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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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W' . c-9 ENTERGY~!
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A.e F . April l29, 1992- """"""E" U.S. Nuclear RWdulatory Comminnion
-Mail Station P1-137-
- LWashington,-D.C. 20555' TAttention: . Document Control Desk
Subject:
Grand Gulf Nuclear Station Unit 1 Docket - No'. 50-416 H
-License No. NPF-29
-Quarterly Status-Report ror Period Ending March 31., 1992 -
-Degraded Core Accident Ilydrogen Control Program
~GNRO-92/00047- -
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. Gentlemen:
The; Grand: Gulf Nuclear Station-(GGNS) Unit 1 Operating-I.icense requires-E
?that-Entergy. Operations,nInc. . submits quarterly reports on the status of 1the " Degraded Core Accident' Hydrogen Control Program." In response to that s
irequirement,:Entergy Operations, Inc. submits-'the attached report covering ithe; period January'1. 1992 through March 31, 1992.
t-l3 - Should you have(anyl questions concerning this-report, please contact *
.-Jewel Summers at (601)~437-2149.-
C ,
-Yours truly, w W c exac::--
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,WTC/JS/mtc attachment: i Quarterly- Status Report for _ Period' Ending March 31, 1992
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cc: Mr.- D.- C. Ilintz (w/a) _
Mr._ J. - L. Mathis -(w/a) _
Mr. R..B. McGehen (w/a)
HMr. N. S._Reynolds (w/a)
Mr.: U. L. Thomas (w/o)
Mr. Stewart D.,Ebneter.(w/a)
Regional Administrator U.S. Nuclear Regulatory Commission RegionL11
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- -101 Marietta St., N.W., Suite 2900 Atlanta, Georgia .30323 Mr. P. W. O'Connor, Project Manager (w/2)
Office of Nuclear-Reactor Regulation -
U.S. Nuclear _ Regulatory Commission Mail- Stop.13113 Washington,ED.C. -20555 1
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Attachment to GNRO-92/00047 i 1
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1: Quarterly Status Report for Period Ending March 31, 1992
" Degraded Core Accident Hydrogen Control Program" 1.0 . Introduction' This quarterly status report is submitted to comply with the Grand Gulf Nuclear Station (GGNS) ar it 1 Operating License. This requirement specifies that Entergy Operations, Inc. should provido quarterly reports outlining the status of the ongoing research program to address degraded core hydrogen control requirements. This report covers the first calendar quarter of 1992, ending March 31, 1992. ,
This report includes brief summaries of submittals made by Entergy Operati ins this quarter, along with summaries of mootings between the NRC Staff-and Entergy Operations. Entergy. Operations is participating in the' Hydrogen Control Owners Group.(IICOG) which is conducting generic'research and analyses to resolve the degraded core hydrogen control issue. Since the work completed by HCOG parallels Entergy Operations' program to resolve this issue, this report also includes
~
summaries of. meetings between the HCOG and the NRC. The meetings summarized in this report do not reflect a formal llCOG position with respect t'o any issue,_but represent Entergy. Operations' interpretation of those meetings, 22.0 ' Summary of'Entergy Opera gons m Inc. Submittals Entergy Operations made no submittals to the NRC on the Degraded Core
. Accident flydrogen _ Control Program during thia calendar quarter of 1992.
3.0~ Eummary of IICOG and NRC Hoetings t
No formal meetings were held between Eatergy Operations or llCOG and the NRC during this quartar.
4.0' ilydrogen Control Program Status
- The summaries and status of the lijdrogen Control Program es stated herein do not reflect the HCOG position with respect to any program, but represent Entergy Operations' interpretation of these programs.
The generic research.and generic analyses conducted by IICOG to resolve the degraded core hydrogen control issue are complete. In accordance with this, the NRC issued. a Safety rvaluation Report (SER) on he generic flydrogen C ntrol Program ?n August 10, 1990. The SER-documented the NRC's review of the generic Fydrogen Control Program and delineated which issues were considered closed by the NRC and which required. additional action by the HCOG and/or the individual t
utilities.
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'G9204091/SNLICFLR - S L
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' i Attachment.tc GNRO-92/00047 i D.- ,.
- ft 5.0 Sta_tus of Significa_nt Issues
- 1, Formal-NRC acceptance of IICOG's response to concerns identified in the
August 10, 1990 Generic Mark III. Coatainment liydrogen Control Safety Evaluation Repart (SER) is still pending. .
6.0 Planned- Activities for the Second quarter 1992 Following acceptable resolution of NRC issues relating to the generic SER, Entergy Operations will review its schedule for submittal of the GGNS Fir.a1 flydrogen Control Report, identify the remaining work necesL ry -for this submittal, and initiate work on the 'vnaining plant-specific tasks.
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