Letter Sequence Request |
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TAC:ME4679, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: ENOC-11-00021, Entergy Operations, Inc., Entergy Nuclear Operations, Inc., Submittal of Planned Reorganization of Quality Control Reporting Relationship, GNRO-2012/00150, Final Report for Replacement Steam Dryer, GNRO-2017/00039, Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages, ML111720830, ML112560396, ML112790370, ML12167A257, ML12167A269, ML12170B091, ML12177A287, ML13108A217, NRC-2012-0105, Environmental Assessment and Finding of No Significant Impact Related Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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MONTHYEARML1010603922010-04-19019 April 2010
Notice of Forthcoming Conference Call with Indiana Michigan Power Company to Discuss the Proposed Responses to Requests for Additional Information Associated with GL 2004-02 for the D. C. Cook Nuclear Plant
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ML1026604002010-08-20020 August 2010
GE-Hitachi Nuclear Energy Americas LLC - Affidavit of Edward Schrull Withholding from Public Disclosure Proprietary Report NEDC-33477P
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ML1026603992010-08-31031 August 2010
NEDO-33477, Revision 0, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate
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ML1026604032010-09-0808 September 2010
License Amendment Request Extended Power Uprate
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GNRO-2010/00056, Grid Stability Evaluation2010-09-0808 September 2010
Grid Stability Evaluation
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NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix E Through Appendix G
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NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Appendix B Through Appendix D
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NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Cover Through Appendix a
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ML1030102002010-11-0909 November 2010
Supplemental Information Needed for Acceptance of License Amendment Request, Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Megawatts Thermal
Project stage: Acceptance Review
GNRO-2010/00071, Supplemental Information, License Amendment Request, Extended Power Uprate2010-11-18018 November 2010
Supplemental Information, License Amendment Request, Extended Power Uprate
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GNRO-2010/00073, Supplemental Information License Amendment Request, Extended Power Uprate2010-11-23023 November 2010
Supplemental Information License Amendment Request, Extended Power Uprate
Project stage: Supplement
ML1034201082010-12-16016 December 2010
Request for Withholding Information from Public Disclosure, 9/7/10 Affidavit Executed by E. Schrull, GEH Re NEDC-33601P
Project stage: Withholding Request Acceptance
ML1034705862011-01-0505 January 2011
Request for Withholding Information from Public Disclosure, 11/19/10 Affidavit Executed by E. Schrull, GE-Hitachi, Regarding NEDC-33621P
Project stage: Withholding Request Acceptance
ML1102602812011-01-26026 January 2011
E-mail, Request for Additional Information Instrument and Controls, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1102602872011-01-26026 January 2011
E-mail, Request for Additional Information Fire Protection, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1102701872011-01-27027 January 2011
Request for Additional Information, Emcb Non-Steam Dryer Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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E-mail, Request for Additional Information, Vessels and Internal Integrity Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00005, Core Operating Limits Report Cycle 18 Mid-Cycle Revision2011-02-0808 February 2011
Core Operating Limits Report Cycle 18 Mid-Cycle Revision
Project stage: Request
ML1103901732011-02-0808 February 2011
Email, Request for Additional Information, Nrr/Dci/Csgb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00007, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
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GNRO-2011/00012, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
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GNRO-2011/00011, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
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ML1105407052011-02-23023 February 2011
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Project stage: RAI
ML1105407122011-02-23023 February 2011
E-mail, Request for Additional Information, Nrr/Dra/Apla Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00013, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
Request for Additional Information Regarding Extended Power Uprate
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Request for Withholding Information from Public Disclosure, 8/20/10 Affidavit Executed by E. Schrull, GEH, for NEDC-33477P
Project stage: Withholding Request Acceptance
ML1106007172011-03-0101 March 2011
Email Request for Additional Information, Round 2, Nrr/Dci/Cvib Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1105504752011-03-0202 March 2011
Request for Additional Information (Redacted), Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00016, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML1107501322011-03-16016 March 2011
Email, Dose Assessment Branch, Request for Additional Information, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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Email, Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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Email, Request for Additional Information, Nrr/Dss/Snpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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ML1113905252011-05-31031 May 2011
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ML1115204582011-06-0101 June 2011
Email, Request for Additional Information, Nrr/Dra/Aadb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
2011-03-01
[Table View] |
Text
GNRO-2011/00007 February 23, 2011 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Request for Additional Information Regarding Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
- 1.
Email from A. Wang to F. Burford dated January 26, 2011 GGNS EPU Request for Additional Information Related to Fire Protection (ME4679)
(Accession Number ML110260287)
- 2.
License Amendment Request, Extended Power Uprate, dated September 8, 2010 (GNRO-2010/00056, Accession Number ML102660403)
Dear Sir or Madam:
The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1) regarding certain aspects of the Grand Gulf Nuclear Station, Unit 1 (GGNS) Extended Power Uprate (EPU) License Amendment Request (LAR) (Reference 2). Attachment 1 provides responses to the additional information related to Fire Protection.
