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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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January 9, 1991 w. T. cottie
. 4 m U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Ati.ention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 !
Docket No. 50-416 License No. NPF-29 >
Current Cycle Safety Analysis, Revision 3 GNRO-91/00003 Gentlemen:
Entergy Operations, Inc. hereby transmits one signed original and ten copies of Revision 3 to the Current Cycle Safety Analysis (CCSA), for L Grand Gulf Nuclear Station (GGNS).
The'CCSA provides information on the current GGNS fuel cycle operations and contains analyses supporting operation and the current fuel reload.
Analyses included in the CCSA have been approved by the NRC either through specific review of the GGNS reload applications or as topical reports submitted by vendors.
The CCSA was ce.veloped to provide a convenient source for current accident and tra.nsient analyses. The CCSA is considered part of the Updated Final Safety Analysis Report (UFSAR), and will be updated at least within 60 days of the start of every cycle. Revision 2 was submitted June 30, 1989 (AECM-89/0110) and reflected analyses to support =
GGNS Cycle 4. This revision to the CCSA reflects the Cycle 5 fuel reload accomplished during the fourth GGNS refueling outage which occurred in late 1990.
The Advanced Nuclear Fuels (ANF) Corporation report, ANF-89-171(P),
Volumes 1 and 2, submitted as part of Attachment 2 to this letter contains information considered by ANF to be proprietary. In accordance l with 10CFR2.790(b), the enclosed affidavit (Attachment 1) executed by R. A. Copeland of ANF provides the necessary information to support the withholding of the subject report from public disclosure.
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f January 9, 1991 GNRO-91/00003 Page 2 of 3 As required by 10CFF50.71(c)(2) and as authorized by Entergy Operations, I hereby certify, to the best of my knowledge, Information and belief, that the information given in the attached CCSA Revision 3 accurately represents changes made since the previous submittal, necessary to reflect information and analyses submitted to the NRC or prepared pursuant tn NRC requirement.
If you have any questions, please contact this o'fice.
Yours truly, 4m T" W WTC/ PRS /ams attachment: 1. ANF Affidavit
- 2. CCSA Revision 3 cc: Mr. D. C. Ilintz (w/c)
Mr. J. Mathis (w/a)
Mr. R. B. McGehne (w/o)
Mr. N. S. Reynolds (w/o)
Mr.11. L. Thomas (w/o)
Mr. Stewart D Ebnet.cr (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georg ia '0323 Mr. L. L. Kintner, Project Manager (w/o)
Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Hall Stop 11D21 Washington, D.C. 20555 A9012072/SNLICFLR - 2
f: 1 Attachment l'to GNRO-91/00003 i l
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ADVANCED NUCLEAR FUELS CORPORATION .
AFFIDAVIT [
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A F FID AVIT
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COUNTY 07 BENTON )
I, R. A. Copoland being duly sworn, hereby say and depose:
- 1. 1.am Manager, Reload Licensing, for Advanced Nuclear Fuols Corporation,
("ANF"), and as such I am authorized to oxocute this Affidavit.
- 2. I am familiar with ANF's detailed document control system and policies which
_ govern the protection and control of information.
- 5. I am famillar with the topical report ANF-89-171(P), Volumos 1 and 2 ontitled
" Grand Gint 1 ANF 1.4 Design Report Mechanical, Thermal-Hydraulic and Neutronic Design for Advanced Nuclear Fuels 9x9 5 Fuel Assemblies," referred to as " Document." information contained in this Document has boon classified by ANF as propriotary in accordance with the control system and policios established by ANF for the control and protection of information,
- 4. The Document contains information of a propriotary and confidential nature and is of tho type customarily hold in confidence by ANF and not made available to the public.
Based on my experience, I am aware that other. companies rogard information of the kind contained in the Document as proprietary and confidential.
- 5. The Document has beeri made available to the U.S. Nuclear Regulatory Commission in confidence, with the request that tho information contained in the Document will not be disclosed or divulgod, t ._ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - _ - _ _ _ _
. / ..
AFFIDAVIT Page 2
- 6. The Document contains information which is vital to a competitive advantage of ANF and would be helpful to competitors of ANF when competing with ANF.
- 7. The information contained in the Document is considered to be proprietary by ANF because it reveals certain distinguishing aspects of ANF licensing methodology which secure competitive advantage to ANF for fuel design optimization and marketability, and includes information utilized by ANF in its business which affords ANF an opportunity to obtain a competitive advantage ever its competitors who do not or may not know or use the information contained in the Document.
