|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20056C9241993-06-30030 June 1993 GGNS GL 89-10 MOV Program ML20095J9471992-03-31031 March 1992 Quarterly Status Rept for Period Ending 920331 Re Degraded Core Accident Hydrogen Control Program ML20114B8011992-01-23023 January 1992 Rev 13 to Offsite Dose Calculation Manual ML20086A4101991-11-0707 November 1991 Rev 0 to Administrative Procedure 01-S-10-4, Emergency Plan Training & Drills, Reflecting Cancellation of Emergency Plan Procedure 10-S-01-23,Rev 11 ML20043H0541990-06-19019 June 1990 Receipt,Routing & Disposition Form for Procedures S-330, Security Training & Qualification Plan & S-480, Physical Security Plan. ML20043B2501990-05-14014 May 1990 Rev 4 to Spec SERI-M-189.1, Pump & Valve Inservice Testing Program. ML20059C9231990-04-11011 April 1990 Rev 3 to Process Control Program ML20196E9331988-11-30030 November 1988 Cycle 4 Proposed Startup Physics Tests ML20154L7771988-04-27027 April 1988 Rev 3 to SERI-M-189.1, Pump & Valve Inservice Testing Program ML20153G7031988-01-0101 January 1988 Temporary Change Notice 6,Directive 04-1-01-EX-1 to Rev 18 to Administrative Procedure 04-1-01-E32-1, MSIV Leakage Control ML20235Y9141987-09-22022 September 1987 Rev 0 to Procedure 07-S-53-C11-22, Loop Calibr Instruction Backup Scram Valve B Functional Test,Safety-Related ML20235Y8951987-09-22022 September 1987 Rev 0 to Procedure 07-S-53-C11-21, Loop Calibr Instruction Backup Scram Valve a Functional Test,Safety-Related ML20212E0031986-12-10010 December 1986 Rev 10 to Offsite Dose Calculation Manual ML20207G9301986-11-24024 November 1986 Rev 2 to MP&L-M-189.1, Mississippi Power & Light Pump & Valve Inservice Insp Program ML20212G1571986-10-31031 October 1986 Revised Pages to Procedures Generation Package ML20215L2871986-10-15015 October 1986 Rev 2 to Process Control Program Description ML20212E0751986-10-15015 October 1986 Rev 2 to Process Control Program Description ML20212D9411986-08-28028 August 1986 Rev 9 to Offsite Dose Calculation Manual. Marked-up Rev 9 to Manual Encl ML20212D8001986-08-25025 August 1986 Rev 8 to Offsite Dose Calculation Manual. Marked-up Rev 8 to Manual Encl ML20215C1921986-08-25025 August 1986 Rev 8 to Offsite Dose Calculation Manual ML20211Q9111986-07-31031 July 1986 Rev 1 to Grand Gulf Nuclear Station-Unit 1 Emergency Procedures Upgrade Program Procedures Generation Package ML20137L6891985-11-15015 November 1985 Rev 6 to Vol 8,Section 3,Procedure 08-S-03-17, Chemistry Procedure Core Damage Estimation Safety-Related ML20133G9951985-09-27027 September 1985 Rev 6 to Offsite Dose Calculation Manual ML20133F3731985-07-31031 July 1985 SPDS Safety Analysis & Implementation Plan ML20128K6621985-06-28028 June 1985 Rev 0 to App a of Spec MP&L-M-189.1, Max Stroke Times for Power Actuated Valves ML20115G5241985-04-30030 April 1985 Emergency Procedures Upgrade Program,Procedures Generation Package ML20126D3521985-02-0505 February 1985 Rev 15 to Sys Operating Instruction 04-S-01-P64-1, Fire Protection Water Sys AECM-84-0537, Detailed Control Room Design Review Program Plan1984-12-19019 December 1984 Detailed Control Room Design Review Program Plan ML20098B7801984-08-31031 August 1984 Rev 4 to Offsite Dose Calculation Manual ML20093A2691984-07-31031 July 1984 Phase 1B Program,Div I Diesel Generator Disassembly,Reinsp & Verification of Div II Diesel Generator As-Mfg Similarity ML20092P2831984-07-0303 July 1984 Rev 2 to Offsite Dose Calculation Manual ML20093J5121984-06-29029 June 1984 Vols I-III to Inservice Insp 10-Yr Program ML20092P2841984-05-31031 May 1984 Rev 3 to Offsite Dose