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Category:QUALITY ASSURANCE PROGRAM
MONTHYEARML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A3161998-06-0202 June 1998 Rev 25 to QA Program for Station Operation. Draft of Program,Included ML17265A2631998-05-0505 May 1998 Rev 25 to QA Program. ML17264B1431997-12-17017 December 1997 Rev 24 to QAP for Stations Operation. Draft Copy of Program,Encl ML17264A7661996-12-13013 December 1996 Rev 23 to QA Program for Station Operation. ML17264A3091995-12-19019 December 1995 Rev 22 to QA Program for Station Operation. ML17263A8891994-12-21021 December 1994 Rev 21 to QA Program for Station Operation. ML17263A7561994-08-31031 August 1994 Rev 20 to QA Program for Operation. ML17263A6501994-05-31031 May 1994 Rev 20 to QA Program for Station Operation. ML17263A6231994-03-0202 March 1994 Rev 2 to QA Manual App C Inservice Pump & Valve Testings Program for 1990-1999. ML17309A5351993-12-31031 December 1993 Rev 19 to QA Program for Station Operation. ML17263A3511992-12-31031 December 1992 Rev 18 to QA Program for Station Operation. ML17262A7201991-12-31031 December 1991 Rev 17 to QA Program for Station Operation. ML17262A6381991-09-23023 September 1991 Rev 1 to QA Manual,App C, Inservice Pump & Valve Testing Program for 1990-1999 Interval. ML17262A2831990-12-31031 December 1990 Rev 16 to QA Program for Station Operation. ML17261A9041989-12-31031 December 1989 Rev 15 to QA Program for Station Operation. ML17309A4931989-07-20020 July 1989 Rev 0 to QA Program Ginna Station Inservice Insp Program for 1990-1999 Interval. ML17251A5231989-05-23023 May 1989 Rev 0 to App C Inservice Pump & Valve Testing Program for 1990-1999 Interval, QA Manual ML17261A7981988-12-31031 December 1988 Rev 14 to QA Program for Station Operation ML17251A9431988-02-19019 February 1988 Corrected Pages 5 & 53 to Rev 13 to QA Program ML17261A6991987-12-31031 December 1987 Rev 13 to QA Program for Station Operation. ML17261A5621987-07-24024 July 1987 Rev 11 to App B Ginna Station Inservice Insp Program for 1980-1989 Interval. ML17309A3901986-12-31031 December 1986 Rev 12 to QA Program for Station Operation ML17251A8461986-09-22022 September 1986 Rev 9 to QA Manual,App B Re Inservice Insp Program for 1980-1989 Interval ML17254A7431986-01-24024 January 1986 Rev 7 to QA Manual,App C, Ginna Station Inservice Pump & Valve Testing Program for 810101-891231 Period. ML17254A7141985-12-31031 December 1985 Rev 11 to QA Program for Station Operation. ML17254A4141985-06-30030 June 1985 Rev 10 to QA Program for Station Operation ML17254A4231985-01-10010 January 1985 Rev 6 to QA Manual,App C Re Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1989 ML17254A7911984-06-30030 June 1984 Rev 9 to QA Program for Station Operation. ML17255A7681984-04-0303 April 1984 QA Manual App B, Inservice Insp Program for 1980-1989 Interval. ML17255A5711983-11-29029 November 1983 Rev 4 to Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990 ML17255A5751983-10-14014 October 1983 Rev 7 to Inservice Insp Program for 1980 - 1989 ML17255A2981983-06-15015 June 1983 Rev 3A to App C to QA Manual Re Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990 ML17258A4581982-01-11011 January 1982 to QA Manual Re Inservice Insp Program for 1980-1989 Interval, App B ML17258A3291981-11-19019 November 1981 Proposed QA Manual,App B,Inservice Insp Program for 1980-89 Interval Reflecting Tech Specs Changes Re safety-related Snubbers.Safety Evaluation Encl ML17258A9801981-04-21021 April 1981 to App B of QA Program for Inservice Insp ML17258A8531981-02-0101 February 1981 to QA Program Manual,App C Re Inservice Pump & Valve Testing for 810101-901231 ML17250A7541980-11-0505 November 1980 Inservice Insp Program for 1980-89,Revision 4,App B to QA Manual ML17255A5171980-07-22022 July 1980 Rev 3 to QA Manual:App A,Quality & safety-related Listing & Diagrams ML17249A2901979-11-15015 November 1979 App C to QA Manual Re Revised Inservice Pump & Valve Testing Program for May 1979-Dec 1980 ML17244A5871979-07-0202 July 1979 Inservice Insp Program for 1980-89 (App B of QA Manual) ML17255A5761979-06-30030 June 1979 Rev 0 to Inservice Insp Program for 1980 - 1989 1999-03-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp. ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30
