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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:M82809 |
| | | stage = RAI |
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| y REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-08. THERMO LAG FIRE BARRIERS | | y REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-08. THERMO LAG FIRE BARRIERS |
| .ENTERGY OPERATIONS. INC. | | .ENTERGY OPERATIONS. INC. |
| GRAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-416 Entergy Operations, Inc. (the licensee) submitted the letter dated June 5,1997, in response to | | GRAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-416 Entergy Operations, Inc. (the licensee) submitted the {{letter dated|date=June 5, 1997|text=letter dated June 5,1997}}, in response to |
| - the staffs request for additional information (RAI) dated February 26,1997. After reviewing the information submitted in the letter dated June 5,1997, the staff has the following questions: | | - the staffs request for additional information (RAI) dated February 26,1997. After reviewing the information submitted in the {{letter dated|date=June 5, 1997|text=letter dated June 5,1997}}, the staff has the following questions: |
| : 1. In response to Question 2 of the staffs 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. 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 exceed 30 degrees C. In addition, discuss the procedure that applies to monitoring and controlling the room temperature. | | : 1. In response to Question 2 of the staffs 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. 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 exceed 30 degrees C. In addition, discuss the procedure that applies to monitoring and controlling the room temperature. |
| : 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 ! | | : 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 ! |
Letter Sequence RAI |
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MONTHYEARML20134H7621996-11-0606 November 1996 Proposed Tech Specs 3.4.6.1 Re Reactor Coolant Leakage Detection Systems Project stage: Request ML20137W3311997-04-17017 April 1997 Summary of 970407 Meeting W/Util & Transco Products,Inc Re Versawrap,New Electrical Raceway Firewrap Sys.Attachment 1 Describes Components of Typical Veraswrap Barrier & Attachment 2 Re Transco Products,Inc Test Procedure Encl Project stage: Meeting ML20141B4751997-05-0909 May 1997 Forwards RAI Re Util 961106 Response to GL 92-08, Thermo- Lag 330-1 Fire Barriers. NRC Identified Number of Open Issues & Concerns Requiring Clarification.Response Requested within 60 Days of Ltr Date Project stage: RAI ML20140H9181997-05-0909 May 1997 Trip Rept of 970410-11 Visit to Ul to Observe full-scale Fire Endurance Test of 1 & 3 Hour Versawrap Fire Barrier Sys.List of Participants Encl Project stage: Other ML20141A9341997-05-12012 May 1997 Responds to Util Responding to NRC RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. Encl Contractor Rept Identified Number of Open Issues & Concerns Requiring Clarification Project stage: RAI ML20141A8601997-05-12012 May 1997 Forwards RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers. NRC Staff Reviewed & Identified Number of Open Issues & Concerns Requiring Clarification Project stage: Approval ML20141B6211997-05-13013 May 1997 Forwards RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Plant,Units 1 & 2 Re Ampacity Derating Issues.Technical Rept Encl Project stage: RAI ML20140F6731997-06-10010 June 1997 Forwards Request for Addl Info Re 970331 Response to NRC GL 92-08 for Plant Thermo-Lag Related Ampacity Derating Issues.Snl Ltr Rept Also Encl Project stage: RAI RBG-43994, Ack Receipt of NRC RAI Ltr Re Thermo-Lag-Related Ampacity Derating at River Bend Station.Draft Calculations Provided to Support Plant Response & Resolution of Associated Questions1997-06-16016 June 1997 Ack Receipt of NRC RAI Ltr Re Thermo-Lag-Related Ampacity Derating at River Bend Station.Draft Calculations Provided to Support Plant Response & Resolution of Associated Questions Project stage: Draft Other ML20149E0881997-07-0909 July 1997 Forwards Request for Addl Info Re Thermo-Lag Related Ampacity Derating Issues for Byron & Braidwood Stations Re GL 92-08 Project stage: RAI ML20217J5661997-08-11011 August 1997 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers. Requests Notification in Writing If Schedule or Resolution Plans Described in Submittal Change Project stage: Other RBG-44186, Informs That Detailed Response to NRC RAI & Final Calculations Re Thermo-Lag Related Ampacity Derating,Will Be Submitted by 9709261997-08-28028 August 1997 Informs That Detailed Response to NRC RAI & Final Calculations Re Thermo-Lag Related Ampacity Derating,Will Be Submitted by 970926 Project stage: Response to RAI ML20211J4861997-10-0202 October 1997 Discusses Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Plant Project stage: Other ML20199H6641997-11-14014 November 1997 Forwards Request for Addl Info Re 970324 Response to NRC RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, for Peach Bottom & Limerick.Requests Response within Sixty Days to Support Review Schedule Project stage: RAI RBG-44325, Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis1997-11-25025 November 1997 Notifies That Actions Associated W/Resolution of Thermo-Lag Issues at Plant Completed,Per