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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211H4311999-08-27027 August 1999 Revised Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints ML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20210L1631999-08-0404 August 1999 Proposed Tech Specs,Ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification to 4 H Prior to Commencing Backfill Operation ML20212J3041999-06-22022 June 1999 Proposed Tech Specs Re Revised Surveillance Frequency & Action Times Reactor Trip & ESFAS ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20206N3691999-05-0606 May 1999 Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic ML20206G8361999-05-0303 May 1999 Proposed Tech Specs,Deleting &/Or Relocating Addl primary- to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206H0301999-05-0303 May 1999 Proposed Tech Specs Bases Page B 3/4 6-1,allowing Use of NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing ML20206G8811999-05-0303 May 1999 Proposed Tech Specs,Increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20203C8251999-02-0505 February 1999 Proposed Tech Specs Re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Operability ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20198J0971998-12-22022 December 1998 Proposed Tech Specs Bases Changes Re EDG Steady State Frequency to Be Incorporated Into TS During Implementation of Amends 216 & 197 ML20196K1971998-12-22022 December 1998 Rev 0 to NE-1176, North Anna Unit 1,Cycle 14 Startup Physics Tests Rept, Dec 1998 ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20195J4431998-11-18018 November 1998 Proposed Tech Specs Re Revs to Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9461998-11-10010 November 1998 Proposed Tech Specs,Clarifying Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20154P2831998-10-16016 October 1998 Marked-up & Typed Tech Spec Pages to Revise EDG Section to Be Consistent with Station Procedures Associated with Steady State Conditions & W NSAL 93-022,for 980728 Application for Amends to Licenses NPF-4 & NPF-7 ML20153H5341998-09-24024 September 1998 Proposed Tech Specs 3/4.5.1 Re Safety Injection Accumulator Boron Concentration Verification ML20236U8411998-07-28028 July 1998 Proposed Tech Specs 4.6.2.2.1 & 4.6.2.2.2,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20236U8711998-07-28028 July 1998 Proposed Tech Specs,Revising EDG Section to Be Consistent W/ Station Procedures Associated W/Steady State Conditions & W Nuclear Safety Advisory Ltr NSAL 93-022 ML20236U8651998-07-28028 July 1998 Proposed Tech Specs 3/4.1.2 & 3/4.5.5,re RWST & Boron Concentration Ph Range Bases Change to Address Discrepancies Between Previous NRC Issued Ser,Ts Bases & Applicable Sections of SRP ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236U8891998-06-25025 June 1998 Rev 0 to NE-1163, North Anna Unit 2 Cycle 13 Startup Physics Tests Rept ML20249C7211998-06-19019 June 1998 Proposed Improved Tech Specs for North Anna ISFSI ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML18152A3651998-03-25025 March 1998 Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220 ML20217E9011998-03-25025 March 1998 Proposed Tech Specs Re Configuration Risk Mgt Program for risk-informed Allowed Outage Times & Insp Frequency of EDGs ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20202E1551998-02-0909 February 1998 Proposed Tech Specs Re EDG Allowed Outage Time ML20202C5871998-02-0303 February 1998 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insps & Loop Flow Straightener Insps ML20202C3381998-02-0303 February 1998 Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20203G5191997-12-29029 December 1997 