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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
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.. lia 1 O Entargy Operations,Inc.
PO. Box 756 Port Gibson, MS 39150 I
Tel 601437-6470 W.K.Hughey Dwector Nuclear Safety & Fkwydatvry Affars December 15, 1998 i
l U.S. Nuclear Regulatory Commission l Document Control Desk Mail stop P1-37 Nashington, D.C. 20555
' subjects- Grand Gulf Nuclear station I Docket No. 50-416 License No. NPF-29 Response to the Request for Additional Information Regarding Generic Letter (GL) 92-08: Thermo-Lag Fire Barriers, dated June 19, 1998 GNRO-98/00101 Gentlemen:
Generic Letter (GL) 92-08 was issued by the NRC to obtain information needed to verify that Thermo-Lag 330-1 fire barrier systems comply with ,
NRC fire protection requirements for protecting equipment required to l achieve and maintain safe shutdown in the event of a fire.
Reporting Requirement Item 2(c) of GL 92-08 requests information concerning the ampacity dorating of cables enclosed in Thermo-Lag fire barriers and the evaluation and application of ter.t results performed to
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determine the ampacity dorating of Thermo-Lag barriers.
By our letter dated June 5, 1997 (Reference 1), GGMs provided a response to the staff's Request for Additional Information (RAI) dated February 26, 1997 (Reference 2). The staff reviewed our June 5, 1997 submittal and ]
identified items needing clarification. The staff's RAI dated June 19, j 1998 (Reference 3) solicited responses from GGNs for the items requiring j clarification. The items contained in the staff's June 19, 1998 letter I were discussed between GONS and the NRC during teleconferences conducted l on June 17, 1998 and September 24, 1998, respectively. The intent of these ;
discussions was to assess the staff's understanding of our conceptual plan j of action for addressing the staff's concerns delineated in the June 19, '
1998 RAI and to facilitate satisfactory resolution of Thermo-Lag ampacity dorating issues pursuant to Generic Letter 92-08 for GGNs. ,
I Attachment 1 provides our responses to the June 19, 1998 RAI. These l responses have been developed based on standard industry practices and/or methodologies previcusly found acceptable by the NRC.
During the september 24 teleconference, the staff specifically requested that our response discuss certain elemen% discussed during the teleconference. +
i% gyI 9912230135 981215 PDR ADOCK05000416]b P PDR iff, j L 1
l l December 15, 1998
- GNRO-98/00101
- Page 2 of4 ;
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i j These elements include identification of any circuits with negative j i ampacity dorating design margin and corrective actions planned for 4
- monitoring those circuits to ensure their continued acceptability, if I i warranted.
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Attachment 1 includes identification of those circuits with negative design margin for dorated cable ampacity. A detailed service life l j evaluation has been performed for the circuits encompar. sed by this '
j criteria and concluded that these cables are acceptable, with no l 4 corrective actions currently necessary. To ensure that pre-established j Full Load Amp (FLA) currents for these circuits are not exceeded, we plan l 4 to collect voltage and current data following maintenance activities that I may potentially result in FLA currents for these circuits being exceeded.
Should dorated ampacity limits be exceeded, an engineering review will be performed to access appropriate corrective actions.
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f During the June 17 teleconference, GONS was also requested to discuss a i question (Question 5) that was contained within s May 20, 1998 advance 1
copy of the June 19 Request for Additional Information. This question i requested clarification of the grouping factor applied to multiple i conduits contained within a single Thermo-Lag clad raceway at GONS.
j clarification by GON8's staff that the grouping factor applied w.as based I j on a worst case assumption prior to field walkdowns to confirm actual I i
raceway configurations. Subsequent to the field walkdowns, we identified l 4 that the assumed grouping factor was overly conservative for GONS l 4
configurations. Nevertheless, we elected to retain this additional I conservatism for the grouping factor applied to conduits enclosed within i GONS Thermo-lag clad raceway. Following this clarification, the staff withdrew guestion 5 from the June 19, 1998 Request for Additional Information.
This information is being submitted under affirmation in accordance with 10 CFR 50.54(f)(Attachment 2).
Please contact Charles E. Brooks at (601) 437-6555 should you have any questions, or require additional information.