GL 92-08.First Phase Completed by Development of Revised Safe Shutdown Analysis Project stage: Other ML20249B7801998-06-19019 June 1998 Forwards Request for Addl Info Related to Thermo-Lag Fire Barriers & GL 92-08 for Grand Gulf Nuclear Station,Unit 1 Project stage: RAI ML20199H5821999-01-20020 January 1999 Forwards SE Re Ampacity Derating Issues Due to Application of Thermo-Lag Fire Barrier Matl at Plant Project stage: Approval ML20202E4631999-01-25025 January 1999 Provides Confirmation That Corrective Actions Re Thermo-Lag 330-1 Issues,Per GL 92-08,have Been Completed.Ltr Also Confirms Completion of Actions Required by Confirmatory Order Modifying License for Plant,Issued by NRC on 980622 Project stage: Other ML20202B3671999-01-26026 January 1999 Forwards Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues & Technical Evaluation of Duane Arnold Energy Ctr Analysis of Ampacity Loads for Fire Barrier Clad Power Cables. Technical Evaluation Rept Encl Project stage: Approval 1997-06-10
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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20196J5811999-06-30030 June 1999 Advises That Version of Info Submitted in 990504 Application & Affidavit Re Engineering Rept ME-98-001-00,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 as Amended 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 ML20195G3811999-06-0909 June 1999 Ack Receipt of ,Which Transmitted Emergency Plan Procedure 10-S-01-1,Rev 103,under Provisions of 10CFR50, App E,Section V ML20195G2971999-06-0909 June 1999 Ack Receipt of Re Emergency Plan Procedure 10-S-01-1,rev 104.No Violations Identified & Changes Subject to Insp to Confirm Effectiveness ML20195G3511999-06-0909 June 1999 Ack Receipt of 980831 & 1022 Ltrs,Which Transmitted Changes to Grand Gulf Emergency Plan,Rev 36 & 37,under Provisions of 10CFR50,App E,Section V ML20207D3351999-05-27027 May 1999 Forwards Insp Rept 50-416/99-05 on 990321-0501.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A6961999-05-21021 May 1999 Forwards Insp Rept 50-416/99-06 on 990419-23.No Violations Noted.Determined That Fire Protection Program Was Implemented IAW Requirements of License & GL 86-10.One Unresolved Item Noted Re fire-induced Failures on Equipment ML20206U3851999-05-18018 May 1999 Forwards Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20207A7561999-05-17017 May 1999 Ack Receipt of Which Transmitted Exercise Scenario for Emergency Plan Exercise Scheduled for 990623. Some Parts of Exercise Scenario Package Not Submitted & Being Developed ML20206N3921999-05-11011 May 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20206K1261999-05-0707 May 1999 Informs That on 990407 NRC Administered Gfes of Written Operator Licensing Exam.Facility Did Not Participate in Exam.Copy of Master Exam with Answer Key Encl.Without Encl ML20206E0571999-04-29029 April 1999 Discusses EOI 960418 Request for License Amend for GGNS That Would Permit Addl Method of Fuel Movement & Loading in Core When Control Rods Removed.Determined That Insufficient Info Provided to Permit Completion of Review ML20206B0951999-04-23023 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/99-01 & NOV .Reply Found to Be Responsive to Concerns Raised in Nov.Implementation of C/As Will Be Reviewed in Future Insps ML20206B3601999-04-23023 April 1999 Forwards Insp Rept 50-416/99-04 on 990131-0320.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206E7661999-04-19019 April 1999 Submits Summary of 990415 Meeting Conducted in Port Gibson, Mi Re Results of Plant Performance Review Completed on 990211 & Transmitted on 990319.List of Attendees Encl ML20205N7251999-04-13013 April 1999 Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls IR 05000416/19980131999-04-0606 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-416/98-13 .Discussions on 990330 Resulted in Addl C/A Commitments to Address Violation Re Onsite Investigation ML20205J1051999-03-29029 March 1999 Forwards Objectives for Plant,Unit 1 1999 FEMA Emergency Plan Exercise Scheduled for 990623 ML20205E8701999-03-19019 March 1999 Advises of Completion of Plant Performance Review on 990211 to Develop Integrated Understanding of Safety Performance. Overall Performance Acceptable.Isolated Examples of Failure to Follow Procedures Noted ML20207L3621999-03-0303 March 1999 Advises That Effective 990217,NRC Project Mgt Responsibilities for Grand Gulf Nuclear Station Transferred to Sp Sekerak 1999-09-09
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_ _ _ _-_ . - - _ - _ _ - _ - _ - _ _ - _ _ _ _ _ - _ - _ - -
June 19, 1998 Mr. Joseph J. Hagan -
Vice President, Oparations GGNS Entergy Operations, Inc.
P. O. Box 756 -
. Port Gibson, MS 39150 -
SUBJECT:
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)
Dear Mr. Hagan:
In your letter of June 5,1997, you submitted the response to the staffs request for additional
- information (RAl) that was in the staffs letter of February 26,1997. The staff has reviewed the information provided in your June 5,1997, letter and has identified several areas needing clarification as described in the enclosure. These areas were discussed with your staff on
. June 17,1988, to expedite the response to the enclosed RAl. The enclosed RAI is part of the generic resolution of ampacity derating issues that was addressed in our letter of April 21,1997,
'on Generic Letter 92-08.
