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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20195J6351999-06-16016 June 1999 Forwards Addendum to Rev 30 of GGNS Physical Security Plan IAW 10CFR50.54(p).Addendum Is Submitted to Announce Relocation/Reconfiguration of Plant Central & Secondary Alarm Station Facilities.Rev Withheld,Per 10CFR73.21 ML20195G0281999-06-0909 June 1999 Submits Summary on Resolution of GL 96-06 Re Eighteen Penetrations Previously Identified as Being Potentially Susceptible to Overpressurization ML20207F5041999-06-0202 June 1999 Forwards Updated Medical Rept IAW License Condition 3 for DA Killingsworth License OP-20942-1.Without Encls ML20206P2981999-05-13013 May 1999 Forwards Responses to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Cancelling 990402 Submittal ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J0941999-05-0404 May 1999 Forwards Proprietary & Redacted ME-98-001-00,both Entitled, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators. Rept ME-98-002-00 Re Flexible Wedge Gate Valves,Encl.Proprietary Rept Withheld ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20206D8171999-04-29029 April 1999 Informs NRC of Results of Plant Improvement Considerations Identified in GGNS Ipe,As Requested in NRC . Licensee Found Efforts Have Minimized Extent of Radiological Release in Unlikely Event That Severe Accident Occurred ML20206D7281999-04-28028 April 1999 Forwards South Mississippi Electric Power Association 1998 Annual Rept, Per 10CFR50.71(b).Licensee Will Submit 1998 Annual Repts for System Energy Resources,Inc,Entergy Mississippi,Inc & EOI as Part of Entergy Corp Annual Rept ML20206C9551999-04-22022 April 1999 Forwards 1999 Biennial Emergency Preparedness Exercise Scenario. Without Encl ML20205M1311999-04-0202 April 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Info Was Discussed During Conference Call with NRC on 990126.Wyle Position Paper Encl.Subj Paper Withheld ML20205H5861999-04-0101 April 1999 Requests Relief from ASME B&PV Code,Section XI for Period of Time That Temporary non-code Repair Was in Effect,Per 10CFR50.55a(g)(5)(iii) ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) ML20205A6511999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-416/99-01 on 990201-05.Corrective Actions:Program Will Be Implemented to Ensure Accessible Areas with Radiation Levels Greater than 1000 Mrem/H ML20204E7391999-03-15015 March 1999 Forwards Objectives for June 1999 Emergency Preparedness Exercise for Plant.Without Encl ML20207H9291999-03-0404 March 1999 Submits Update to Original Certification of Grand Gulf Nuclear Station Simulation Facility IAW Requirements of 10CFR55.45(b)(5) ML20207E3081999-03-0303 March 1999 Informs That GGNS Severe Accident Mgt Implementation Was Completed on 981223.Effort Was Worthwhile & Station Ability to Respond & Mitigate Events That May Lead to Core Melt Has Been Enhanced ML20207E3221999-03-0303 March 1999 Notifies of Change in Status of Mj Ellis,License SOP-43846. Conditional License Requested to Accommodate Medical Condition.Revised NRC Form 396 with Supporting Medical Evidence Attached.Without Encls ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20203A1551999-02-0101 February 1999 Forwards Grand Gulf Nuclear Station Fitness for Duty Program Performance six-month Rept for Reporting Period 980701-981231 ML20202G0791999-01-26026 January 1999 Informs That He Mcknight Has Been Permanently Reassigned from Position Requiring License to Perform Assigned Duties. License Is No Longer Needed,Effective 981231 ML20199K4151999-01-20020 January 1999 Forwards Proposed Addendum to Emergency Plan Changes Previously Submitted Via GNRO-98/00028 for NRC Review & Approval as Required by 10CFR50.54(q) & 50.4 ML20199K6771999-01-14014 January 1999 Provides Notification of Planned ERDS Software Change Scheduled to Take Place on 990215 ML20199D8811999-01-11011 January 1999 Submits Response to SE JOG Program on Periodic Verification of motor-operated Valves,In Response to GL 96-05 ML20199D9521999-01-0808 January 1999 Informs That CE Cresap,License SOP-4220-4,has Been Permanently Reassigned from Position Requiring License & No Longer Has Need for License,Per 10CFR50.74 ML20199A6081999-01-0606 January 1999 Submits List of Plant Info Brochures Disseminated Annually to Public & List of Updated State &/Or Local Emergency Plan Info,Per NRC Administrative Ltr 94-07, Distribution of Site-Specific & State Emergency Planning Info ML20202B7531998-12-21021 December 1998 Submits Ltr Confirming Discussion with J Tapia,Documenting Extension for Response to NOV 50-416/98-13.Util Response Will Be Submitted by 990212 1999-09-08
[Table view] |
Text
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, *:~
- . CORRECTED COPY TO CORRECT' v:-:- Entergt PARAGRAPH 3 ON ATTACHMENT
- PAGE $ of 6' Ent*'sy operatione,ine.