Calculation Manual - Safety-Related ML20127B5201984-04-14014 April 1984 Rev 13 to Procedure 05-1-02-I-4, Loss of Offsite Power ML20127B5301984-04-14014 April 1984 Rev 11 to Procedure 05-1-02-I-6, Station Blackout ML20087H5071984-03-31031 March 1984 Tech Spec Review Program Description ML20127B5241984-03-31031 March 1984 Rev 0 to Gas/Turbine Generator Sys Maint & Operation Procedure AECM-84-0180, Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure1984-03-30030 March 1984 Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure ML20087N6031984-03-23023 March 1984 Rev 2 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related. W/840323 Memo ML20087N5951984-03-22022 March 1984 Administrative Procedure TS-1, Requirements for Grand Gulf Nuclear Station Tech Spec Review ML20087N6001984-03-18018 March 1984 Rev 1 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related. W/840318 Memo ML20087N5981984-03-13013 March 1984 Rev 0 to Administrative Procedure TS-1, Grand Gulf Nuclear Station Tech Spec Review,Safety-Related ML20212E0311984-02-29029 February 1984 Rev 1 to Process Control Program Description ML20127B5331983-12-0606 December 1983 Rev 12 to Procedure 05-1-02-VI-2,Hurricanes,Tornados & Severe Weather ML20083G3421983-11-0707 November 1983 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 10-S-01-19 Re Personnel injury,10-S-01-25 Re Onsite Personnel Response & 10-S-01-26 Re Offsite Emergency Response ML20080E1111983-09-24024 September 1983 Rev 1 to Procedure 08-S-04-109, Chemistry Instruction: Operation of Orion 701 Ion Analyzer,Safety Related 1997-12-15
[Table view] |
Text
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GP/,S O GU$F SUCLEAR STATION DIERGENC'l PROCEDCE:
n-
..U PLANT CPERATIONS MANUAL
' Volume 5 0 5- S-01-EP-4 Secticn i Revision C Date:
EMERGENCY PROCEDURE .
LEVEL RESTORATION SAFETY RELATED Prepared: '
' Date Reviewed: Date Technical Review Reviewed: ' ' ' ~ '
Date Operations Superintenden:
Reviewed: ' ' '
Date '
Nuclear Plant Qualit;r Superintendent Approved: - '
Date -
Assistant Plant Manager PSRC: Date List of Effective Pages :
Pace: Revisicn:
l 1- Rev. C I
Attachment Rev. C t
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2.0 ENTRY CCNDITICNS Enter this procedure frc= IP-1 (Level Centrol) er EP-2 (Cocidewn) when RP water level cannot be determined cr maintained above TAT.
NOTE TAF = 0" as read on . the following fuel :ene instru=entation :
P601 - RER Section - 321-R615 P601 - RCIC Section - 321-R610 3.0 OPERATOR ACTICNS
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_ -- d availability and ease of utilization. The chcice of using the felicwing systems may vary with plant ccnditions .
27 3.1 Line up for injection and start pu=ps in at least two of the fc_lcwi injection subsyste=s:
.,.n
.v 4 w The =cs: rapid way to initiate ECCS injecticn systems (EP CS , LPCS , LPCI) is by arming and depressing the respective divisional initiation push-w,a.
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f_/ 3.1.1 Condensate Ecoster ( 0 4 01-N19 -1) (435 - O psig) f[[ 3.1.2 Cendens ate ( 0 4-1-01-N19 -1) (270 - O psig) f[7 3.1.3 HPCS (04-1-01-E22-1) (1103 - O psig) f[7 3.1.4 LPCI A ( 0 4 01-E12 -1) (310 - O psig)
/7 3.1.5 LPCI 3 ( 0 4-1-01-E12-1) (310 - O esiv)
[[7 3.1.6 LPCI C (04-1-01-E12-1) (310 - O psig)
[[/ 3.1.7 LPCS ( 0 4-1-01-E 21-1) (503 - 0 r sic)-
/7 3.2 If less than tac iniecticn subsystems (paragraph 3.1) can be lined up, then ec=nence lining up as many of the follcwing alternate
-:- injection subsystems as possible, but do not injection with these alternate injection subsyste=s at this time.