- 8. The disclosure of the proprietary information contained in the Document to a competitor would permit the competitor to reduce its expenditure of money and manpower and to improve its competitive position by giving it valuable insights into ANF licensing methodology and would result in substantial harm to the competitive position of ANF.
- 9. - The Document contains proprietary information which is held in confidence by ANF and is not available in public sources.
- 10. . In accordance with ANF's policies governing the protection and control of information, proprietary information contained in the Document has been made available, on a limited basis, to others outside ANF only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 11. ANF policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 12. -Information in this Document provides insight into ANF licensing methodology _
developed by ANF. ANF has invested significant resources in developing the methodology as
AFFIDAVIT Page 3 well as the strategy for this application. Assuming a competitor had available the same background data and incentives as ANF, the competitor n ::n, at a minimumi develop the information for the same expenditure of manpower and money as ANF.
THAT the statements made hereinabove are, to the best of my knowledge, information,
, and belief, truthful and complete.
FURTHER AFFIANT SAYETH NOT.
r SUBSCRIBED before me this /0 day of October .1990.
cM ON (u_
Susan K. McCoy N NOTARY PUBLIC, STATE OF A INGTON MY COMMISSION EXPIRES: 1/1 2
Attachment 2 to GNRO-91/00003 REVISION 3 0F Tile GGNS UNIT 1
> CURRENT CYCLE SAFETY At!ALYSIS A9012072/SNLICFLR - 5
GG
- CCSA n
L Entergy Operations, Inc.
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 Revision 3 Instructions For Filing Revision 3 1,- Insor't the " Revision 3" tab, transmittal le"cer (GNRO-91/00003) and this instruction sheet into the back of the CCSA Volumn.
2.. Remove and insert the pages and topical reports listed below. Dashes
(---) in the remove or insert column indicato no action required.
REMOVE INSERT CCSA Cover Sheet CCSA Cover Sheet TAB, "Page Index" Page Index Table of Contents- Table ,f Contents Introduction (all pages) Introduction (all pages)
ANF-88-1' (all pages) ANF-90-022, Revision 2 (all pages)
ANF-88-15.-(all pages) ANF-90-021, Revision 2 (all pages)
XN-NF-80-19(P)( A), Volume 4, ----
Revision 1.(all pages)
XN-NF-80-19(P), Volume 4, ----
Supplement ~1 (all pages)
NESDQ-88-003 Revision 0- ANF-89-171(P), Volumes 1 and'2 (all-pages) (all pages) t r
A9012072/SNalCFLR - 6 u
..m. , _, , ____ _ _ _ _ _ _ _ _ _ _ _
GRAND GULF NUCLEAR STATION UNIT 1 CUP 2ENT CYCLE SAFETY ANALYSIS (CCSA) i M9012071/SNLICFLR - 1 Rev. 3 01/91 .3 1
f _
00 CCSA J' AGE INDEX Page Revision Cover Sheet 3 Page Index 3 Tabic of Contents 3 Introduction Cover 3 Sheet 1 3 2 a 3 3 4 3 5 3 6 3 3
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M9010152/SNLICFLR 1 Rev. 3 01/91
CURRENT CYCLE SAFETY ANALYSIS
-(CCSA)
Table of Contents Tab Description 1- Introduction 2 ANF-90-022 Grand Gulf Unit 1 Cycle 5 Reload Analysis Revision 2 3
3 ANF-90-021 Grand Gulf Unit 1 Cycle 5 Plant Transient Revision 2 Analysis 4 XN-NP-86-37 (P) Generic LOCA Break Spectrum Analysis for BWR/6 Plants 5 Deleted 6 XN-NF-825 (P)(A) BWR/6 Generic Rod Withdrawal Error Analysis, Supplement 2 MCPR for Plant Operations Within the Exte8ded Operating Domain 7 ANP-88-183 (P) Grand Gulf Unit i Reload XN-1.3, Cycle 4 3 Mechanical Design Report 8 ANF-89-171 (P) Grand Gulf 1 ANF-1.4 Design Report Mechanical, Volumes 1 and 2 Thormal-Hydraulic and Neutronic Design for Advanced Nuclear Fuels 9x9-5 Fuel Assemblies Revision 0 AECM-87/0234 Transmittal letter Revision 1 AECM-88/0188 Transmittal letter and Revision 1 Insert Instructions ,
Revision 2 AECM-89/0110 Transmittal letter and Revision 2 Insert Instructions Revision 3 GNRO-91/00003 Transmittal letter and Revision 3 Insert Instructions 3
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INTRODUCTION 3
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l.0 Background Performing 10CFR50.59 evaluations requires the review of analyzed events presented in the UFSAR. In the process of performing such evaluations, it was ?
recognized that the UFSAR annual revision may not include reload analyses performed for the current plant operating cycle due to the relative timing of the cycle startup and the revision submittal.