No change is needed to the no significant hazards consideration included in the initial LAR (Reference 2) as a result of the additional information provided. There are no new commitments included in this letter.
If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.
Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6684
GNRO-2011/00007 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on February 23, 2011.
Sincerely, MAK/FGB/dm Attachments:
- 1.
Response to Request for Additional Information, Fire Protection cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)
ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
GNRO-2011/00007 Grand Gulf Nuclear Station Extended Power Uprate Response to Request for Additional Information Fire Protection to GNRO-2011/ 00007 Page 1 of 2 Response to Request for Additional Information By letter dated September 8, 2010, Entergy Operations, Inc. (Entergy) submitted a license amendment request (LAR) for an Extended Power Uprate (EPU) for Grand Gulf Nuclear Station, Unit 1 (GGNS). By correspondence dated January 26, 2011 (Accession Number ML110260287), the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information related to Fire Protection is needed for the NRC staff to complete their review of the amendment. Entergys response to each item is also provided below.
RAI # 1 The NRC staff notes that license amendment request (LAR), Attachment 5B, to GNRO-2010/00056, Safety Analysis Report for the Grand Gulf Nuclear Station Constant Pressure Power Uprate, Section 2.5.1.4.1, on page 2-194, states that, Any changes in physical plant configuration or combustible loading as a result of modifications to implement the EPU will be evaluated in accordance with the plant modification and FPPs It is unclear to the NRC staff whether there are any fire protection program plant modifications planned (e.g., adding new cable trays, or re-routing of existing cables, or increases in combustible loading affecting fire barrier ratings, or changes to administrative controls) at EPU conditions. Clarify whether this LAR involves plant modifications, or changes to the fire protection program, including any proposed modifications to implement EPU. If any, the NRC staff requests the licensee to identify proposed modifications and discuss the impact of these modifications on the plants compliance with the fire protection program licensing basis, 10 CFR 50.48, or applicable portions.
Response
The modifications planned to support EPU are listed in Attachment 8 to the License Amendment Request. Several of these plant modifications affect safety-related areas of the plant. These modifications include:
Increased boron enrichment in the Standby Liquid Control System
Standby Service Water Cooling Tower Upgrades
Increase Ultimate Heat Sink Available Water Supply
Steam Dryer Replacement
Installation of an additional Fuel Pool Cooling Heat Exchanger
Component Cooling Water (CCW) Heat Exchanger Tube Cleaning System
Installation of the Power Range Neutron Monitoring System (PRNMS)
Of these, only modifications associated with the Fuel Pool Cooling Heat Exchanger, the new CCW Heat Exchanger Tube Cleaning System, and the PRNMS have the potential to impact the Fire Hazards Analysis (FHA). The FHA (UFSAR Appendix 9A), which is a portion of the GGNS Fire Protection Plan (UFSAR Appendix 9B), describes the fire areas and zones, the safe shutdown equipment located in the area, the fire suppression equipment in the area and summarizes the analysis of the combustible loading.
to GNRO-2011/ 00007 Page 2 of 2 These modifications will add new cables to safety-related areas of the plant and, in some cases, involve using new or existing penetrations between rooms. However, the extent of new combustible loadings is small and will not affect the associated fire barrier rating. Affected penetrations are designed and sealed to maintain the required current fire barrier rating. All of these modifications are designed to be consistent with the current GGNS fire protection program such that there is no impact on the plants compliance with the fire protection program licensing basis or 10 CFR50.48.
RAI # 2 The results of the Appendix R evaluation for current license thermal power (CLTP) and EPU are provided in Table 2.5-1 and Figures 2.5-1 through 2.5-6. The NRC staff notes in Table 2.5-1 that at EPU condition, there is an increase in the suppression pool bulk temperature to 181.4F, 7.5F above the current suppression pool bulk temperature of 173.9F. Does the GGNS safe shutdown instructions credit any operator manual action in the containment? If so, discuss how this operator manual action can be accomplished within the available time at higher suppression pool bulk temperature (e.g., manually opening the main steam relief valves).
Response
GGNS safe shutdown instructions do not credit any manual operator actions in containment.
RAI # 3 Some plants credit aspects of their fire protection system for other than fire protection activities, e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems. If GGNS credits its fire protection system in this way, the LAR should identify the specific situations and discuss to what extent, if any, the extended power and measurement uncertainty recapture uprates affect these non-fire-protection aspects of the plant fire protection system. If GGNS does not take such credit, the NRC staff requests that the licensee verify this.
In your response discuss how any non-fire suppression use of fire protection water will impact the need to meet the fire protection system design demands.
Response
GGNS does not credit the fire protection system to support the design basis for non-fire protection functions. This system is considered a potential backup source of water for beyond design basis events that involve inadequate decay heat removal capability or the need for transfer of water inventory. Therefore, there are no non-fire suppression uses of the system that could impact the systems demands during design basis accidents.