Yours truly, WKE/CEB/ceb cc: see Next Page
I December 15, 1998 GKRO-98/00101 Page 3 of4 I
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l l WKN/CES/ cab attachment: 1. GONS response to the NRC Request for Additional
! Information, dated June 19, 1998
- 2. Affirmation, per 10 CPR 50.54(f) of the GGNS Response l to 92-08 Request for Additional Information, dated June 19, 1998 cca Ms. J. L. Dixon-Herrity, GGNS Senior Resident Inspector Mr. R. B. McGehee (w/a)
Mr. R. S. Reynolds (w/a)
Mr. H. L. Thomas (w/a) i Mr. Ellis W. Merschoff (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission l Region IV 611 Ryan Plaza Drive, suite 400 Arlington, TX 76011 l Mr. J. N. Donohew, Project Manager (w/2)
(
office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l Mail Stop 13H3 ,
j Washington, D.C. 20555
)
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becember 15, 1998 GWRO-98/00101 Page 4 0f 4 a
bcca' File (LCTS/RPTS) (w/a).
File (Eard Copy) (w/a)
File (MS&RA) (w/a) ;
File (Central) (w/a) (14 )
3 cctuall' Mr. G. R. Ashley (AMO-LIC) !
- Mr. T. E. Barnett Mr. W. J. Beck (RB-LIC)
- Mr. E. D. Berryhill Mr. S. J. Bethay(ECH-LIC) l Mr. D. G. Best
!- Mr. C. A. Bottomiller l' Mr. C. E. Brooks
. Mr. R. W. Byrd i Mr.='/. R. Cameron ,
- . Mr. M. R. Cumbest
- Mr. D. W. Chipley 1
- . Mr. L. F. Dale j' Mr. L. F. Daughtery 1 Mr. C. M. Dugger (VP-W3) j Mr. W. A. Eaton i Mr. Ra K. Edington (VP-RB) j Mr. C. W. Elisaasser 4
Mr. E. C. Ewing (W3-LIC)
^,, Mr. W. K. Hughey j Mr. M. L. Bumphries :
), Mr. C. R. Ettchinson (VP-ANO)
Mr. C. W. Lambert' ,
j Mr. G. B. Lantz !
Mr. J. R. McGaha (ECH) j Mr. D. C. Miss (ANO) l Mr. R. V. Moomaw Mr. J. C. Roberts j Mr. 8. A. Rogers Mr. M. V. Rohrer i Mr. C. D. Stafford i Mr. L. G. Temple Mr. J. E. Venable Mr. D. W. Vinci (W3) i Mr. R. I. Wright I
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Attachment 1 to GNRO-98/00101 Grand Gulf Nuclea? Station
! Response to Generic Letter 92-08 Request for Additionkl Information dated June 19, 1998 l'
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GNRO-98/00101 Attachment 1 The following items require clarification as delineated in the staff's RAI dated June 19, 1998. These items were identified as a result of the staff's review of the GGNS response to the GL 92-08 Request for Additional Information, dated June 5, 1997.
GGNS Discussion:
To conservatively simplify the ampacity derating methodology, GGNS will use the ICEA Standard 40 degree C temperature for ampacity derating in the OC302 room rather than using 30 degrees C. Also, for the one GGNS tray that is clad with Thermo-Lag 330-1 nominal 1-1/4" thick panels the original 48% derating will oe used rather than 44%. Therefore, the ampacity derating correlation established in the paper entitled, " Fire Endurance and Ampacity Testing of One- and Three-Hour Rated Thermo-Lag Electrical Raceway Fire Barrier System" authored by Mark H.
Salley and Kent W. Brown will not be used. For the continuous duty constant KVA equipment (Z51-Control Room HVAC and Z77 -
Emergency Switchgear and Battery Rooms Ventilation fan motors) that has power cables contained within Thermo-Lag enclosed raceways, field measured voltage and Full Load Amp (FLA) current values have been taken. The PLA values have been corrected to the minimum anticipated grid voltage (0.992 per unit) to ensure that the highest anticipated normal operating current is used to evaluate the ampacity margin. Measures have been established to ensure that the corrected FLA currents for these circuits are not exceeded. As a result of applying these very cor.servative measures, all but three of the constant KVA continuous duty motor cables have been found to have acceptable design margins for derated cable ampacity. A detailed cable service life evaluation was performed for the three cables of concern. The useful service life for cables 1AB561041 (Q2Z77B001A Low Speed),
1AB561181 (Q2Z77C001AA Low Speed), and 1AB561201 (Q1Z77C001AA Low Speed) has been evaluated using Arrhenius methodology and found to be acceptable. The service life evaluation
- conservatively uses 40 degrees C for the entire 3 month summer period and 30 degrees C for the remaining 9 months of the year.