Ultrasonic Exam Technique for Detection of Microbilogically Induced Corrosion in North Anna Stainless Steel Service Water Piping ML20199G4161997-11-18018 November 1997 Revised Proposed TS Pages,Establishing 14 Day AOT Applicable Whenever EDG Is Inoperable ML20199H4001997-11-18018 November 1997 Proposed Tech Specs Permitting Quarterly Testing of Turbine Governor & Throttle Valves ML20199A1481997-11-0505 November 1997 Proposed Tech Specs Pages,Providing Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20198G5401997-08-31031 August 1997 Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997 ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20141F3741997-05-14014 May 1997 Proposed Tech Specs Revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided for TS 3/4.7.1.7 ML20137C8581997-03-18018 March 1997 Proposed Tech Specs Re Containment Gaseous & Particulate Radiation Monitors ML20134J4141997-02-0404 February 1997 Revised Pp of Proposed TS Changes Re Intermediate Range Trip Setpoints & Allowable Values for Units 1 & 2 ML20134F1231997-02-0303 February 1997 Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2 1999-08-04
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211D9201999-08-20020 August 1999 Revised Pages to Third Ten Year ISI Program & Relief Requests ML20195B5881999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna Unit 2 IST Program Plan for Pumps & Valves Second Insp Interval,901214-001214 ML20195B5691999-05-14014 May 1999 Rev 8,Change 2 to Vepc North Anna,Unit 1 IST Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20205P2511999-05-0101 May 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Program Plan for Third Insp Interval:Components & Component Supports ML20205P2341999-05-0101 May 1999 Rev 0 to Vepc North Anna Unit 1 ISI Program for Third Insp Interval Vol 1:ISI Program for Components & Component Supports for Interval 3 990501-090430 ML20205P2651999-02-0404 February 1999 Rev 0 to Vepc North Anna Power Station Unit 1 ISI Plan for Third Interval for Sys Pressure Tests ML20206N8851998-12-14014 December 1998 Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval ML20206N8711998-11-30030 November 1998 Rev 11,Vol I to ISI Plan for Second Insp Interval for Components & Component Supports ML20236H5311998-07-0101 July 1998 Draft Nuclear Control Room Operator Development Program NAPS Module NCRODP-78 Spent Fuel Dry Storage Cask System. Draft Lesson Plans & Job Performance Measures Included ML20236H5391998-06-0404 June 1998 Rev 1 to Procedure VPAP-0809, NUREG-0612 Heavy Load Program ML20236H5541998-06-0404 June 1998 Rev 5 to Procedure VPAP-0810, Crane & Hoist Program ML20206N8581998-04-30030 April 1998 Rev 5,Vol 1 to ISI Program for Second Insp Interval & Components & Component Supports,For 901214-010430 ML20236H5701998-04-0202 April 1998 Rev 8 to Procedure VPAP-1901, Industrial Safety & Health ML20236H5631998-02-10010 February 1998 Rev 11 to Procedure VPAP-0105, Fitness for Duty Program ML20210Q2051997-12-31031 December 1997 1997 Severe Accident Management Tabletop (Scenario 1) Drill Manual ML20199G5681997-06-30030 June 1997 Rev 5 to VPAP-2001, Station Planning & Scheduling. Even Numbered Pages of Incoming Submittal Not Included ML20210Q1991997-06-10010 June 1997 Rev 0 to VPAP-2604, Severe Accident Mgt Guideline (SAMG) Program Administration ML20199G4461996-08-29029 August 1996 Rev 28 to 1-MOP-6.90, Emergency Diesel Generator 1-EE-EG-1H. Page 35 of 72 in Attachment 4 of Incoming Submittal Was Not Included ML20236H5561996-08-0202 August 1996 Rev 3 to Procedure TRCP-0009, Instructional Staff Training & Qualifications ML20134J9601996-05-31031 May 1996 /Unit 2 Fuel Assembly Insp Program ML20138B5421996-05-16016 May 