It was further recognized that some of the analyses presented in the UFSAR form the basis for subsequent analyses performed for future cycles.
These analyses typically require little revision from cycle to cycle unless a significant change in fuel type or methodology is made. The reload analyses 3
that are repeated each cycle address such changes in fuel type or methodology and either complement or are based on these " baseline" analyses provided in the UFSAR. Also, during any given cycle, additional analyses may be performed l 3 to support operations, procedural changes, technical specification changes, etc.
To provide a ready access to current cycle analyses and their relationship to baseline analyses for 10CFR50.59 and other evaluations, this
" Current Cycle Safety Analysis" (CCSA) document was developed. Analyses included in the CCSA have been approved by the NRC either through specific review of Entergy Operations applications or as topical reports submitted by l3 vendors. The CCSA is considered part of the UFSAR, is controlled by administrative procedure, and is maintained current consistent with 10CFR50.71(e).
The CCSA offers a convenient means apart from the UFSAR annual revjalon to provide the latest accident and transient analysis results to personnel using this information. It is intended that the CCSA will be updated at least within 60 days of the start of every cycle, and more frequently depending on the nature and scope of changes accumulated. l3 2.0 . Scope and Description The CCSA is related to the UFSAR as an integral updated document. 3 Sections in the UFSAR that are af fected by subsequent analyses presented in the CCSA-refer the reader to the CCSA and, therefore, the current analyses.
It is intended that before performing a review of analyses presented in -
the UFSAR, the reader is to consult Table 1 of the CCSA 9nd determine whether the analysis of interest is included in the CCSA. If the analysis is in the CCSA, the review should commence with the document in the CCSA assisted by baseline information presented .n the UFSAR,'as required. If the analysis is not in the CCSA,-it is an Indication that the information in the UFSAR represents the latest analyses on that subject and that the review should
. proceed using the UFSAR.
The UFSA; will be revised annually to include information from the CCSA that is judged to be of a permanent baseline nature. This information will 3
then be deleted from the CCSA. The UFSAR will also include references directing the reader to the appropriate sources for analysis not incorporated in the specific sections of-the UFSAR.
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The non-baselinn cycle related analyses that are presented in the CCSA 3 provide the current cycle analyses. These are replaced as they become superseded each cycle.
2.1 Analyzed Events The analyzed events presented in the CCSA are those for which the description contained in the UFSAR is not applicable to the current cycle.
Analyses described in the UFSAR that are still applicable to the plant in the current cycle are not presented in the CCSA. Thus, sections in the UFSAR that 3 do not refer to the CCSA are applicable as presented. For those sections that contain a reference to the CCSA, a review of the analyses presented in the CCSA is required.
2.2 Presentation of Analyzed Events CCSA analyses are provided as attachments identified by their document numbers. A listing of these documents along with titles and the events analyzed is provided in Section 3.0 below.
2.3 UFSAR-CCSA Cross Reference Listing Table 1 " Summary of Analyzed Events" provides a cross-reference listing of UFSAR events analyzed for the current cycle to CCSA attachments. Table 1 relates the event with its UFSAR section, the primary purpose for analyzing 3
.the event, and the CCSA attachmerit containing the current cycle analysis of this event.
For the sake of completeness, UFSAR sections presenting methodologies, design bases, and design descriptions have also been listed to provide an appropriate cross-reference to vendor information for these modeling issues.
The " event" column states " Methods" for these entries.
2.3.1 This section provides explanation of column headings found in Table 1.
UFSAR -
The Section in the UFSAR in which this event in Section addressed. If the event has not been previously addressed in the UFSAR, it is so stated, j3 Event -
This column identifies the event analyzed.
Primary -
The primary purpose (parameter and/or conditions Purpose evaluated) for performing this specific analysis.
CCSA -
Identifies the appropriate G:SA attachment which Attachment provides the analysis description and results for the event of interest.