Operatlons
- .u.~ .
~+ 601 -F d W. 7. Cottle
, :,., n-
'C 4 T ( "4 August 15, 1991 U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Technical Appeal of the Denial of the Amendment Request For Reactor Protection System Instrumentation GNRO: 91/00149 Gentlemen:
By letter and SER dated July 10, 1991 the NRC denied a proposed aen to the Grand Gulf Technical Specifications which would have modifi*d a surveillance (STP) requirement for the flow biased simulated thermal pos -
trip instrumentation.
enclosed information.Entergy Operations wishes to appeal this technical d discuss this matter further.We would be happy to arrange an appeal m Yours truly, w r e-J0F/be Attachment cc: (See Next Page) hiodbO248910915 A p
PDR ADOCK 03000416 jd PDR G9108151/SNLICFLR pl
Augusc 15.-199L GNRO-91/00149 Page 2 of 3 cc: Mr. D. C. Hintz, w/4 Mr. J. Mathis, w/a Mr. R. B. McGehee, w/a Mr. N. S. Reynolds w/a Mr. H. L. Thomas, w,/a Mr. Stewart D. Ebneter, w/a Regional Administrator U.S. Nuclear Regulatory Commission Region-II 101-Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. L. L. Kintner, Project Manager, w/a Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail.Stop 11021 Washington, D.C. 20555 t
l L
G9108151/SNLICFLR
_-.-.-_u . . ~ . _ - - - _ _ - ----- -- -
[
Attachment Page 1 of 6 to GNRO.91/00:49 I Introduction e
" %rence 1, dated April 46, 1991, tc autaitted a request by Grand G u lf to modify V,
~
tally channel mentation in TScheck for the flow biased simulated thermai Table 4.3.1.1'1. rp power (
i The change was requested to reduce itch approved the same change for the Clinton Powj .
t The request was denied by the NkC on July 10, 1991 via Reference 3 .
}
In the SER accompanying the denial of the Grand Gulf request
, the Staff noted: !
"The STP trip signal is used by the reactor protection syst em to scram the I reactor to limit maximum rector power so as to maintain the minimum critical power ratio loss of foodwater above the appropriate safety limit for events such!
heating." '
i t
On this basis, the NRC concludedt v
"The requested chang 1s to the TS are 4*nied because the del ti e on of the would permit an undetected and unanalyzed incrI
{
As will be discussed in detail below, the STP trio signal is gnused Gulf reactor protection systen to maintaincurrently l
by limitthefor Grand any event. MCPRe safety above th -
In fact, any increase in thk v analyzed for the applicable Grand Gulf event (i.e., scram setpoint is well has been repeatedly reviewed and approved by the NRC..; scram is assumed), and r l i Grand Gulf FSAR ;,
i briefly discuss the arrangement of the Grand Gulf o FStR.Bef NSSS supplier (GE) for Grand Gulf's first cycle y the A separate volume of opers,j i description current c;rcle of operation. of those Chapter 15 events which For a particular or the were ! ;
i L htroduction current arialysis. includes instructions to the re orjer the to refer !'
l Chapter 15' also contains appendices which may u, date the Cycle 1 event
-descriptions. !
j Appendices include r6 analyses for l such initiatives as the Maximus Extended Operating Omain Again, (MEOD).mplicable the evi l Cycle 1 evont description in the appropriate Chapter 15 subsection will (
! the reader to any. applicable appendices for more current info rmation.
refer W
Grand since theGulf has employed-first FSAR update following this Cycle practice 1. (i.e. , CCSA and endices) Chapter 15 app '
G9108151/SNLICFLR 1
_ _ .- _ _ . __ - . _ _ _ - . - . . - -~_ - -
, Attachment Pago 2 of 6to GNRO.71/00143 Loss of FeedW*ar_Heatina (LFWH) Analyses the STP trip surveillance requirement and thengesubseque to historically taken. it is the only safety analysis for whichenial STP because trip credit e
has b The analysis methodology for this event changed significantly during Cyc As originally minimize licensed the calculated for Cycle severity of the 1, the LFVH analysis creditedo the STP transient.
An improved analytic mechodology, first employed during the MEOD analyses during Cycle en 1 and th '
repeated for each reload, assumes no STP trip (or any trip for that matter) .
1.