You are requested to provide a response to the RAI in the enclosure within 60 days of the receipt of this letter. If there are any questions conceming the enclosure, please contact me by phone at 301-414-1307, or by e . mail at jnd@nrc. gov on the Intemet.
Sincerely, i )
y' J e4 ack N. Donohew, tenior Project Manager C Project Directorate IV 1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-416 -
Enclosure:
Request for Additional Information cc w/ encl: See next page DISTRIBUTION:
Docket File PUBLIC PD4-1 r/f E. Adensam (EGA1) J.Donohew T. Gwynn, RIV ACRS OGC (15B18) C.Hawes J.Hannon ' J. Calvo A. Pal Document Name: ~ GG82809.RAI :(MEMO Dated 04/21/981 i OFC- PMtlPO1~ LA/PD4-1 PD/PDIV-1h
~
NAME J CHa JHannon a; ..
DATE k/b/98- .
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COPY YES/NO YES/NO YES/NO
- OFFICIAL RECORD COPY
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l p it p *4 UNITED STATES 4' [ j R
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30086 4 001 1
\*****/ June 19,1998 Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.
z P. O. Box 756 l l Port Gibson, MS 39150 l
SUBJECT:
REQUEST FOR ADDITIONAL ;NFORMATION RELATED TO THERMO-LAG FIRE BARRIERS AND GENERIC LETTER 92-08 FOR GRAND GULF NUCLEAR STATION, UNIT 1 (TAC NO. M82809)
Dear Mr. Hagan:
In your letter of June 5,1997, you submitted the response to the staff's request for additional information (RAI) that was in the staff's letter of February 26,1997. The staff has reviewed the information provided in your June 5,1997, letter and has identified several areas needing ,
clarification as described in the enclosure. These areas were discussed with your staff on l June 17,1988, to expedite the response to the enclosed RAl. The enclosed RAI is part of the 1 generic resolution of ampacity derating issues that was addressed in our letter of April 21,1997, on Generic Letter 92-08.
You are requested to provide a response to the RAI in the enclosure within 60 days of the receipt of this letter. If there are any questions conceming the enclosure, please contact me by phone at 301-414-1307, or by e-mail at jnd@nrc. gov on the intemet.
Sincerely, D
l l \
M Jack N 2'.h M'e t Donobew, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/lV Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
Request for Additional Information cc w/ encl: See next page
p Mr. Joseph J. Hagan Entergy Operations, Inc. Grand Gulf Nuclear Station cc:
Executive Vice President General Manager, GGNS
& Chief Operating Officer Entergy Operations, Inc.
! Entergy Operations, Inc. P. O. Box 756 P. O. Box 31995 Port Gibson, MS 39150 Jackson, MS 39286-1995 l
Attomey General Wise, Carter, Child & Caraway Department of Justice P. O. Box 651 State of Louisiana Jackson, MS 39205 P. O. Box 94005 Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer Washington, DC 20005-3502 State Board of Health P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural Office of the Govemor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attomey General President, Asst. Attomey General Claibome County Board of Supervisors State of Mississippi P. O. Box 339 P. O. Box 22947 Port Gibson, MS 39150 Jackson, MS 39225 Regional Administrator, Region IV Vice President, Operations Support U.S. Nuclear Regulatory Commission Entergy Operations, Inc.
611 Ryan Plaza Drive, Suite 1000 P.O. Box 31995 Arlington,TX 76011 Jackson, MS 39286-1995 Senior Resident inspector Director, Nuclear Safety U. S. Nuclear Regulatory Commission and Regulatory Affairs P. O. Box 399 Entergy Operations, Inc.
Port Gibson, MS 39150 P.O. Box 756 Port Gibson, MS 39150
y REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-08. THERMO LAG FIRE BARRIERS
.ENTERGY OPERATIONS. INC.
GRAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-416 Entergy Operations, Inc. (the licensee) submitted the letter dated June 5,1997, in response to
- the staffs request for additional information (RAI) dated February 26,1997. After reviewing the information submitted in the letter dated June 5,1997, the staff has the following questions:
- 1. In response to Question 2 of the staffs 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. 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 exceed 30 degrees C. In addition, discuss the procedure that applies to monitoring and controlling the room temperature.
- 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? l
- 3. - it is the staffs 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 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 i 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 l
Gulf.
- 4. In response to Question 1 of the staffs RAI, the license stated that an ampacity dorating 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 I conduits using the analytical method described in the response to Question 2 of the staffs RAl. Discuss which dorating factor is correct and identify which raceways '
i enclosed by Thermo-Lag would have sufficient design margin given an ampacity dorating
~ factor of 48%.
L l
ENCLOSURE l