1996 Rev 7 to VPAP-2103, Odcm ML20217K4481995-10-31031 October 1995 Seismic Design & Evaluation Guidelines for DOE HLW Storage Tanks & Appurtenances ML20084U1811995-04-30030 April 1995 Rev 5 to Second 10-yr Interval ISI Program Plan ML20069A7971994-03-29029 March 1994 Second Interval ISI Plan, Rev 5 ISI Program,Rev 3 ML20065H9221993-11-30030 November 1993 ISI Program General Second Insp Interval ML20058N4911993-11-0505 November 1993 Rev 7 to North Anna Units 1 & 2 IST Program Plan Second Insp Interval 901214-001214 ML20092M9061991-09-0101 September 1991 Rev 2 to VPAP-2103, Odcm ML20081F3501991-05-28028 May 1991 Rev 1 to North Anna Unit 1 Inservice Insp Plan for Components & Component Supports,Second Insp Interval ML20082K8211991-05-0303 May 1991 Rev 1 to Station Administrative Procedure VPAP-2104, Radwaste Process Control Program ML18151A6551990-11-14014 November 1990 Revised Corporate Emergency Plan Implementing Procedures, Including Rev 0 to CPIP-1.0,CPIP-2.0,CPIP-2.1,CPIP-2.2, CPIP-2.3,CPIP-2.4,CPIP-2.5,CPIP-2.6,CPIP-3.0,CPIP-3.1 & CPIP-3.2 ML20058C1151990-10-17017 October 1990 Inservice Testing Program Plan for North Anna Unit 1 ML20065P2741990-09-30030 September 1990 Rev 1 to Vol 1 of VEPCO North Anna Power Station Unit 2 Inservice Insp Plan for Second Insp Interval:For Components & Component Supports 901214-001214 ML20065P2711990-09-30030 September 1990 Vol 1,Rev 0 to VEPCO North Anna Power Station Unit 1 Inservice Insp Plan for Second Insp Interval:For Components & Component Supports Dec 1988 - Dec 1998 ML20058G0551990-08-31031 August 1990 Inservice Insp Program for Second Insp Interval,Vol 1,Inservice Insp Program for Components & Component Supports ML20055D4931990-06-14014 June 1990 Rev 6 to VEPCO North Anna Power Station Unit 1 Inservice Testing Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20055D4941990-06-14014 June 1990 Rev 6 to VEPCO North Anna Power Station Unit 2 Inservice Testing Program Plan for Pumps & Valves Second Insp Interval 901214-001214 ML20043B1091990-04-27027 April 1990 Rev 0 to Station Administrative Procedure VPAP-2103, Odcm. ML20043B1111990-04-27027 April 1990 Rev 0 to Station Administrative Procedure VPAP-2104, Radwaste Process Control Program. ML20248E9231989-10-0303 October 1989 Inservice Testing Program Plan for Pumps & Valves First Insp Interval 801214 - 901214, Rev 5 ML20248E9201989-10-0303 October 1989 Inservice Testing Program Plan for Pumps & Valves First Insp Interval 780606 - 901214, Rev 5 ML20197F1261988-03-31031 March 1988 Rev 0 to Inservice Insp Program Plan for Second Insp Interval,Vol 1,Inservice Insp Program Plan for Components & Component Supports,880606-980606. W/92 Oversize Drawings ML20235U3391987-06-12012 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 1.00 to 1-ES-3.1, Post-STGR Cooldown Using Backfill (W/No Attachments) & Rev 1.00 to 1-EP-0, Reactor Trip or Safety Injection (W/No Attachments). Related Info Encl ML20215K2681985-12-19019 December 1985 Offsite Dose Calculation Manual,North Anna Power Station Units 1 & 2 ML20215K2731985-11-27027 November 1985 Process Control Program,North Anna Power Station Units 1 & 2 ML20108A1041985-03-0404 March 1985 Proposed Methodology for Implementing Mechanical Cleaning of Svc Water Piping & Repair of Svc Water Isolation Valves ML20108B5801985-02-28028 February 1985 VEPCO Proposed Program,Mechanical Cleaning & Valve Repair Svc Water Sys,North Anna Power Station,Feb 1985. W/One Oversize Drawing.Aperture Card Available in PDR ML20112G3771984-11-15015 November 1984 Emergency Exercise 841115,Exercise Manual ML18141A5301984-03-0101 March 1984 Control Room Design Review Program Plan for North Anna & Surry Power Stations, in Response to Suppl 1 to NUREG-0737 ML20079L5361983-12-21021 December 1983 Public Version of Rev 5 to Emergency Plan Implementing Procedure EPIP-3.04, Activation of Emergency Operation Facility ML18142A1371983-09-15015 September 1983 Procedure 1-OP-4.19, Receipt & Storage of Spent Fuel TN-8L Shipping Cask,Unloading & Handling Procedures. 1999-08-20