G? bD GUhF NUCLEAR STATION EMERGENCY PROCEDURE t
. 4 i EITLE: Level Restoration NO. 05-5-01-EP-4 REV.O PAGE 2 of 4 i e
.O 3.2.1 Standby Service Water crosstie (150 - O psig)
- a. Operate valves E12i-F094 and E12A-F096 from RER section of 1H13-P601 6 3.2.2 Fire System
- a. Fill any tank that can be pumped to the RPV O 3.2.3 ECCS flush connections from the Condensate Transfer System.
O 3.2.4 SLC (test tank) (04-1-01-C41-1) (1103 - O psig)
O 3.2.5 SLC (boron tank) (04-1-01-C41-1) (1103 - O psig)
-/7 3.3 If at any time RPV water level cannot be determined but at least oHeinjection or alternate injection subsystem is lined up for injection with at least one pump running, then proceed to EP-5 (Rapid RPV Depressurization) .
~~
// 3.4 If at any time RPV water level cannot be determined and no injection or alternate injection subsystem is lined up for injection with at least one pump running, then proceed to EP-6 (Core Cooling Without Injection).
O 3.5 Monitor RPV pressure and water level and perform only the steps listed in Table A.
/7 3.5.1 If at any -time the RPV water level trend reverses or RPV pressure changes region, then return to Table .C NOTE 500 psig = LPCS Shutoff Head 50 psig = BCIC Low Steam Pressure Isolation Setpoint l
l RPV LEVEL INCREASING INor INCREASING l
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GRA'!D GULF NUCLEAR STATICN E2ERGINCY PRCCEDURE t
9ITLE:' Level Restoration No.05-S-01-EP-4 REV. d PAGE 3 cf 4
/_7 3.5.2 Determine the availability of RCIC and perform the following actions:
[[7 a. Il RCIC is not ready for operation and RPV pressure is increasing, then proceed to EP-5 (Rapid RPV Depressurination).
~
/7 b. If RCIC is not ready for operation and RPV pressure is not increasing or is steady, then proceed to EP-1 (Level Control) at paragraph 3.3. ,
/E7 c. If RCIC is ready for operation and RPV water level incresaes to +10", then pr:eeed to EP-1 (Level Control) at paragraph 3.3.
[[7 3.5.3 Determine RPV pressure and perform the following actions:
-/7 a. If RPV oressure i,s increasing then proceed to EP-5 (Rapid RPV Depressurl:ation).
[[7 b.
^
If RPV cressure is not increasing then proceed to EP-1 (Level Control) at paragraph 3.3.
2[7 3.5.4 With RPV water level not increasing perform the following actions:
[]7 a. If ROIC is not operating, then restart RCIC.
/7 b. If CRD is not operating and no injection subsystem is lined up for injection with pumps running, then start pumps in all alternate injection subsystems which are lined up for injections (Systems listed in paragraph 3.2).
[[7 c. Il CRD is not operating but at least two injection subsystems are lined up for injection with pumps running, then proceed to EP-5 (Rapid RPV Depressurization;
~
/7 d. When RPV water level droos to TAF, perform the actions of (1) or (2) below:
NOTE TAF = 0" as read on fuel zone intrumentation:
P601 - RER Section - B21-R615 P601 - RCIC Section - 321-R610 (1) If CRD is not ocerating and no injection or alternate injection subsy' stem is lined up for injection with at least one pump running, then proceed to EP-6 (Core Cooling Without Injection).
GRAND GULF NUCL E STATICN -
EMERGENCY PRCCECURE TITLE: Level Restoration NO. 05-S-01-EP-4 P.IV. 3 pAGE 4cf4 (2) M CRD is operating o_r_ any injection or alternate injection subsystem is lined up for injection with at least one pump running then proceed to EP-5 (Rapid RPV Depressurization)
L_/_ 3.5.5 Perform the following actions:
/7 a. If no injection subsystem is lined up for injection with at least one pump running, then start pumps in ,
alternate injectionc subsystems which are lined up for injection,
/7 b. If after performing substep 3.5.5.a, RPV pressure is increasing, then proceed to EP-5 (Rapid RPV'Depressuri-zation).
/7 c. If after performing substep 3.5.5.a RPV pressure _is not increasing, .and RPV water level decreases to TAF, then proceed to EP-7 (Core Cooling Without Level Restora-
/7 d. If no injection or alternate injection subsystem is lined ~
up with pumps runIiing and when RPV level decreases to TAF, then proceed to EP-6 (Core Cooling Without Injection) k l
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