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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
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SOUTE CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION
. NUCLEAR OPER!.TIONS f J rng r g '
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EMERGENCY OPERATING PROCEDURE E0P-14 INADEQUATE CORE COOLING REVISION O NOVEMBER 10, 1980 SAFETY RELATED Reviewed.by: .
ORIGINATOR (of this revision) Date l
QUALIFIED REVIEWER Date Approved:
OPERATIONS SUPERVISOR Date Date Issued:
Form AP-101-2 (1/60) 8011210/67
1 **
4 . i E0P-14 PAGE i REVISION O 11/10/80 LIST OF EFFECTIVE PAGES PAGE REVISION i , 0 1 0 s')
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~~. E0P-14
, PAGE 1 RE7ISION O :
11/10/80 1.0 PURPOSE 1.1 This procedure provides instruction to:
1.1.1 Establish cooling to the reactor during periods when other means of core cooling are not available.
1.1.2 Minimize core damage during emergencies where core temperatures are increasing.
2.0 REFERENCES
AND GLOSSARY -
2.1 References .
2.1.1 E0P-1 Safety Injection Actuation.
2.1.2 E0P-13 Natural Circulation.
2.'2 Glossary None 30 SYMPTOMS 31 Main and emergency feedwater is not operable or sufficient to maintain a heat sink and adequate core cooling. s
, 32 Steam generator-levels ,are lowor off scale. . -
3 3,, Secondary. stean ragease,is '
not sufficiegt. ,$,o provlde adequate core cooling.-
3.4 Any five' (5) incore thermocouples indicating > 650*F and .
increasing as measured on:
- 1) Plant computer or
- 2) Subcooling monitor or ~
- 3) In Core thermocouple indicator
~
4.'O. AUTOMATIC ' ACTION 4.1 None
-50 IMMEDIATE OPERATOR ACTION i 51 None
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l EOF-14 -
PAGE 2 REVISION O 11/10/80 6.0 FOL10W UP OPERATOR ACTION NOTE: Throughout this procedure continue efforts to establish feedwater flow'to the steam generators and reestablish core cooling via the secondary steam dumps.
6.1 If not safety injecting, manually safety inject.
6.2 If during the procedure the RWST lov low level is reached, establish cold leg recirculation as per E0P-1, Attachment I, steps 6.19 through 6.26.
63 Stop all operating Reactor Coolant Pump to reduce heat load.
6.4 continue maximum safety injection flow to fill the pressurizer.
6.5 When pressurizer le water solid as indicated by rapidly increasing pressurizer pressure valve (PCV-444B, 445A, or 4453), open one (1) PZR power relief NOTE: The pressurizer relief tank rupture disk will break.
6.6 Open or C".se additional PZR power relief valves ao necessary to maintain cubcooling and pressurizer preasure less than 2400 psig. .
N5tE: Pressurizer Pressure will stabilize at come pressure where charging /SI flow will equal relief valve flow. This stable pressure can be varied by opening / closing relief valves and or charging pump mini flow' valves.
d . 6 .1 If pressure must be held near,2400 psig to provide ;
subcooling. i A. Reset Safety Injection Train A & B. !
B. Open MVG-8109A, B, and C and MVG-8106 to establish '
charging pump minimum flow.
C. Close MVG-6109A, B, and C and MVG-8106 whenever 1 pressurizer pressure drops to 1550 psig.
- 6.7 Continue menitoring incore thermocouples on the core subcooling .
monitor or plant computer._ j 6.6.1 If thermocouple readings exceed the computer range, have a :
millivolt meter attached to the core exit thermocouple indicator for reading higher temperatures.
. v. .
E02-14 PAGE 3 l REVISION O 11/10/80 6.8 If the above does.not result in decreasing. core exit thermocouple temperatures,. start one (1) Reactor Coolant Pump to establish forced flow through the core.
NOTE: Frecautions smd limitations for RCS status are waived for this procedure.
6.8.1 Run the Reactor Coolant Pump for 5 to 10 minutes and then stop.
6.8.2 _ Alternating the reactor coolant pump in use, start and stop another reactor coolant pump at 30 minute intervals as long as'they are available.
70 FINAL CONDITIONS 71 Reactor Cooling has been achieved via the pressurizer relief valves.
OR 72 Reactor Cooling via the secondary steam dumps has been achieved.
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