27027 May 1988 Special Rept:On 880415,carbon Dioxide Fire Suppression Sys Taken Out of Svc for More than 14 Days.Caused by Continuous Fire Watch Required in Cable Spreading Room During Repair of Hole in Floor.Hole Repaired & Subj Sys Returned to Svc ML20153B4681988-03-16016 March 1988 Revised Special Rept Re Diesel Driven Fire Pump out-of-svc for More than Tech Spec Limit of 7 Days.On 871111,diesel Driven Fire Pump Declared Inoperable.Probably Caused by Battery Failures.Surveillance Procedure Revised ML20153B3101988-03-16016 March 1988 Special Rept:On 880302,E-224 440-volt Emergency Load Ctr Supply Breaker Tripped Open,Removing Power Supply for Motor Driven Fire Pump.Caused by Failure of Undervoltage Relay on E-22 Bus.Failed Relay Replaced ML20196G5521988-03-0707 March 1988 Ro:On 880302 & 05,motor Driven Fire Pumps Declared Inoperable.Caused by Level in Storage Tank Dropped Due to Oil Being Transferred from Storage to Day Tank.Diesel Fuel Added Storage Tank to Bring Level Above 300 Gallon Limit ML20147G1531988-03-0303 March 1988 Ro:On 880302,both Fire Pumps Became Inoperable When Breaker E-224 for Motor Driven Fire Pump Tripped.Diesel Driven Fire Pump Taken Out of Svc for Maint on 880301.Caused by Failure of Bus E-22 Undervoltage Relay.Temporary Jumpers Installed ML20147C2081988-01-11011 January 1988 Special Rept:On 871216,planned Release of Liquid Radwaste from Laundry Drain Tank B Made W/O Being Treated as Described in Limiting Condition of Operation 3.8.B.4.Caused by Procedural Deficiency.Procedure Revised ML20238C5071987-12-21021 December 1987 Special Rept:On 871111,diesel-driven Fire Pump Failed Surveillance Test & Declared Inoperable.Cause Unknown.Four Sets of Cells for Two Batteries Replaced & Charged W/Portable Charger.Surveillance Test Procedure Revised ML20236K9111987-08-0303 August 1987 Ro:On 870731,motor Driven Fire Pump Automatically Started on Decreasing Header Pressure at 140 Psig.Caused by Personnel Digging in Yard Directly Behind Radwaste Bldg.Affected Portion of Fire Header Isolated for Repair of Leak ML20214W7691987-06-0505 June 1987 Special Rept:On 870428,bus E22 Deenergized to Perform Series of outage-related Mods,Causing Motor Driven Fire Pump to Be out-of-svc for More than 7 Days,In Violation of Tech Specs. Motor Driven Fire Pump Restored to Svc on 870515 ML20214U0341987-06-0404 June 1987 Special Rept:During Update of Safe Shutdown Data Base, Conditions Re Unencapsulated Cables in Fire Areas Identified as Reportable Per Confirmatory Action Ltr 86-07 & App R. Caused by Exclusion from Previous Analysis.Fire Watch Begun 05000000/LER-1986-009, Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised1986-04-14014 April 1986 Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised ML20199F4401986-03-27027 March 1986 Special Rept:On 860216,during Cold Shutdown,Condensate Storage Tank (CST) Filled & Overflowed Into CST Moat & Outside Moat.Caused by Blown Fuse Resulting in Removal of Power from Hotwell Level Controllers.Fuse Mods Considered ML20093F1951984-09-21021 September 1984 RO MM-3-03:on 840823,routine Surveillance Testing Indicated Three Moisture Sensors in Recirculation Sys Moisture Monitoring Sys Functioning Improperly.Cause Not Determined. Hourly Monitoring Being Performed ML20096F4901984-08-14014 August 1984 RO-MM-3-02:on 840715,surveillance Test Revealed Malfunctioning of Moisture Sensors in Recirculation Sys Moisture Monitoring Sys.Cause Unknown.Hourly Monitoring of Drywell Sump Collection Initiated Until Next Outage ML20094F4451984-07-23023 July 1984 RO MM-3-01:on 840622 & 25,moisture Sensors in Recirculation Sys Moisture Monitoring Sys Functioned Improperly.Cause Unknown.Drywell Sump Collection Sys Monitored Hourly Until Next Outage ML20083Q0231984-03-23023 March 1984 Ro:On 840224,during Verification of Moisture Monitoring Sys,Point 7 Failed.Cause Will Be Determined During Next Outage W/Drywell Deinerted.Drywell Sump Collection Sys Will Be Monitored Hourly ML20083P9631984-03-12012 March 1984 Ro:On 840209,CO2 Fire Protection Sys,Serving Cable Spreading Room & Computer Room,Declared Inoperable.Caused by Ground in One of Two Cables from Smoke Detector Control Panel.Cables Replaced & Sys Available for Svc ML20083P8201984-03-0505 March 1984 Ro:On 840125,moisture Sensor in Recirculation Sys Moisture Monitoring Sys Functioned Improperly & Sys Declared Inoperable.Caused by Failed Techmark Limited Moisture Sensor Circuit Card.Sensor Replaced ML20080A7731984-01-16016 January 1984 Ro:On 831128,from 830830-1128,seismic Monitoring Sys Inoperable.Caused by Personnel Oversight.Startup check-off List Modified to Require Maint Request ML20069L3171983-04-11011 April 1983 Corrected RO 3-83-11/1P:on 830407,full-in Position Signal Jumpered Into Probe Buffer Cards.Control Rods Could Have Been Withdrawn W/O Initiating Single Control Rod Interlock. Caused