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QUALITY ASSURANCE MANUAL GINNA STATION ROCHESTER GAS 6 ELECTRIC CORPORATION EFFECTIVE DATEs RE Y.PAGE 1 OF February 1, 1981 TITLE: Appendix C-Ginna Station Inservice Pump and Valve Testing Program for the January 1, 1981 through December 31, 1990 Period PREPARED BYI I REVIEW APPROVED BY>SIGNATURE DATE z/n Ii Pro ram Table of Contents
Introduction:
Definitions:
Program: Discussion PVT 1.0 Scope and Responsibility PVT 2.0 Code Edition and Testing Interval PVT 3.0 Inservice Pump Testing Program PVT 4.0 Inservice Valve Testing Program PVT 5.0 Records 0 0 J QUALITY ASSURANCE MANUAL GINNA STATION TITLE:APPENDIX C Pump and Valve Testing Program DATE 2/1/81 PAGE 14 OF 42 52C 28 081 APV Valve I~Te Descri tion Control Room Ventilation Damper Note Test~Fre Stroke Q 082 083 084 085 086 112B APV APV APV APV APV LCV Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Emergency Makeup RNST to Charging Pump Stroke Q Stroke Q Stroke Stroke 9 Stroke Q Stroke Q 112C 427 430 431C LCV VCT Outlet AOV Letdown From Loop B PORV Reactor Coolant System Pressure Relief PORV Reactor Coolant System Pressure Relief Stroke Q 3 Stroke C/R 16 Stroke C/R 16 Stroke C/R 515 516 MOV MOV Pressurizer PORV Block Valve Pressurizer PORV Block Va lve 23 Stroke Q 23 Storke 9 624 625 626 HCV 1-B RHR HX Outlet HCV l-A RHR HX Outlet FCV RHR Loop Return Stroke 9 Stroke 0 Stroke Q Stroke C/R 700 MOV Suction Stop From Loop A to RHR Pumps r~
QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPFNDIX C Pump and Valve Testing Program DATE 2/1/81 PAGE 15 OF 42~52 C 28 701 MOV Valve N~Te Descri tion Suction Stop From Loop A to RHR Pumps Note Test Freer 8 Stroke C/R 704A 704B 720 MOV 10" Discharge to R Loop From RHR Pumps MOV Suction 1-A RHR Pump MOV Suction 1-B RHR Pump Stroke Q Stroke Q Stroke C/R 721 MOV 10" Disch to B Loop From RHR Pumps 8 Stroke C/R 738A 738B 825A 825R 826A 826B 826C 826D 836A 836B 85 OA'50B POV CC to 1-A RHR HX MOV CC to 1-B RHR HX MOV SI Pump Suction From RWST 9 MOV SI Pump Suction From RWST 9 MOV SI Pump Suction'rom BA Tank-MOV SI Pump Suction From BA Tank-MOV SI Pump Suction From BA Tank-MOV SI Pump Suction From BA Tank-HCV Spray Additive Tank Dis-17 charge HCV Spray Additive Tank Dis-17 charge MOV Sump B to RHR Pumps MOV Sump B to RHR Pumps Stroke Q Stroke 9 Stroke C/R Stroke C/R Stroke Stroke Stroke Stroke Stroke.Q Stroke Stroke Stroke 852A 852B MOV RHR Pumps to Reactor Vessel 18 Stroke C/R MOV RHR Pumps to Reactor Vessel 18 Stroke C/R 856 857A HOV RWST to RHR Pumps MOV Isola te 1B RHR HX From CS and SI Pum s Stroke C/P.Stroke QUALITY ASSUPANCE MANUAL GINNA STATION TITLE: APPENDIX C Pump and Valve Testina Program DATE 2/1/81 PAGE 26 OF 42 52C 28 storage tank to the safety injection and residual heat removal pumps.These valves will be stroked at cold shutdowns and re-fueling outages.Note 10-Valves 853A and 853B cannot be stroked during normal plant operation on a quarterly basis because this test require would pressurizing the RHR system to the primary system operation pressure.These valves will be stroked at refueling outages.Note ll-Valves 1076A, 1076B, 1080A, 1084A, 1084B, IV 3Ag IV 3B/IV 5A/IV 5B/IV 2A/IV 2BJ 1811Ag 1811BJ 6151'175'141~
7226'443 7444, 7445, 8418 and 8419 are considered passive valves which are not required to chanae position to acccomplish their specific function.Strokina these valves would serve no useful function and will therefore not be done as per I>IV-3700-1.