Initial Cycle 1 LFWH Analysis TheFSAR.
Gulf initial Jycle 1 LFWH analysis is discussed in Section 15.1 1 of .
the G rand With respect to the STP trip (also called the thermal power monitor trip)
Subsection 15 1.1.2.2 of the FSAR notes: ,
l
{
"The thermal power monitor sitigating the consequences (of this event.TPM) is the primary protection system Gulf plant design, reactor scram during the loss of transient scrag set would point. occur when the neutron flux exceeds the high APRM flux than the high thermal power scram set point by approximate percent.
Therefore, the loss of feedwater heating transient would be more i severe without the high thermal power trip scram design. This would lead to a higher operation." operating CPR limit and reduce the flexibility of niant In other words, rather than revising the CPR limit which would have unduly restricted In some sense, plant operation, Grand Gulf chose to credit the STP trip for Cycle 1 the need to credit the STP trip was an artificial situation .
necessitatedatby methodology thatthe limitations imposed by tha GE computer codes and analysis time.
Subsection 15.1.1.3.1 of the FSAR and its associated references discuss the mathematical Initial Cycle 1 analysta of (including modeling the LFWH sys.~. a poin' 'inetics core model) employed for the
! point kinetics models yield extremely conservative results for the LFWH event.
2.
Change in Analysis Methodology Subsequent to the initial Cycle 1 analyses for Grand Gulf, GE (and the industry) changed its approach to modeling and analyzing LFWH events.
l i
Rather than a steady state power level and other core conditions before a This approach, which was used on Grared Gulf for the MEOD end all subsequent enalyses discussed below, eliminated the need to credit any plant trip l (including the STP trip) in the course of demonstrating acceptable CPR results .
G9108151/SNLICFLR l
Attachment Page 3 of 6to GNRO 91/00149 Some may additional be helpful. background concerning the change in LFWH o o ogy analysis m A
entering loss ofthefoodwater heating event results in a decrease in feedwater reactor vessel. emperature t
the core (i.e., increases subcoolingThis lowers the temperature of the water enterin3 and thereby causes the core average p)o,wer to increase. reduces the average cor causes a void redistribution and a corresponding power redistributionThe While change in su the not change is a total core power increase, not all areas of increase at the same rate.
th.
e core This tends to flatten tne radial power distribution.
Due to the stored energy and mixing of feedwater in the downcomer and lo plenum with the recirculation flow, the temperature reduction at the core i (and, therefore, seconds to minutes.the power increase) occur relatively slowly - onorder the of maintain a quasi-equilibrium in which the water temperature, neutron flux distribution maintain their steady state relationships.
The LFWH analysis presented in FSAR Section 15.1.1 for Cycle 1 evaluated event with represent theacore transient thermal feedback hydraulics code using a point kinetics model to mechanisms.
The point kinetics model is a redistribution that occurs in this event and must assum that bound all the statepoints in the event.
model results in a large overprediction of the LFWH core power increaseConseq .
sudden increases or decreases of important paramete j beginning and and of the event bound those throughout the transiant. Therefore, performing appropriate. the LFWH analysis with a three-dimensional quasi-steady state code state core conditions) are determined based on the positive of the ccider feodwater, and the effect on CPR is calculated.
Since the radial power redistribution effects are accounted for in the methodology, the excessive core power overprediction and associated need to credit a trip is eliminated .
3.
Maximum Extended Operating Domain (MEOD) - Cycle 1 During Cycle operation 1 GE conducted and NRC approved analyses to support Grand Gulf in the MEOD.
l l A bounding analysis was performed using a standard DWR/6 All plant.abnormal
- operating transients, including the LFWH event were examined. In analyzing the l LFWH event, GE employed the revised steady state approach discussed above.
1 At the request of the NRC staff, a plant specific LFWH event was performed u the GE three dimensional BWR Core Simulator (Reference 4) docu approved GESTAR Amendment (Reference 5).
by Reference (Reference 7). 6 and approved by the NRC by letter dcted 15, AugustThis 1986 analysis was G9108151/SNLICFLR
Attachment Page 4 of 6 to GNRC-91/00149 was shown to bei bounded by the generic analysis.The core and ana analysis or any other, nortrip.
the Grand Gulf-specific LWH analysis assumed credit for t ,
Gulf FSAR (Revision 2) in December,The 1987.
results of these e Grandanalyses 4.