by Personnel Error.Jumpers Removed ML20079L2681983-02-15015 February 1983 RO 3-83-08/1P:on 830214,three of Eight MSIVs Failed to Pass Tech Spec Limit of 11.5 Scfh & Containment Isolation Valve Mo 2-74 Failed Leak Rate Test.Caused by Abnormal Wear of Valve Internals.Valves to Be Inspected & Repaired ML20066A5811982-10-28028 October 1982 RO 2-82-36/1P:on 821024,71J Safety Relief Valve Opened When Pressure Reached 832 Psig.Cause Unknown.Valve to Be Sent to Vendor.Two Vacuum Breakers Replaced.Fatigue Analysis Determined Downstream Piping Not Overstressed ML20066A9391982-10-25025 October 1982 Ro:Response Spectrum Analyzer Component of Seismic Monitoring Sys Intermittently Inoperable Since 820909.Caused by Malfunctioning Power Control Card.Card Will Be Replaced. Component to Be Returned to Svc by 821130 ML20058B7101982-07-14014 July 1982 Ro:On 820619,during Scheduled Loss of Power Test on Unit 2, Inadvertent Startup of ECCS on Unit 3 Initiated While at Full Power.Caused by Defective Elma Dc Power Supply to 24-volt Dc Logic Circuit ML20055B5181982-07-13013 July 1982 RO Advising That Triaxial Accelerometer Devices in Reactor Core Isolation Cooling Sys Pump Room Inoperable for More than 30 Days.Replacement Detector to Be Installed by 820831 ML20126L1441981-05-20020 May 1981 RO 2-81-32/1P:on 810520,w/units in Shutdown Condition, re-evaluation of Concrete Block Walls Identified Four Walls Unstable Under Effects of Tornado Depressurization & Cardox Injection.Caused by Const or Design Error 1996-07-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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PHILADELPHIA ELECTRIC COMPANY 2301 M'ARKET STREET
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PHILADELPHI A, PA.19101 M COM (215)841 4o00 February 18, 1977 l 4?-M *'Iy Mr. Victor Stello, Jr. '
N Director Division of Operating Reactors (Tj", [f
- {. *!
Office of Nuclear Reactor Regulations !(-. f[C 2 3 lW' .i U. S. Nuclear Regulatory Commission - u,s.sexws W#
4 WN Washington, DC 20555
' sy g
Dear Mr. Stello:
/77T@/
4
Subject:
Environmental Deviation s-The following deviation was reported to Mr. Walt Baunack, Office of Inspection and Enforcement, Region 1, United Uthtes Nuclear Regulatory Commission on February 9, 1977. ,
Reference:
License Number DPR-44/56 Appendix B Environmental Technical Specifications:
Section 2.2.2 Report No.: 50-277/278-77-6 ?
Report Date: February 18, 1977 Deviation Date: February 8, 1977 .
Facility: Peach Bottom Atomic Power Station Units 2 & 3 : - ~
R. D. 1, Delta, PA 17314 Identification of Deviation:
The total suspended solids for the Unit 2 and 3 sewage plant effluent exceeded the Environmental Technical Specification 2.2.2 limith Conditions Prior to Deviation:
.=
The sewage plant was in the automatic mode.
Description of Deviation:
The daily turbidity measurement of the sewage plant effluent .
was high and a gravimetric analysis for total suspended solids gras run, The net total suspended solids for the sewage plant was 87.6 pp'ttgreater than the river sample. s i
- i. s
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L G401090308 770218 4 PDR ADOCK 05000277 S ""
l vm i SENT REGION _-/ ~ 3.s.a
Mr. Victor S - o, Jr. , 50-277/278-77-6 Fsbrusry 18, 1977 Paga 2 '
. . I Designation of Apparent 'Ciuse:
The sample was taken during a period of high flow into the sewage plant. The greater than no. mal water input came from increased sanitary facility usage caused by the Unit 3 Refueling Outage. High flow carried solids over from the aeration tank into the chlorine contact tank and from there into the effluent. ' The follow-up sampic, taken following cleaning of the chlorine contact tank and after the flow had returned to normal, was within Technical Specification limits. ,
Analysis of Deviation:
Because the sewage plant effluent was being diluted by a facter of 50,000 with circulating water flow, the suspended solids level of.the circulating water leaving the discharge canal was not affected.
Iterofore, the environmental. impact was minimaI.,
Corrective Action:
i The chlorine contact tank was cleaned and the settled solids were removed. The Mechanical Engineering Division has been requested to investigate the installation of surge equalization basins as recommended by our censultant. Installation of an equalization system would help to prevent hydraulic surges,that cause suspended solids to be carried over into the effluent.
Failure Data:
50-277/278-77-4, 50-277/278-77-1, 50-277/278-76-44, 50-277/278-76-37, 50-277/278-76-34, 50-27?/278-76-28, 50-277/278-76-26, 50-277/278-76-7, 50-277/278-76-6. .
i Very truly yours,
/
M. J. Cooney S perintendent Generation Division-Nuclear 4
l l '
cc: Mr. J. P. O' Reilly Director, Region 1 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 I
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