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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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SOUTH CAROLINA ELECTRIC AND GAS COMPANY -
VIRGIL C. SUMMER NUCLEAR STATION
\ NUCLEAR OPERATIONS..._, ,,. , -- . r c---n.- = - -
W- .
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PROCESS CONTROL PROGR E PCP-001
~
PROCESS CONTROL PROGRAM FOR PACKAGING OF LOW-LEVEL RADIOACTIVE WASTE REVISION 3 APRIL 3, 1984 SAFETY RELATED L
1 L0!94 DISCIPLINE SUPERVISOR Date APPROVAL AUTHORITY y-/l-8y Date APR 13 584
! DATE ISSUED RECORD OF CHANGES l CHANGE TYPE DATE DATE CHANGE IYPE DATE DATE NO. CHANGE APPROVED CANCELLED NO. CHANGE APPROVED CANCELLED e
i DOC Oh00h5 PDR
, i
~PC P-001 .
T PAGE 1
(.' REVISION 3 4/3/84 LIST OF EPPECTIVE PAGES PAGE R EVISION
, 1 3 11 3 1 3 2 3 3 3
' ~
4 3 i
ATTACHMENTS Attachment I, pages 1-10 3 Attachment II, pages 1-9 3 Attachment III, pages 1-26, 25A, 2 6A ,
2 7A & 2 8A 3
~ '
Attachment IV, pages 1-15 3 i
e
, 4 .,
k'
.g
. 1 l.
d 3; PCP-001 g' - PAGE 11 .
REVISION 3 4/3/84 TABLE OF CONTENTS PAGE ,
List of Effective Pages i 1.0 PURPOSE 1 2.0 SCOPE 1
3.0 REFERENCES
1 4.0 LIMITS AND PRECAUTIONS 2 50 PROCEDURE 3 6.0 RECORDS 4 x:crAC:::.;;;;TS ATTACHMENT I -
Chem-Nuclear Systems, Inc.
' Ecodex Precoat/Powdex/ Diatomaceous Earth Dewatering Procedure for CNSI 14-195 or smaller Line. e ATTACHMENT II - Chem-Nuclear Systems, Inc.
Bead Dewatering Procedure for CNSI 14-195 or Smaller Liners ATTACHMENT III - Chem-Nuclear Systems, Inc.
Process Control Program for CNSI Cement Solidification Units ATTACHMENT IV - Chem-Nuclear Systems, Inc.
Operating Guidelines for Use of Polyethylene High Integrity Containers ts l
l , t l-. .
] >
I PCP-001 j- (L')
I REVISION 3 4/3/84 l
1 1.0 PURPOSE ,
1.1 The purpose of this Process Control Program for the l Virgil C. Summer Nuclear Station is to establish a set of l process parameters which provide reasonable assurance that ~
the packaged radioactive wastes meet applicable Department j of Transportation (DOT), Nuclear Regulatory Commission '
(NRC), and South Carolina State regulations for shipment and offsite burial at an approved site. Additionally, i reasonable assurance is provided that the acceptance criteria of said burial facility are met.
I 2.0 SCOPE 2.1 This Process Control Program shall be used by all personnel for the packaging of low level radioactive wastes. This program includes Chem-Nuclear Systems Incorporated (CNSI). personnel operating CNSI supplied equipment.
2.2 This Peocesa Control Program is applicable to all " Wet I!
Wastes" (such as evaporator concentrates, spent resins, etc.) and all wastes classified as Class B and Class C
., (in accordance with 10 CPR61) which are to be disposed of in a radioactive waste, land disposal site.
30 REFERENCES 3.1 Virgil C. Summer Nuclear Station Final Safety Analysis Report, Chapter 10 and 11, PSAR Questions 321.17,. through 321.23 32 SCE&O Corporate ALARA Plan. ,
33 Virgil C. Summer Nuclear Station Technical Specification 3/4.11 3
- 34 Virgil C. Summer Nuclear Station Quality Assurance ;
Program.
35 CNSI Quality Assurance Program, QA-AD-001, and CNSI ;
Process Control Program, in 4313-01354-01.
{!
'3.6 ,CNSI Operating Procedures for' Cement Solidification and !
