Proposed Tech Specs Clarifying That Quorum Consists of Chairman & Alternate & Majority of Plant Safety Review Committee Members or Alternates.Insert a of Original 900718 Tech Spec Change Also Clarified| ML20065K684 |
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Summer  |
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| Issue date: |
11/26/1990 |
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| From: |
SOUTH CAROLINA ELECTRIC & GAS CO. |
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| Shared Package |
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| ML20065K676 |
List: |
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| References |
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| NUDOCS 9012040074 |
| Download: ML20065K684 (5) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D6351999-10-0808 October 1999
Proposed Tech Specs Sections 3/4.4.9 & B 3/4.4.9,revising Heatup & Cooldown Curves
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Proposed Tech Specs Re ECCS Charging/Hhsi Pump Cross Connect & mini-flow Header Isolation Motor Operated Valves
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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
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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
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Proposed Tech Specs,Consisting of Change Request TSP 940002, Incorporating Revs to 10CFR20
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Proposed Tech Specs for Uprate Power Operation
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Proposed Tech Specs Re PORVs & Block Valves
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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
ML20085L0411995-06-19019 June 1995
Proposed Tech Specs Re Deletion of Schedular Requirements for Type a Testing
ML20080K1981995-02-21021 February 1995
Proposed Tech Specs,Incorporating Revs to 10CFR20
ML20078G9231995-01-30030 January 1995
Proposed Tech Specs Re Relocation of Seismic Monitoring Instrumentation
ML20078B6121994-10-20020 October 1994
Proposed TS Page,Incorporating Approved Amend 116 & Requested SR Replacement TS Change
ML20076J6691994-10-17017 October 1994
Proposed Tech Specs,Reflecting Relocation of Seismic Monitoring Instrumentation Lco,Srs & Associated Tables & Bases in TS Section 3/4.3.3.3 to FSAR or Equivalent Controlled Document
ML20073D4111994-09-20020 September 1994
Proposed TS Pages,Including Page 6-16a,revising Rev Level & Date of WCAP-10216-P-A to Reflect Updated Methodology Used in Determining Plant Core Operating Limits
ML20149G1301994-09-20020 September 1994
Proposed TS 3/4 5-6 Re Charging Pump Runout Flow Limit
ML20071K3761994-07-22022 July 1994
Proposed TS Page 3/4 3-56,reflecting Required Action to Restore One Inoperable Hydrogen Monitor Channel to Operable Status,W/Less than Min Number of Channels Operable
ML20070J7561994-07-20020 July 1994
Proposed Tech Specs,Permitting Alternative Equivalent Testing Methods to Be Performed on Diesel Fuel Purchased for EDGs & Changing Rev Level of WCAP-10216-P-A,that Will Be Used to Determine Core Operating Limits for Future Cycles
ML20070J7881994-07-20020 July 1994
Proposed TS Pages for TS Tables 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints & 3.3-4, ESFAS Instrumentation Trip Setpoints
ML20065B8361994-03-25025 March 1994
Proposed Tech Specs Pages for Missing Page Numbers of TS Pages Submitted in
ML20064H9591994-03-11011 March 1994
Proposed TS 4.8.4.1.a.3,deleting Fuses Used as Penetration Overcurrent Protection Devices from SRs & from Bases B 3/4.8.4
ML20064H9251994-03-11011 March 1994
Proposed Tech Specs 3/4.4.9.3,changing AOT for RHR Suction Relief Valves from 7 Days to 72 H
ML20064H4501994-03-11011 March 1994
Proposed Tech Specs Re Steam Generator Replacement
ML20064G5541994-03-11011 March 1994
Proposed Tech Specs Re Limiting Safety Sys Settings for Reactor Trip Sys Instrumentation Trip Setpoints ESF Actuation Sys Instrumentation Setpoint
ML20064C6421994-02-25025 February 1994
Proposed Tech Specs,Incorporating Current Provisions of 10CFR50.36(a)2 Re Semiannual Radioactive Effluent Release Rept to Be Submitted Annually Rather That Semiannually
ML20062K6321993-12-13013 December 1993
Proposed Tech Spec Figures 3.9-1 & 3.9-2,permitting Storage of Fuel Assemblies in Regions 2 & 3 of Spent Fuel Storage Racks,Respectively
ML20059G2901993-10-29029 October 1993
Proposed Tech Specs Supporting SG Replacement
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Proposed Revised TS Re Emergency Feedwater Per 10CFR50.59
ML20045F7771993-06-30030 June 1993
Proposed Tech Specs SR 4.7.1.2 for Performance of Turbine Driven EFW Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig
ML20045C3441993-06-16016 June 1993
Proposed Tech Spec 4.7.1.2.a.2 Supporting Request to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psig
ML20044G7551993-05-25025 May 1993
Proposed Tech Specs Revising Page 3/4 7-4,re Changing TS 4.7.1.2.a.2,to Perform Turbine Driven Pump Surveillance Test at Secondary Steam Pressure Greater than or Equal to 865 Psi
ML20128H9781993-02-12012 February 1993
Proposed TS Modifying Insp Requirements of TS 3/4.4.5 Re SGs & LCO for 3/4.4.6.2 Re Operational Leakage to Establish Interim Plugging Criteria
ML20128K1821993-02-10010 February 1993
Proposed Tech Specs Re Main Steam Safety Valves
1999-08-19
[Table view]
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
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Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR
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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] |
Text
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ATTACllMENT 1 MARKED-UP TECilNICAL SPECIFICATION PAGE Page - hecification Change Description 6-4 6.5.1.2 Clarification to Insert A of the original Technical Specification Change (July 18,1990).
