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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] |
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, '; ' ATTACHMENTIV i_ i ; j ') ;, . . . _ _ 4 PAGE 10F 3 'p REVl510N 12 Procedure Development Form A ;
DATE: !"/ W O - PROC. # *N/ .# CHG. COMM.P
-L ITITLE: /?refNr OM?ac. /2coh /04. W5/A 6 /Uf~ [ A ) n
- l. NEW PROC ,
y REVl510N SAFETY RELATED V QUAllTY RELATED CHANGE PERMANENT ..ESTRICTED . FROM TO NON SAFETY RE LATED
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.TWO YEAR REVIEW _
I l li . DESCRIPTION: (Seesection 9 6 4 3) / dM $iN.M N O _h'r5/0J IM 4>k /{f_M-/}9, i
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Ill. WILL THIS REVISION! CHANGE /NEW PROCEDURE: 'Yes No N/A
- 1. Represent a change to procedures 45 described in FSAR, FPER or RE P? (50.59 #eview)
- 2. Represent a chat'ge to the f acility as described in the FSAR, FPE R or REP? (50.59 review)
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- 3. Represent a test or experiment not described in FSAR FPER or REP? (50 59 review)
Y
- 4. Require a change to Technical Specifications? (50 59 review)
~
Y -
- 5. Result in significant increased personnel radiation esposure ? (ALARA review)
~
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~Y
- 6. Result in a release of effluents to the Environment?
7, Degrade the safeguards effectiveness of the PhysicalSecurity Plan?.
~ 2:
- 8. Degrade the safeguards of fectiveness of the Safeguards Contingency Plan? _/c l
SUMMARY
JUSTIFICATION:
j '. 'If estion 1 throu is answered *y ,
F5AR, FPER, REP or TS l REFERENCES (See Section 6 4 4):
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- 'V TEMPORARY APPROVAL U
- j. QUAL. REVIEWE R Date FOR 5 APs.5PPs.E PPs:
- TELECON 8Y GMNPO/MD5 DATE
< $HIFT SUPERVISOR Date IU FINAL APPROVA REQUIREDBY DATE REQUIRED REVIEW AND COMMENT VI. RC REVIEW V.
P/ CAP ACCEPTABLE C. - YES - N A
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[ RESP MGR. Date P g3 () Vit. FINAL QA REVIEW (As Ap gRC ()GMNS A Date Acurrence PICAP AFFECTED 8 YES NO '
COMMENTS RESOLVED: - /!/ 6 // //[
5:scipiine grvisor / o&te Approvadoncurrence oate j l
IX. PSRC REVIEW j B. PSRC Comments Resolved; b /l/J2/?d MANAGER DATE PSRC CHAIRMAN DATE f F SRC CH AIRMAN DATE Comments: YE5 _ No
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...- - ' PAGE i~ ,
REVISION 8 f
i t
TABLE __OF CONTENTS PAGE
- 1.0 PURPOSE l' 2.0 SCOPE 1 1
3.0 REFERENCES
4.0 LIMITS AND PRECAUTIONS: 2 5.0 PROCEDURE 3 6.0 RECORDS 8 7.0 REVISION
SUMMARY
8 l
O ATTACHMENTS A Attachment I - Dewatering Requirements / Acceptance Requirements Attachment II - Dewatering Completion Record - Bead-Type Resins and Activated Carbon Attachment III - Dewatering Completion Record - Powdex/Ec'odex Attachment IV - High Integrity Container Exposure Log I
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- PCP-001 REVISION 8 5 5 Cas4/ Container /Overpack handling will be performed in accordanc9 with approved vendor's procedures. High Integrily Container sunlight exposure shall be documented using Attachment IV.
NOTE:
The High Integrity Container vendor may require further handli.74 documentation to ensure adherence 'vith the container's Certificate of Compliance. Refer to HPP-716 i
for additional requirements.
l 6.0 RECORDS 6.1 All records generated 11 accordance with this procedure and any related vendor-required procedures shall be maintained .
by Health Physics for subsequent transmittal to documents for retention.
7.0 REVISION
SUMMARY
. 7.1 Revised body and attachments to eliminate vendor from procedure. Consolidated redundancies present in original procedure, f PAGE 8 0F 8 GENERAL REVISION
,