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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D6351999-10-0808 October 1999 Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves ML20211C2141999-08-19019 August 1999 Proposed Tech Specs,Revising Heatup & Cooldown Curves in TS 3/4.4.9, RCS P/T Limits ML20206T2141999-05-17017 May 1999 Proposed Tech Specs Section 3.7.1.3, CST - LCO, Revising Required Min Contained Volume of CST from 172,000 Gallons of Water to 179,850 Gallons of Water ML20212H4651999-05-0404 May 1999 Amend 17 to Training & Qualification Plan ML20197H5521998-12-0404 December 1998 Proposed Tech Specs Revising Testing Methodology Used by Vcns to Determine Operability of Charcoal Adsorber in ESF Air Handling Units ML20153C4001998-09-18018 September 1998 Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP ML20202C3271998-08-31031 August 1998 Amend 16 to Training & Qualification Plan ML20236G7581998-07-0101 July 1998 Proposed Tech Specs 4.7.7.e,removing Situational Surveillance Requirement of During Shutdown Following Specified Surveillance Interval of at Least Once Per Eighteen Months ML20153F9241998-04-23023 April 1998 Change A,Rev 10 to FEP-1.0, Fire Emergency Procedure Selection ML20153G7081998-03-30030 March 1998 Rev 2 to FEP-4.1, Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire in Control Building ML20153F9691998-03-25025 March 1998 Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire ML20153F9341998-03-23023 March 1998 Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire ML20202G6891998-02-0909 February 1998 Proposed Tech Specs Requesting Removal of Table 4.8-1, Diesel Generator Test Schedule & SR 4.8.1.1.3,Repts ML20203H5741998-02-0505 February 1998 Rev 31,change C to EPP-002, Communication & Notification ML20203H5981998-02-0202 February 1998 Rev 3 to EPP-105, Conduct of Drills & Exercises ML20203H5831998-01-27027 January 1998 Rev 5 to EPP-103, Emergency Equipment Checklist ML20153F9461997-10-22022 October 1997 Rev 2 to FEP-2.1, Train a Shutdown from Hot Standby to Cold Shutdown Due to Fire, Change B ML20153F9511997-10-22022 October 1997 Rev 2 to FEP-3.0, Train B Plant Shutdown to Hot Standby Due to Fire, Change B ML20153F9931997-10-22022 October 1997 Rev 2 to FEP-4.0, Control Room Evacuation Due to Fire, Change D ML20210V2481997-06-30030 June 1997 Amend 15 to Training & Qualification Plan ML20217H3521997-06-16016 June 1997 Amend 14 to, Training & Qualification Plan ML20141K2481997-05-21021 May 1997 Proposed Tech Specs Revising Testing Methodology Utilized by VCSNS to Determine Operability of Charcoal Adsorbers in Emergency Safeguards Features Air Handling Units ML20140C1071997-03-26026 March 1997 Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves ML20140C1401997-03-26026 March 1997 Proposed Tech Specs Re Change to Core Alteration Definition ML20140C0641997-03-26026 March 1997 Proposed Tech Specs 3.8.1.1 Re AC Sources - Operating ML20137F8501997-02-0404 February 1997 Change E,Rev 7 to Inservice Testing of Pumps Second Ten Year Interval RC-96-0229, Startup Report for VC Summer Nuclear Station Power Uprate1996-09-23023 September 1996 Startup Report for VC Summer Nuclear Station Power Uprate ML20138H7191996-09-0606 September 1996 Rev 22 to ODCM for VC Summer Nuclear Station ML20134J9741996-06-0505 June 1996 V C Summer Fuel Assembly Insp Program ML20107G3511996-04-16016 April 1996 Proposed Tech Specs 3/4.6 Re Containment Sys,Per App J, Option B ML20138H7141996-03-25025 March 1996 Rev 21 to ODCM for VC Summer Nuclear Station ML20101E6461996-03-19019 March 1996 Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR ML20097F4721996-02-10010 February 1996 Proposed Tech Specs,Revising Testing Methodology Utilized to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20096F0211996-01-18018 January 1996 Proposed Tech Specs,Lowering RWCU Isolation Setpoint from Reactor Low Level to Reactor low-low