Data obtained from the Plant Data System indicates that while the peak daily OC302 room temperature does occasionally exceed 30 degrees C during the summer months, it rarely ever approaches 40 degrees C. Therefore, the service life evaluation is very conservative for the conditions normally experienced by the subject cables, and would even encompass possible increased temperatures resulting during an unexpected fan outage.
Request for Additional Information - Questico 1:
In response to Question 2 of the staff's RAI, it is stated that
" Room OC302 has an average temperature of approximately 80 degrees F and typically a temperature of less than 86 degrees F (30 degrees C)." The ICEA Standard allows an ampacity factor of 1.09 for an ambient temperature of 30 degrees C provided the room temperature never exceeds that temperature.
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-l emc~98/00101 Attachment 1
.Therefore, a room temperature of 40 degrees C for some length of time and 20 degrees C for the remaining period, with the average-being 30. degrees C, will not qualify for an ambient room temperature of 30 degrees C. Confirm that the ambient temperature of Room OC302 will not ex6eed 30 degrees C. In addition, discuss the procedure that applies to monitoring and controlling the room temperature.
GGNS Response to Question 1:
i GGNS will use the standard 40 degree C ambient temperature in OC302 for determining derated cable ampacity.
Peak daily room temperature data was obtained from the Plant )
Data System for a perica of several years for purpose of ;
developing a worst case temperature profile. This temperature profile has been used only in performing the service life evaluation for cables 1AB561041, 1AB561181, and 1AB561201. The I service life evaluation conservatively uses 40 degrees C for the l entire 3 month summer period and 30 degrees C for the remaining 9 months of the year. Data obtained from the Plant' Data System indicates that while the peak daily OC302 room temperature does occasionally exceed 30 degrees C during the summer months, it I rarely ever approaches 40 degrees C. Therefore, the service life evaluation'is very conservative for the conditions normally experienced by tne subject cables, and would even encompass possible increased temperatures resulting during an unexpected fan outage.
Dequest for Additional Information - Question 2:
Provide (1) the details of the analytical method used to calculate an ampacity correction factor of 44% and (2) a copy of the paper entitled, " Fire Endurance and Ampacity Testing of One-and Three-Hour Rated Thermo-Lag Electrical Raceway Fire Barrier System." Discuss if the paper is endorsed by the IEEE?
GGNS Response to Question 2:
l The 44% derating is no longer being used. GGNS will use the 48%
derating published in Omega Point Laboratories Report No. 11960-97333, "Ampacity Derating of Cables Enclosed in a Cable Tray with Thermo-Lag 330-1/770-1 upgrade Electrical Raceway Fire i Barrier System (ERFBS)" prepared for TVA and TSI. The 44%
l ampacity derating correlation established in the paper entitled, j- " Fire Endurance and Ampacity Testing of One- and Three-Hour Rated Thermo-Lag Electrical Raceway Fire Barrier System" i authored by Mark H. Salley and Kent W. Brown will not be used.
Therefore, the ..'ipacity derating concern for 44% is negated.
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! Request for Additional Information - Question 3:
l It is the staff's understanding that the licensee stated to the effect that all loads except the emergency switchgear and battery rooms cooling motor will have at least 100% of the rated voltage for all conditions. The emergency switchgear and battery rooms cooling motor will have instead at least 98% of rated voltage for all conditions. Hence, no adjustment of full-load current for constant KVA loads due to voltage contingencies is required. Confirm that these statements are correct for Grand Gulf and discuss the effects of variation in voltage experienced by the constant KVA loads in the past at Grand Gulf.
GGNS Response to Question 3:
GGNS has used the minimum anticipated grid voltage (0.992 per i unit) in determining the minimum available terminal voltage for the continuous duty constant KVA equipment (Z51-Control Room HVAC and Z77 - Emergency Switchgear and Battery Rooms
- Ventilation fan motors) that has power cables contained within Thermo-Lag enclosed raceways. As expected, all of these fan motors would experience less than 100% of rated voltage for the j 0.992 pu condition. However, as discussed below this is a
, concern for only three cables and these have been evaluated and found to be acceptable.