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L 12.3.2 The following defines acronyms used in Tablo 1, CPR -
Critical Power Ratio CS -
Coro Stability ELL -
Extended Lond Lino FLE -
Fuel Loading Error 1
FWCF -
foodwater Controllor Falluro '
FWil0S -
Foodwater ileator Out of Servico ICF -
Increased Corn Flow LOFWil -
Loss of Foodwater llonting transient l
LRND -
Load Reject No Bypass-(also known as GLR for Generator Load Rejection)
RDA -
Rod Drop Accident RWE -
Rod Withdrawal Error SLHCPR -
Safety Lim.lt MCPR SLO -
Single Loop Operation
-3.0 CCSA Attachments Tho- following lists attachments found in the CCSA.
- 1. -ANF-90-022 Grand Oulf Unit 1 Cycle 5'Roload Analysis Revision 2 Event - SI.0 ;
LOCA; CS; FLE; RDA.
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- 2. ANF-90-021 Grand Grand Unit 1 Cycle 5 Plant Transient Analysia Rovision 2 Even t. : LOFWil; FWCF; LRND; RWE; Flow Excursion; Overprossurization
- 3. XN-NF-86-37 (P) Generic LOCA Dreak Spectrum Analysis for BWR/6-Planta Event: LOCA
- 4. Deleted
- 5. XN-NF-825 (P)(A) BWR/6 Conoric Rod Withdrawal Error Analysis, Supplomont 2 HCPR for Plant. Operations Within the Extended 2h OperEtIng Domain M9010152/SNLICFLR 3 Rev. 3 01/91
- 6. ANF-88-183 (P) Grand Gulf Unit 1 Reload XN-1.3, Cycle 4 ,
Mechanical Design Report I
- 7. ANF-89-171 (P) Grand Gulf 1 ANF-1.4 Design Report Mechanical, Volumes 1 and 2 Thermal-Hyrdraulic and Neutronic Design for Advanced Nuclear Fuels 9x9-5 Fuel Assemblies l
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TABLE 1 Summary of Analyzed Events UFSAR SECTION EVENT PRIMARY PURPOSE CCSA ATTACHMENT 4.1 Methods General analysis ANF-90-022 techniques, summary fuel description 4.2 Methods Fuel mechanical design ANF-90-022 description ANF-88-183 (P)
ANF-89-171'(P) 4.3- Methods Nuclear design ANF-90-022 description 4.4 Methods Thermal-hydraulic ANF-90-022 ;
design description 4.4'.4.6 CS Define detect and ANF-90-022 suppress region 5.2.2 Overpressurn Overpressure ANF-90-021 protection SA- ASME over- MSIV closure Max ANF-90-022 pressurization pressure ANF-90-021 3
6.3.3 ECCS Peak Clad ANF-90-022 Performance Temperature '
.15.0.3.3- Safety Limit SLMCPR ANF-90-022 ANF-90-021 15.1.1 LOFWH CPR with reduced FW' ANF-90-021 temperature 15.1.2- FWCF- CPR at rated ANF o^-021
-15D -FWCF CPR with ICF ANF .'0-021 15D- FWCF CPR with ELL ANF-90-021
-15D 15/CF CPR ac Power below ANF-90-021 40% (w/o direct scram) 15D FWCF CPR - w/o bypass ANF-90-021 ISD FWCF CPR with FWHOS ANF-90-021 M9010152/SNLICFLR 5 Rev. 3 01/91
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l TABLE-1 Summary of Analyzed Events (Cont.)-
UFSAR SECTION EVENT PR1HARY PURPOSE CCSA ATTACllMENT l i
-15.2.2 LRNB CPR at rated ANF-90-021 1
15D LRNB CPR with ICF ANF-90-021 )
i 15D LRNB CPR with ELL ANF-90-021 15D LRNB CPR at power below ANF-90-021 40% (w/o direct scram)
ISC SLO Operation with one ANF-90-022 loop out of service 15.4.1, 2 RWE CPR vs. Power ANF-90-021 3 XN-NF-825 (P)(A),
Supplomont 2 15.4.7 FLE CPR - Misloaded ANF-90-022 bundle 15.4.9 RDA Enthalpy ANF-90-022 deposition 15.6.5 LOCA Dotormino break' XN-NF-86-37 (P) location, limiting-break size 15D Flow Runout- CPR & MAPLilGR- :ANP-90-021 vs. Flow t -.
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ANF-90-022 I REVISION 2 f'em,.b w c
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%fy p , ADVANCEDNUCLEARFUELSCORPORATION GRAND GULF UNIT 1 CYCLE 5 RELOAD ANALYSIS AUGUST 1990 A Siemens Comoany
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