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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
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- s 11/14/83
,\
g VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS PROCEDURES EMERGENCY PLAN PROCEDURES TABLE OF CONTENTS
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PROCEDURE DATE NUMBER PROCEDURE TITLE REVISION ISSUED EPP-001 Activation and Implementation of Emergency Plan 6 11/9/83 EPP-002 Communication and Notification 8 11 /9/83 EPP-003 In-Plant Radiological Surveying 3 6/1/83 EPP-004 Out-of-Plant Radiological Surveying 4 5/25/83 ,
EPP-005 Offsite Dose Calculations 5 11/9/S3 EPP-007 Environmental Monitoring 1 7/27/82 EPP-009 On-Site Medical 2 7/27/82 EPP-010 Personnel / Vehicle Decontamination 3 '11/9/83 EPP-011 Personnel Search and Rescue 2 7/27/82
' EPP-012 Onsite Personnel Accountability & Evacuation 4 5/25/83 ,
l EPP-01~ Fire Emergency 3 5/25/83 EPP-014 Toxic Release 1 7/27/82 EPP-015 Natural Emergency (Earthquake, Tornado) 3 11/9/83 EPP-016 Emergency Facilities Activation & Evacuation 4 11/9/83 EPP-017 Post-Recovery and Re-Entry 4 11/9/83 EPP-018 Emergency Training and Drills 3 11/10/83 EPP-019 Emergency Equipment Checklist 4 6/1/83 EPP-020 Emergency Personnel Exposure Control 3 11/14/83
- Safety Related Procedure -
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'PROCEDUP3 .DATE NUMBER PROCEDURE TITLE REVISION ISSUED EPP-021 Activation of the Early Warning Siren
- ] System (E' DSS) 5 5/25/e3
, J EPP-022 Verification of Communicationa Operebility 2 5/25/83 e
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, SOUTH. CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION
'd NUCLEAR OPERATIONS NUCLE /0 CPERATiOMS COPY No.........I M EMERGENCY PLA
N. PROCEDURE
EPP-020 EMERGENCY PERSONNEL EXPOSURE CONTROL REVISION 3 I
NOVEMBER 3, 1983 l l
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APPROVAL AUTHORITY
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NOV 141983 DATE ISSUED RECORD OF CHANGES
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CHANGE TYPE DATS DATE CHANGE TYPE DATE DATE NO. CHANGE APPRCVED CANCELLED NO. CHANGE APPROVED CANCELLED l-l . ,
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. EPP-0 20 PAGE i '
O 'v REVISION 3 11/3/83 T.IST OF EFFECTIVE PAGES Page : ', ? Revision
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2 2 3 2 4 3 5 3 .
ATTACHMENTS Attachment I 2 Attachment II 3
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EPP-020 REVISION 3 11/3/83
(~h y ' .? 1.0 PURPOSE 1.1 Provide guidelines for-issuing dosimetry and controlling j personnel exposure when responding to conditions that have i placed the plant in an Alert, Site, or General Emergency status.
2.0 REFERENCES
l 2.1 Virgil C. Summer Nuclear Station Radiation Emergency Plan.
2.2 100FR20.
23 NCRP Report #39 " Basic Radiation Protection Criteria".
2.4 HPP-153, " Administrative Exposure Limit s" .
25 RPP-150, "Issusnce and Control of Personnel Dosimetry. ?
2.6 HPP-505, " Issuance and Con +.rol of Personnel Dosimetry".
27 NCEP Report #55, Protection of the Dayroid Gland in the Event of Relecses of Radioiodine.
2.8 CHP-309, Emergency Operations Facility Dose Assessment C'~
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Gaidance.
30 CONDITIONS AND PREREQUISITES 31 Limits and Precautions.
3 1.1 This procedure may be activated by the Interin Energency Director / Emergency Director or Radiological Assessment Supervisor when conditions dictate. Any deviations from this procedure should be authori~ zed by the Interim Emergency Director / Emergency Director or Radiological Assessment Supervisor snd docunented. As soon as conditions allow return to normal plant procedures.