l For this same continuous duty constant KVA equipment, field measured voltage and FLA current values have been taken. The FLA current values have been corrected to the minimum anticipated grid voltage (0.992 pu) to ensure that the highest anticipated normal operating current is used to evaluate the l cable ampacity margin. As a result of applying these very conservative measures, all but three of the constant KVA continuous duty motor cables have been found to have acceptable design margins for derated cable ampacity. A detailed cable service life evaluation was performed for the three cables of l concern. The useful service life for cables 1AB561041 l
(Q2Z77B001A Low Speed), 1AB561181 (Q2Z77C001AA Low Speed), and 1AB561201 (Q1Z77C001AA Low speed) has been evaluated using Arrhenius methodology and found to be greater than 40 years under the evaluated conditions. 1 i
1 Measures have been established to ensure that the corrected FLA l currents for these circuits are not exceeded. Tnese measures 1 require that voltage and current measurements are taken when any activity is performed which could cause the corrected FLA current of the equipment to be exceeded. If the corrected FLA current of the equipment exceeds the derated ampacity limits I
established, Engineering must be notified so that a detailed review can be performed and the appro;riate corrective action initiated, if necessary.
' The evaluations performed indicate that no corrective actions are currently necessary. The measures that are being established will ensure that if conditions change in such a manner as to affect these evaluations, Engineering will be i notified so that appropriate corrective actions can be initiated 1 as necessary.
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f GLUto-99/00101 Attachusent 1
. Request fee Additional Information - Question 4:
In response to Question 1 of the staff's RAI, the licensee stated that an ampacity derating factor of 48% is_used for the configuration of two horizontal conduits enclosed by Thermo-Lag; however, an ampacity derating factor of 44% was calculated for the conduits using the analytical method described in the response to Question 2 of the staff's. RAI. Discuss which derating factor is correct and identify which raceways enclosed by Thermo-Lag would have sufficient design margin given an ampacity derating factor of 48%. I I
GGNS Lesponse to Question 4:
The previously used 44% derating did not apply to conduit configurations. However, GGNS currently uses only the 48%
derating, therefore this clarification is no longer necessary. l l
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mmo-98/00101 Attachment 1
References:
- 1. -Letter J. J. .Hagan to the U. S. Nuclear Regulatory Commission, dated' June 5, 1997 Response to the " Request'for Additional Information Regarding Generic Letter 92-08 (GL) Item 2(c): '
Thermo-Lag Fi. Barriers" dated February 26, 1997.
- 2. Letter U. S. . Nuclear Regulatory Commission to J. J. Hagan, dated February 26, 1997 " Request for Additional Information Related to Thermo-Lag Fire Barriers, Generic Letter 92-08, Grand Gulf Nuclear Station,. Unit 1 (TAC No. M85554)".
- 3. Letter U. S. Nuclear Regulatory Commission to J. J. Hagan, dated June 19, 1998 " Request for Additional Information Related to Thermo-Lag Fire Barriers and Generic Letter 92-08 for Grand Gulf Nuclear Station, Unit 1 (TAC No. M82809)".
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, CNRO-98/00101:
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1 Attachment 2 to l
i GNRO-98/00101 l Grand Gulf Nuclear. Station ,
Response to Generic Letter 92-08' l'
Request for Additional Information dated June 19, 1998 Affirmation per 10CFR50.54(f) l l
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. , CNRO-98/00lOl BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET NO. 50-416 IN THE MATTER OF ENTERGY MISSISSIPPI and SYSTEM ENERGY RESOURCES, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION and ENTERGY OPERATIONS, INO.
AFFTRMATTON I, William K. Hughey, state that I am Director, Nuclear Safety & Regulatory Affairs of Grand Gulf Nuclear Station; that on behalf of Entergy Operations, Inc., System Energy Resources, Inc., and South Mississippi glectric Power Association, I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Commission, this response (GNRO-98/00101) to the Generic Letter 92-08 Request for Additional'Information dated June 19, 1998 for Grand Gulf Nuclear Station; that I signed this response as Director, Nuclear Safety & Regulatory Affairs of Grand Gulf Nuclear Station, and that the statements made and the matters set forth therein are true and correct to
- - .the best of my knowledge, information and belief, h
William i(. Hughey STATE OF MISSISSIPPI COUNTY OF CLAIBORNE SUBSCRIBED AND SWORN TO before me, a Notary Public, in and for the County and
- j. -Sthte above named, this /F # day of necamhar, 1998.
(SEAL).
_ q Notary #Public
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th m ETATiMC6 NOTANY REJC W sneur $Ut Y
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