Level ML20095E6541995-12-0808 December 1995 Proposed Tech Specs,Consisting of Change Request 95-07 Re ECCS Pump Testing ML20095A8061995-12-0404 December 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 Correction of Bases 3/4 11-1 ML20094N8881995-11-21021 November 1995 Proposed Tech Specs,Allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days ML20094L3531995-11-14014 November 1995 Proposed TS 3/4.8.4.2,removing MOVs Thermal Overload Protection & Bypass Devices ML20094E4111995-11-0101 November 1995 Proposed Tech Specs,Consisting of Change Request 95-01, Permitting VCSNS to Operate at Uprate Power Level of 2900 Mwt Core Power When Unit Restarted After Ninth Refueling Outage ML20093F6131995-08-31031 August 1995 Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval ML20092A2371995-08-31031 August 1995 Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20 ML20091L4541995-08-18018 August 1995 Proposed Tech Specs for Uprate Power Operation ML20087F8551995-08-11011 August 1995 Proposed Tech Specs Re Rev to TS Change 95-02 Concerning PORVs & Block Valves ML20087A2601995-07-28028 July 1995 Proposed Tech Specs Re TS 3/4.3.2,ESFAS Instrumentation,Sr 4.3.2.1 Being Revised to Exclude Requirement to Perform Slave Relay Test of 36 Containment Purge Supply & Exhaust Valves on Quarterly Basis While Plant in Modes 1,2,3 or 4 ML20086C0311995-06-30030 June 1995 Proposed Tech Specs Re PORVs & Block Valves ML20085L0411995-06-19019 June 1995 Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing ML20085K4591995-06-19019 June 1995 Proposed TS 3/4.6.2, Depressurization & Cooling Sys, Changing Required Test Frequency for Reactor Bldg Spray Nozzle Flow Test from Once Per Five Yrs to Once Per Ten Yrs ML20080K1981995-02-21021 February 1995 Proposed Tech Specs,Incorporating Revs to 10CFR20 ML20107L8771995-01-31031 January 1995 Rev 19 to Offsite Dose Calculation Manual ML20078G9231995-01-30030 January 1995 Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation 1999-08-19
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212H4651999-05-0404 May 1999 Amend 17 to Training & Qualification Plan ML20202C3271998-08-31031 August 1998 Amend 16 to Training & Qualification Plan ML20153F9241998-04-23023 April 1998 Change A,Rev 10 to FEP-1.0, Fire Emergency Procedure Selection ML20153G7081998-03-30030 March 1998 Rev 2 to FEP-4.1, Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire in Control Building ML20153F9691998-03-25025 March 1998 Rev 3 to FEP-3.1, Train B Plant Shutdown from Hot Standby to Cold Shutdown Due to Fire ML20153F9341998-03-23023 March 1998 Rev 3 to FEP-2.0, Train a Plant Shutdown to Hot Standby Due to Fire ML20203H5741998-02-0505 February 1998 Rev 31,change C to EPP-002, Communication & Notification ML20203H5981998-02-0202 February 1998 Rev 3 to EPP-105, Conduct of Drills & Exercises ML20203H5831998-01-27027 January 1998 Rev 5 to EPP-103, Emergency Equipment Checklist ML20153F9931997-10-22022 October 1997 Rev 2 to FEP-4.0, Control Room Evacuation Due to Fire, Change D ML20153F9511997-10-22022 October 1997 Rev 2 to FEP-3.0, Train B Plant Shutdown to Hot Standby Due to Fire, Change B ML20153F9461997-10-22022 October 1997 Rev 2 to FEP-2.1, Train a Shutdown from Hot Standby to Cold Shutdown Due to Fire, Change B ML20210V2481997-06-30030 June 1997 Amend 15 to Training & Qualification Plan ML20217H3521997-06-16016 June 1997 Amend 14 to, Training & Qualification Plan ML20137F8501997-02-0404 February 1997 Change E,Rev 7 to Inservice Testing of Pumps Second Ten Year Interval ML20138H7191996-09-0606 September 1996 Rev 22 to ODCM for VC Summer Nuclear Station ML20134J9741996-06-0505 June 1996 V C Summer Fuel Assembly Insp Program ML20138H7141996-03-25025 March 1996 Rev 21 to ODCM for VC Summer Nuclear Station ML20093F6131995-08-31031 August 1995 Rev 7 to General Test Procedure (Gtp) GTP-301, IST of Pumps Second Ten Yr Interval ML20107L8771995-01-31031 