32 In an emergency, the following exposure limits may be utilized:
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EPP-020 REVISION 3 11/3/83 bl xt 4.2 3 As soon as conditions allow and at the d'irection of the Interim Emergency Director /Erergency Director or the Radiological Assessment Supervisor, normal dosimetry issue and exposure control should be reinstituted in accordance with references 2.4 and 2 5. l 4.2 4 Responsibilities of Health Physics:
1 a) Proper collection of dosimetry.
b) Completion of dose cards and Attachment I's.
c) Completion of all required personnel exposure records.
43 Use of KI thyroid blocking agent.
431 The Director of Health Physics or Radiological Assessment Supervisor shall determine the need for -
administering KI (stored in the TSC) .
432 KI should be administered within one hour following an acute uptake that involves a projected thyroid exposure greater than 10 Rem. Guidelines are:
k./ 4 3 2.1 Individuals suspected to have received greater than 650 MPC-hours of internal exposure to'radiciodines should be showered and analyzed by whole body counting (torso) immediately following the uptake. Measured torso burdens greater than 4 C1 (I-131 ) may result in a thyroid exposure greater than 10 Rem.
4 3 2.2 If conditions do not allow whole body counting within two hours after the uptake, the estimated MPC-Hour exposure should be used to determine the need for KI.
4 3 2 3 KI (100-300 mg) should be taken on a daily basis not to exceed 7-10 days until the thyroid uptake of radioiodine is adequately blocked.
4 3 2.4 Any individual has the right to refuse KI and accept the resulting thyroid exposure.
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PAGE 4 0F 5
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REVISION 3 11/3/83 433 Attachment II must be c'ompleted prior to ~
administerin6 KI-44 EOF 3xposure Control.
4.4 1 EOF exposure control'will be performed in accordance with CHP-309 l
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EPP-020
,- ATTACEMENT II PAGE 1 OF 2 i i REVISION 3 v
ACUTE UPTAKES INVOLVING PROJECTED THYROID DOSE COMMITMENTS GREATER THAN 10 REM Date: Time:
MPC-HRS / Time of I-131 Torso / Time of I
- Name - --. _TLD4 Estimate / Uptake Burden (uCi) Count Time KI Taken The threshold for the pcssibility to experience thyroid abnormalities after l uptake of radiciodines is estimated at 20 Rem (low probability of i 6 x 10-4 Higher probabilities (greater than .075) exist with thyroid l exposures greater than 2500 Rem. l KI can be taken after an uptake to prevent accumulation of radioactive iodine in the thyroid due to saturation of the thyroid with stable iodine.
KI is over 90% effective if administered within one hour after the uptake and over 50% effective if administered within three to four hours after the uptake.
Usually, side effects of potassium iodide happen when people take higher
/ doses for a long time. You should be careful not to take more than the D) recommended dose or take if for longer than you are told. Side effects art.
unlikely because of the low dose and the short time you will be taking the drug.
Possible side effects include skin rashes, swelling of the salivary glands, and " iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
A few people have an allergic reaction with more serious symtoms. Thsse could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention.
Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
If side effects are noted or if you have an allergic reaction, stop taking potassium iodide. Then, notify the Director, Nuclear Plant Operations and l obtain medical assistance as needed.
The only people who should not take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or
_ antithyroid drug). Pregnant and nursing women and babies and children can also take this drug.
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EPP-020 ATTACHMENT II PAGE 2 OF 2 O.) REVISION 3 i ACKNOWLEDGEMENT I understand and accept the risk associated with receiving KI and will i
'not hold SCE&G Company liable for any payments or costs resulting from ]
side effects excluding that provided by normal Company policies.
Signature (s) Date Time I choose to accept. thyroid exposure instead of minimizing thyroid exposure by taking KI. I will not hold SCE&G Company liable for any subsequent thyroid abnormalities which may be related to thyroid exposure.
Signature (s) Date Time
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Assoc. Manager of Health Physics (or) Director, Nuclear Plant Operations Radiological Assessment Supervisor (or) Emergency Director
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