6-4 6.5.1.3 Amendment (August 31,1990).
6-4. 6.5.1.5 Amendment clarifies that the quorum shall consist of a chairman or his alternate and a majority of the PSRC members or their alternates.
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', 9012040074 901126 ,,.
PDR ADOCKOSOOgg' P
- _ . __:_--. _ _ _ - _ _ __ - _-. - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ = _ _ _ _ _ _ _ . _ _ _ - _ - _ _ _ _ _ _ _ _
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y ; ..
y" -ADMINISTRATIVE-CONTROLS
- 6. 5 REVIEW AND AVOIT _
2 --
- 6. 5.1 FUNCTION PLANT SAFETY REVIEW CO*lTTEE (PSRC)
. I Operations on all matters relates to., Nuclear nuclearPlant safety.6 COMPOSIT10N
- 6. 5.1.2- TW1:nt u';ty a:';i::
Chai" m: !=ttt;; st,eli Le ;c;;; d Of the:
bee, C:rar:1 "an:p, "M10:r " lent Ov er;;i:n; er ceaere! ":n:
ggA Member: and ut ateaeace;;r, Op;reMons i
"an: ;r, 0 r:tk Member:
0;aar;et "e;;ger, as
~
, Membea: ne Stativo Svyyvrt Memboa: ":n:
Meaeg: , ": ht;aees. 5eryices u e , rar.
C'=puter rngin..ria; ::: .;1 ;p 5:rvi::s Membac.-
Member: Mare er Che-fetrj :nd Heeiu M m ;;a*,
, Dee t;n Cr.;b:;r'ng i Pi,ye gs At.TERNATES ee 6. 5.1. 3 H-+4ernate f.hg i e=:=, t;_447_yg_an e-bers -55:11 b apps h ted ir, ortting bj tt.e ps"4 behdtrnt-%e-CWeman4-aiternateg t;;p;teij U85ii, Ieywever, 00 mored-sBan T
^
mehMSRC ::tivMk t ;a, v,n.ii appiicacie, aneil periisip.i .e wt4fg
. time. '
MEETING FREQUENCY
- 6. 5.1. 4 by the PSRC Chairman or his designated alternate.The PSRC QUORg h,e 6.5.1.5 m . 4-.-
M@ , 'MC-r :;: :fbility mall ceasi;t--cf an:d ;cth&r4ty th Ch&ir;;.a : pr;vi:f one Gf the;;ections- T&shMetMpe
'Q mehdhg-ehornales.
his d;;ignated aiternetricamMhree members.
RESPONSIBILITIES
- 6. 5.1. 6 The Plant Safety. Review Committee shall review:
, a.
- b. Station administrative procedures and changes thereto, The safety evaluations for 1) procedures, 2) changes to proced equipment provision or systems, and-3) tests or experiments completed un of Section 50.59, 10 CFR, to verify that 'such actions did .
'not by' Specification 6.8 andunreviewed constitute an changes thereto. safety question and all programs c.
which Section 50.59,10 mayCFR.involve an unreviewed safety questio .
SUMMER - UNIT 1 I i4 !
Amendment No. JS, 79
, _ _ - + + " ' ' - " ' ~ ' _ _ _ _ _ _ _ _ - - - ~ ~ ^ " - ' -
.~
8 . . . ; .;
INSERT-A lit The' Plant Safety Review Committee (PSRC) shall be composed of a chairman and i f;ve to ten members of the Virgil C. Summer Nuclear Station management staff -I at the manager. level'or_above. These positions will.be-designated by the General Manager, Nuclear Plant Operations in a Station Administrative Procedure. At a minimum, representatives from Operations, Maintenance, Chemistry and Health Physics, and Engineering Services shall be appointed to the PSRC.
.1 j i 1
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4 INSERT B All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, alternates, including the chairman's alternate, who are participating as voting members in the PSRC shall hold a minority vote in all PSRC activities.
- - - - - - - - - , --_------_.__,_s_,__,___a__._____________.__________ __ __ ____ _ _ _
INSERT C
= The minimum quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and a majority of the PSRC appointed members including their alternates.
I
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