Cycle 2 Reload and LWH Event Analysis Grand f Gelf contracted with Advanced Nuclear Fuels (ANF) to provide forthe for C cIn fuel 2 and to conduct the relosd analyses necessary cycle. reload to fuelobtain NRC proval The Cycle 2 reload analyses for LWH utilized the ANT 3-D XMBWR stea cors the LWsimulator H event. code which is similar to the GE code used in the MEOD analy s s of Reference 8. The ANF generic analysis of the LWH event is documented in At the request of the Staff, Grand Gulf subeitted by Reference 9 a plant specific analysis of the LFWH event utilizing the XTGBWR code.
This analysis and the resulting delta CPR.provided the steady state conditions of ent the core be No credit was taken for the STP trip.
The Staff's Reference 10. review and approval of the Cycle 2 analysis is documented in
- 5. Subsequent Relocds steady state approach and NRC approved methodology.The ng a trip (or any trip) credited for achieving acceptable CPR resultsIn .
no instance was the STP employed a relatively new ANF computer code (CASM ame steady state approach described above which did not in trip.
".. . a complete new analysis was run for the LWH.
with the newly approved MICR08 URN-B/ ANT following the ab LWH was analyzed approved for Cycle 4, using an expanded GG1 data base."pproach previously NRC Conclusions in the Denial SER In denying the requested TS change to sodify the STP tri the NRC's SER indicates that the STP trip is necessary "p daily channel check
... to limit maximum reactor power so as to maintain the minimum critical power ratic above the appropriate safety limit for events such as loss of fSedwater heating."
G9108151/SNLICFLR
Attachment-to Page 5 of 6 GNRO-91/00149 This is a correct statoaant only for the initial portion of Cycle rand Gulf, until o 1 at G detail above.perstlom in the MEOD was approved by the Staff.
As discussed in function for the LFVN or other events.. et all subsequent times the STP trip pr In other words, the new LFWH analysis methodology limit. required no limit on reactor power to esintain CPR ey above th The SER concluded that the requested TS change was "... denied e because t deletion of the surveillance unanalyzed increase in the scram setpoint." requirement ... would permit an undetected and 55: ::17 ::: ;;;rfd:d $7 C:::d C:!" '::
per:: t: ::::h : :::, he;t:: tzed; :t MECT t: d :::S :y:!: ::!::d :
1 ::::!tc.
Th!: :;;::::t i: ; iv:! t t: 1:;;l : d i :x.:::;;; ::;;p!!:;;t!;::: CP"t-:
"The analysis provided by Grand Gulf for :::19::'
MEOD ; t%:and r ;12t:
each' 112:: c ' 6ha. -
cycle reload allow reactor #
results.
power STP (and any toother) reach trip. a now, higher steady state level and de industry approach to analyzing the nood for the STP complete and extensively reviewed by the NRC. e, trip has bee Previous NRC Approvals for Sfeilar Requests To our knowledge, at least two other BWRs have received NRC approval to the daily channel check for the STP trip - Forei-2 (Referenceand 12)Clinton Power Station (Reference 2).
In preparing requestu for changes to Technical Specifications it is Grand Gulf a practice approved by the NRC. to determine if steilar requests have been pre,viously e and mad
' In doing so, our intent is to ensure that we have NRC in the approval SERs. considered and addressed the safety issues rais conformed our request to include known issume raised as addressing Grand Gulf-specific concerns.
on other dock
, as well l
i i
G9108151/SNLICFLR
Attachmsnt to GNRO-91/00149 Pa9e 6 of 6 4 References 4
1.
Entergy Letter, GNRO-91/00043 dated April 26, 1991; "onReactor Pro System Instrumentation Surveillance Requirements."
2.
NRC Letter, John Hickman to Dale L. Holtzsher, dated January 31
, 1990.
3.
NRC Letter, Theodore R. Quay to William T. Cottle, dated , 1991.July 10 4
J.
1977. A. Wooley, "Threa-Dimensional BWR Core Simulator,", January NEDO-20953 5.
Reactor Fuel" (GESTAR) Ausust 1985 (GE Proprietary or
- 6. Entergy Letter, AECM-86/0174 Submittal." dated June 9, 1986; " Addendum to ME00 7.
NRC Letter, Lester L. Kintner to Oliver D. Kingsley dated August , 1986. 15 8.
Transient for Boiling Water Reactors", February 1986.XN
- 9. Entergy Letter, AECM-86/0273 Subalttal Additional Information (LOFWH, LOCA, Fuel Liftoff) " da .
10.
NRC 1986. Letter, Lester L. Kintner to Oliver D. Kingsley, Jr. dated October 24 11.
NRC Letter, Lester L. Kistner to William T. Cottle dated November 15
, 1990.
12.
NRC Letter, Theodore R. Quay to B. Ralph Sylvia, dated June 3
, 1988.
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j
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