Note 12-Note 13-Valve 866A cannot be stroke tested during normal plant operation on a quarterly basis because this test would result in a sub-stantial radiation exposure to test per-sonnel.Stroke testing at this location resulted in approximately 400 mrem whole body exposure to the test personnel.
This valve will be stroked at cold shutdowns and refueling outages.Valves 867A, 867B, 878G, and 878J cannot be stroked during normal operation on a quarterly basis or at cold shutdown condition when the primary system is full.This test may only be done when the plant is in a refueling shutdown condition with a partially full primary system in order to prevent an over-pressurization.
Note 14-Valves 3516 and 3517 cannot be stroked during normal plant operation on a auar-terly basis because they are the main stean swina check stop valves.These valves are stroked during each plant startu
OUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX C Pump and Valve Testing Program DATE 2/1/81 PAGE 27 OF 42 52C Note l5-Category C Relief Valves shall be tested in accordance with the extent and fre-quency requirements of Paragraph DlV-3510 of Article INV of Section XI of the Code.Not e 16-Valves 430 and 431C are the power operated relief valves associated with the overpressurization system.These valves shall not be stroked quarterly as they need not be operable when the plant is at normal system pressure.Operability of these valves shall be verified as follows: (1)Full stroke exercising.during cool down prior to achieving water solid condition in the pressurizer and during cold shutdown prior to heat upi (2)Stroke timing to be performed as a minimum once each refuelinq cycle as a part of the channel calibration specified by Technical Specifications 4.16.1b.(3)Fail safe actuation testing is permitted by the code to be per-formed at each cold shutdown if valve cannot be tested during power operation.
(4)Technical specification 4.16.1a and 4.16.1c delineate additional re-quirements for operability verifi-cation of the PORV actuation channel and valve position.Note 17-Valve stroking will be normally ac-complished monthly, except during cold and refueling shutdowns, consistent with the monthly Technical Specification requirement.
Note 18-Valves 852A and 852B cannot be stroked during normal plant operation as these valves, when cycled, could subject the Residual Heat Removal System to a pressure in excess of its design pressure.These valves will be stroked at cold shutdowns and refueling outages.
0 QUALITY ASSURANCF MANUAL GINNA STATION TITLE: APPFNDIX C Pump and Valve Testing Program DATE 2/1/81 PAGE 28 OF 28 Note 19-Stroking Valves 5392 and 5393 during operation and cold shutdown would inter-rupt instrument air to containment, and be disruptive to air operated valves inside.These valves will be stroked at, refueling outages.Note 20-Valve 959 is normally closed and in the containment isolating position during normal operation.
These valves will be stroked at cold shutdown and refueling outages.Note 21-Valve 1786 is not required to function per FSAR Chapter 5 but valve receives a"T" Signal..Note 22-Category A valves 5869, 5870, 5878 and 5879 are normally closed and in the containment isolating position during normal operation.
Leak tightness of these valves is reverified following reclosure after each use in accordance with Section 4.4.2.4 of Technical Speci-fications.
The valves shall be stroked at least each cold shutdown.In addition, if the valves are opened for purging, they shall be stroked at least once each quarter during which they have been opened.Note 23-Valves 515 and 516 stroked quarterly except if already closed or during cold and refueling shutdowns.
PVT 5.0 Records 5.1 Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article INP-6000 of Section XI of the Code.5.2 Records for the Inservice Valve Testing Program shall be developed and maintained in accordance with Article It%'-6000 of Section XI of the Code.
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