January 1995 Rev 19 to Offsite Dose Calculation Manual ML20084Q8821994-10-24024 October 1994 Rev 1 to Sce&G VC Summer Nuclear Station ASME Section XI Inservice Exam Manual for 2nd Insp Interval ML20080P4221994-09-0909 September 1994 Rev 18 to ODCM for South Carolina Electric & Gas Co VC Summer Nuclear Station ML20029E1161994-03-29029 March 1994 Permanent Change B to Rev 6 to General Test Procedure GTP-301, IST of Pumps Second 10-Yr Interval. ML20029E1181994-02-0909 February 1994 Permanent Change a to Rev 8 to General Test Procedure GTP-302, IST of Valves Second 10-Yr Interval. ML20064D5631994-01-20020 January 1994 Amend 12 to, Security Training & Qualification Plan ML20029E1171994-01-0101 January 1994 Restricted Change a to Rev 6 to General Test Procedure GTP-304, ISI Sys Pressure Testing Second 10-Yr Interval. ML20029E1151993-12-30030 December 1993 Rev 6 to Station Administrative Procedure SAP-145, IST Second 10-Yr Interval. ML20029E1091993-12-29029 December 1993 Rev 2 to Quality Sys Procedure QSP-213, NDE Inservice Exam Program. ML20029E1101993-12-29029 December 1993 Rev 2 to Quality Sys Procedure QSP-211, Inservice Exam for Component Supports. ML20029E1111993-12-29029 December 1993 Rev 2 to Quality Sys Procedure QSP-210, ISI Nde. ML20029E1131993-12-29029 December 1993 Rev 3 to Quality Sys Procedure QSP-214, Guidelines for ASME Activities. ML20056G5481993-04-23023 April 1993 Rev 17 to ODCM for VC Summer Nuclear Station ML20086M1111991-09-30030 September 1991 Rev 16 to ODCM ML20066G7951990-12-31031 December 1990 Rev 14 to Odcm ML20065T1481990-12-18018 December 1990 Rev 6 to Emergency Operating Procedure EOP-12.0, Monitoring of Critical Safety Functions ML20058P6701990-06-29029 June 1990 ODCM for Virgil C Summer Nuclear Station ML20059C0151990-02-12012 February 1990 Change a to Rev 8 to PCP-001, Process Control Program for Processing Wet Waste ML20247A4051989-03-31031 March 1989 Rev 4 to General Test Procedure GTP-302, Inservice Testing of Valves ML20155F5961988-09-30030 September 1988 Program of Compliance to NRC Bulletin 88-008 for VC Summer Nuclear Power Plant:Part 1 Action Plan ML20237E9171987-12-23023 December 1987 Revs to ASME Code Section XI Pump & Valve Test Program ML20237A1431987-09-30030 September 1987 Rev 12 to Offsite Dose Calculation Manual ML20215K6161987-04-30030 April 1987 Rev 11 to Offsite Dose Calculation Manual for South Carolina Electric & Gas Co,Vc Summer Nuclear Station ML20215K6001987-01-31031 January 1987 Rev 10 to Offsite Dose Calculation Manual for South Carolina Electric & Gas Co,Vc Summer Nuclear Station ML20205T7271986-11-30030 November 1986 Rev 9 to Offsite Dose Calculation Manual ML20237K8571985-07-19019 July 1985 Rev 1 to General Test Procedure GTP-308, Detection & Evaluation of Steam Piping Erosion/Corrosion & Selected Component Welds for Cracking ML20116B1191985-04-0808 April 1985 Revised Emergency Plan Procedures,Including Updated Index, Rev 12 to EPP-002 Re Communications & Notifications,Rev 8 to EPP-005 Re Offsite Dose Calculations & Rev 4 to EPP-009 Re Onsite Medical ML20107A7031984-10-31031 October 1984 Rev 7 to Offsite Dose Calculation Manual ML20108F1781984-08-24024 August 1984 Rev 2 to General Test Procedure GTP-305, Inservice Insp for Component Supports ML20108F1741984-08-14014 August 1984 Rev 0 to General Test Procedure GTP-304, Inservice Insp Sys Pressure Testing ML20097A0371984-07-31031 July 1984 Rev 6 to Offsite Dose Calculation Manual 1999-05-04
[Table view] |
Text
- . . . - - - _
I
.r-- PRESERVICE INSPECTION PROGRAM .-
FOR THE },
VIRGIL.C. SUMMER' STATION i
, (REVISION 2) ,
i OWNER: South Carolina Electric and Gas Company P.O.. Box 328 Main Street !
Columbia, South Carolina 29218 i PLANT: V.C. Summer Station l Located - Twenty-Six' Miles Northwest of .
Columbia in Jenkinsville, South Carolina
PREPARED BY: Qt . h
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A3[F1 !
[
PLAN APPROVALS: .