Dewatering Qnits, as applicable SD-OP-036 and PO-OP-003 t,
.s PAGE 1 0F 4
- 1
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- PC P-001
'g REVISION 3 -
y ,
4/3/84 37 C NS I Tb pic al Re port , 4313-01354-01. ,
38 NUREG 0472, Radiological Ef fluent Technical Specifications for PWR.
39 Branch Technical Position-ESIB 11-3, De sign Guidance for Solid Radioactive Waste Mana6ement Systems Installed in Light-Water-Cooled Nuclear Power Reac tor Plants.
310 ANSI 199, Liquid Radioa:tive Waste Processir.g Systems for Pressurized Water Reac tor Plants.
311 NRC Regulatory Guide 1.143, Design Guides for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Cooled Nuclear Power Plants .
3 12 SRP 11. 4 Rev. 2 July,1961 " Solid Waste Management Sys t em s" .
3 1310 CPR 50, Appendix A. _
3 14 10 CPR 61, " Licensing Requirements for Land Disposal of Rad ic ac t iv e %a s te" .
3 15 10 CFR 20. 311, " Standards for Protec tion Against Rad ia t io n" .
.\_ " 3 16 U. S. N. R. C. , Br anc h Te c hnical Po sitio n, " Fin al Wast e Classification and Waste Form Technical Position Papers",
dated May 11, 1983 3 17 CNSI-DW-11118-01-N P, "De watering To pic al, Chem-Nuclear Systems, Inc.".
3 18 C NS I-W F-C -014f P, " Ti tl e 10 C P R 61, Wa st e Fo rm Certification -- Cement" by Chem-Nuclear Systems, Inc.
3 19 C NSI-HIC-14571-Oi-N P, " Tb pic al Re po rt , Polyethylene High Integrity Containers" by Chem-Nuclear Systems, Inc.
3 20 V. C. Summer fMelear Station, Tbchnical Specifications, Sec tions 6. 5 1. 6. 0, 6. 8.1.g and 6.13 2.
- 4. 0 LIMITS AND PREC AUTIONS ;
4.1 Ensure that applicable Radiological Controls are established when sampling or processing Radioac tive Waste .
- 4. 2 Only a CNSI operator with a release to work from QA, may operate CNSI solidification and dewatering equipment at
.this station. ,,
PAGE 2 0F 4 l
i FC?-001 REVISION 3 j (]
G 4/3 /b 4 43 Working co pie s o f the PcP must be verified against the ;
Ma ste r Co ntrol Cc py o f PC P-001 p rio r to b eg inn ing wo rk. j 1
50 PROCEDURE 51 For each batch of " Wet Waste" or Class B or C waste, Health Physics shall determine the most appropriate method of processing to meet 10 CPR 61 waste form criteria.
- 5. 2 Normally acceptable waste processing methods and associated waste streams are:
5 2.1 Cement solidification for:
- a. Waste Evaporator Concentrates
- b. Pilter Sludges
- c. Oils & Chemicals 52.2 Dewatering in steel liners for:
- a. Powdex or Bead Type Re sins with specific ,
ac t ivit y < 1 ui/cc i 523 Dewatering in High Integrity Containers for:
(
- a. Powdex or Bead Type Resins with specific ac tivity > 1 ui/ cc 5.2.4 Draining of any " free standing water" and disposal in a high integrity container for:
- a. Process filter cartridges 5 3 Cement solidification shall be acecmplished in accordance with Attachment III. ,
54 Dewatering of Bead Type Resins should be accomplished. in -
accordance with Attachment II.
55 De wa te r ing o f Ec od ex , Po wd ex o r Di a tom ac eo us Ea r th s ho uld
- be accomplished in accordance with Attachment 7. .
- 5. 6 Whenever High. Integrity Containers.are used, Attachment IV l
'should be followed to ensure that the container retains [
its ability to meet 10 CPR 61 waste form requirements. j i
y PAGE 3 OF 4 u.
O I
l 1,,. .
PCP-001
6.0 RECORDS
, 6.1 All records generated in accordance with this procedure -
shall be included with the shipping papers as outlined in HPP-703 6.2 Copies of the shipping papers will be maintained by Health Physics for subsequent transmittal to Documents for retention. ,
l
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T ATTACfDENT I - IV .
ARE PROPRIETARY INEtR% TION 4
.