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2-AP-22.5 Page 1 of 5 5
11-29-79
. . . 7N VIRGINIA ELECTRIC AND P0 tier C0}!PA'.T NORTH ANNA P0k7.?, STATION UNIT NO. 2 PLACING 2-Fk'-P-2 IN SERVICE TO FEED STEA.'i GENERATORS 2-RC-E-1B AND 2-RC-E-1C FIFERENCES:
- 1. T.S. 3.7.1.2, 3.7.1.3
- 2. 12050-FM-74A
- 3. 12050-LSK-5-13A, B and C
- 4. 12050-ESK-5AA, 5AB, 6PR, and 6CL
- 5. Final Safety Analysis Report h
REV. PAGE DATE APPROVAL
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REC 0!DfEND APPROVAL: /w //, . j n :V il APPROVED BY: \9:
CHAIR'M _jTATION NCCLEAR SAFETY Cw,G AND OPI?.ATING CC?ctITTEE l t
DATE: I1-09 '
SAFETY RELATED
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. _ _ . . , ..__._-.1 2- AP-22.5 Page 2 of 5 11-29-79 1.0 Purnose 1.1 This procedure provides i=cediace and lodg ter:n operator actions to be taken in 2-W-P-2 in service to as a steam generators feed source to 2-RC-E-1B via the MOV header and to 2-RC-E-IC via the HCV Header. .
2.0 Indications 2.1 Abnormal steam generatc,: levels.
2.2 Abnormal auxiliary feedwater flows.
3.0 Probcble Cause 3.1 Loss of one or more auxiliary feedwater pumps.
3.2 Secondary coolant breaks on the secondary side of a steam h
generator.
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- 2-AP-22.5 Page 3 of 5 11-29-79 4.0 Icunediate Operator Actions 4.1 None m
9
& 2-AP-22.5 Page 4 of 5 11-29-79 Initials 5.0 long Term Operator Action NOTE: If a stean generator is dry, depressurize the primary systems to less than 16005 across the tube sheet and then cooldown and depressurize the primary aysten using the other operable steam generators.
If all three steam generators loosing level together, feed and bleed all three steam generators and increase levels very slowly. Reduce primary heat sources to a minimum by securing 2 reactor coolant pumps.
NOTE: When level in emergency condensate storage tank reaches 9 feet (37.3% as read on LI-CN-200 in control room) or when suction pressure to aux feed water pumps reaches 4 psig, commence filling the emergency condensate storage tank.
5.1 Verify valve checkoff sheet 2-OP-31.2A is completed.
5.2 Verify steam generator level indication is available.
5.3 Verify electrical power is available for MOV and/or HCV opera-tion. (Valves will have to be operated manually if power is h not available).
5.4 Unlock and open 2-FW-317 if it is desired to feed 2-RC-E-1B via MOV FW200B.
5.5 Unlock and open 2-FW-157 if it is desired to feed 2-RC-E-IC via HCV FW200C.
5.6 Isolate tne steam supply from affected steam generators to 2-FW-P-2 by closing 2-MS-13 from 2-RC-E-IA 1-MS-57 from 2-RC-E-1B, or 2-MS-95 from 1-RC-E-IC. .-
- =v NOTE: Steam pressure will be higher in steam generators with lower levels. If Safety Injection has not occurred limit steam line differential pressure to less than 100# AP or safety injection will occur.
5.7 Open TV MS 211A or B to start 2-FW-P-2.
5.8 Regulate MOV FW 200D to control level in 2-RC-E-1A, MOV FW 2003
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to control level in 2-RC-E-1B and HCV FW 200C to control level in 2-RC-E-1C. l 1
l 1
1 2-AP-22.5 Page 5 of 5 11-29-79 Initials 5.0 Lone Term Ooerator Action (cont.)
5.9 Make-up to 2-CK-TK-1 as required.
NOTE: Return auxiliary feedwater system to normal from this lineup by 2-AP-22.6.
Completed By:
Date:
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