, e//25/W IG3ERVLCE INSPECTION COORDINATOR 'DATE f/ 5 QA GROUP SUPERVISOR DATE (0Y4 MANAGER, V.C. SUMMER NUCLEAR v/>WPi
' 'DATE i ST ION
.l MANAGER, NUCLEAR ENGINEERING
.Y 4 tf f/
DATE (
l CONCURRENCE: c. h
AUTHORIZED @ CLEAR INSERVICE DATE >
, INSPECTOR l
\ . .
, ,s... i s, q,*
5195050296 l
. I
/
fm. - TABLE OF CONTENTS d
l PAGE SECTION A +
Introduction AP-014 "Preservice Inspection Program" ................. A-1 through A-3 ,
SECTION B NDE ,
.1. Introduction ....................................... B-3 through B-7B
- 2. Tables of Class 1 and 2 Systems..................... B'-8 through B-27 and Components
- 3. Relief Request ...................................... B-28 through B-41
- 4. PSI Weld Reference Index ........................... B-42 through B-49
- 5. PSI File No. t6 Weld No. Index ..................... B-50 through B-55B
- 6. Scoped Drawings .................................... B-56 through B-74
- 7. Isometric Drawings
- a. Regular Program ................................ B-75 through B-186
- b. Augmented Program .............................. B-187 through B-198 e SECTION C HYDROSTATIC TESTING (s ,)
Introduction ........................................... C-2 Index .................................................. C-3
- 1. ISI Hydro Reference Index ........... .............. C-4 through C-10A
- 2. Scoped Drawings .....................................C'11 through C-69
- 3. Sample PSI File Packet ............................. C-70 through C-87
- 4. Sample PSI Routing Sheet ........................... C-89 through C-90
- 5. Sample Data Sheets ................................. C-92 through C-93
- 6. Sample Completed Procedure.......................... C-94 through C-109 SECTION D PUMPS Introduction .......................................... D-2 Index ................................................. D-3
- 1. List of Pumps ..................................... D-4 through D-8
- 2. Symbols (De f ini t io n s )' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D- 9 through D-10
- 3. ISI Test Quantities ............................... D-12 l
- 4. Sample Data Sheet ................................. D-14 through D-15 I
- a. Preservice/ Baseline Data Sheet I
- 5. Relief Request (Deleted) Revision 2 . . . . . . . . . . . D- 17 )
1 I
l o
(REVISION 2)
JU
- - . _ . . . . .e . - - . . . . - _. .._ ,
. t
-I TABLE OF CONTENT (Continued) t i
i SECTION E^ VALVES.
Introduction ....................................... E-2 through.E-3'.
Index .............................................. E-4 ;
- 1. . List of Drawings................................ E-5 through E-7 i
- 2. List.of Valve Categories .......................- E-8 through E-9.. l
- 3. Sample. Data Sheet
- a. Preservice/ Baseline Data Sheet ............. E-ll [
- 4. List of Definitions'and Valve Tables ;
Symbols ..................'...................... . E-13 through E-14 i
.5. List of Valves ................................. E-15 through E l
- 6. Relief Request (Deleted) Revision 2........ E-46 through E-75 l
'i i
SECTION:F COMPONENT SUPPORTS ,
l l
Introduction ....................................... F-2 r Index .............................................. F-3 'l
- 1. Component Supported Reference Index ............ F-4 . through F-23 i (Scoped Drawings) (Deleted - Revision 2)....... F-23 ;
- 2. Sample Data Sheet . . ............................ F-25 l r
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i I,
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F I
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O . L A
(Revision 2)
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i
- 4. Preservice/ Baseline Inspection Program i
Baseline data to support the PSI program will be complied in accor . i dance with the 1974 edition of the code through Summer 1975 addenda. i
-f Baseline data /preservice inspections will be performed during the l l
t construction and start-up phases of the station, utilizing l
. i.
Westinghouse inspection procedures and SCE&G startup functional and pre-operational test procedures. The specific procedures and ,
example of same are listed in the-applicable sections of this plan. '
c -. ,
e i
' i
- 5. Control (
This plan, in conjunction with AP-014 (Preservice Inspection Program), ,
@ has been prepared as the controlling documents governing the preservice/
~
baseline data inspection activities at the V.C. Summer Station, j
- 6. Supporting Programs .
,l f
I ii All supporting programs and/or documentations referenced herein are ,
maintained at the station. ;;
t t:
)'
Should cetain ASME Section XI Code requirements be discovered to be !
impractical due to unforeseen reasons during the process of perform . !
ing inspections or test, ;!
'i l
ki k )) ?t i!
i t
i A-2 (Rev. 2) !
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