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| | number = ML13338A141 | | | number = ML13338A141 |
| | issue date = 12/11/2013 | | | issue date = 12/11/2013 |
| | title = Seabrook Station, Unit 1 - Request for Additional Information for License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for Relocation of Specific Frequency Requirements to a | | | title = Request for Additional Information for License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for Relocation of Specific Frequency Requirements to a Licensee Cont |
| | author name = Lamb J G | | | author name = Lamb J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = Walsh K | | | addressee name = Walsh K |
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| | docket = 05000443 | | | docket = 05000443 |
| | license number = | | | license number = |
| | contact person = Lamb J G | | | contact person = Lamb J |
| | case reference number = TAC MF1958 | | | case reference number = TAC MF1958 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 December 11, 2013 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 11, 2013 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| | SEABROOK STATION, UNIT 1- REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 13-03, "APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK-INFORMED JUSTIFICATIONS FOR RELOCATION OF SPECIFIC FREQUENCY REQUIREMENTS TO A LICENSEE-CONTROLLED PROGRAM" (TAC NO. MF1958) |
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| SEABROOK
| | ==Dear Mr. Walsh:== |
| : STATION, UNIT 1-REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 13-03, "APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK-INFORMED JUSTIFICATIONS FOR RELOCATION OF SPECIFIC FREQUENCY REQUIREMENTS TO A LICENSEE-CONTROLLED PROGRAM" (TAC NO. MF1958) | |
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| ==Dear Mr. Walsh:==
| | By letter dated May 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13155A002), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook Station, Unit 1 (Seabrook). The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control- RITSTF [Risk-Informed TS Task Force] |
| By letter dated May 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13155A002), | | Initiative 5b," Revision 3 (ADAMS Accession No. ML090850642). The Federal Register notice published on July 6, 2009 (74 FR 31996), announced the availability of this TS improvement. |
| NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook | | The NRC staff has determined that additional information is necessary to complete its review. |
| : Station, Unit 1 (Seabrook).
| | The request for additional information (RAI) is enclosed. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on October 24, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. A conference call was held on November 25, 2013, and Mr. Kilby agreed that NextEra would respond to the RAI by January 31, 2014. Please note that if you do not respond to the RAI by January 31, 2014, the NRC staff may reject your request for relief under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information." |
| The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." | | |
| The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control-RITSTF [Risk-Informed TS Task Force] Initiative 5b," Revision 3 (ADAMS Accession No. ML090850642). | | K. Walsh If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov. |
| The Federal Register notice published on July 6, 2009 (74 FR 31996), announced the availability of this TS improvement. | | Jo~ |
| The NRC staff has determined that additional information is necessary to complete its review. The request for additional information (RAI) is enclosed. | | J:) ~ |
| A draft of these questions was previously sent to Mr. Gary Kilby of your staff on October 24, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. | | . Lamb, Senior reject Manager Pia t icensing Branch 1-2 Divi on of Operating Reactor Licensing Offi e of Nuclear Reactor Regulation Docket No. 50-443 |
| A conference call was held on November 25, 2013, and Mr. Kilby agreed that NextEra would respond to the RAI by January 31, 2014. Please note that if you do not respond to the RAI by January 31, 2014, the NRC staff may reject your request for relief under the provisions of Title 1 0 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information." | |
| K. Walsh If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov. | |
| Docket No. 50-443 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/ enclosure: | | Request for Additional Information cc w/ enclosure: Distribution via Listserv |
| Distribution via Listserv | |
| . J:) . Lamb, Senior reject Manager Pia t icensing Branch 1-2 Divi on of Operating Reactor Licensing Offi e of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 13-03, APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTSF-425 NEXTERA ENERGY SEABROOK, LLC. SEABROOK
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| : STATION, UNIT 1 DOCKET NO. 50-443 By letter dated May 28, 2013 (Reference 1 ), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook
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| : Station, Unit 1 (Seabrook).
| |
| The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies."
| |
| The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control -RITSTF [Risk-Informed TS Task Force] Initiative 5b," Revision 3 (Reference 2). The Federal Register notice published on July 6, 2009 (7 4 FR 31996), announced the availability of this TS improvement.
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| The NRC staff has determined that the following additional information is necessary to complete its review. REQUEST FOR ADDITIONAL INFORMATION
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| : 1. In Section 2.2 of the submittal, "Optional Changes and Variations,"
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| the licensee states in Item 3 that they propose relocation of surveillance frequencies for surveillances not covered by NUREG-1431, "Standard Technical Specifications Westinghouse Plants,"
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| and TSTF-425.
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| The licensee further states that these changes will be evaluated using Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies" (Reference 3). Discuss what approach (risk, bounding, etc.) will be used and the estimated additional impact to risk, if any, these additions present.
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| : 2. Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,"
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| Revision 1, (Reference
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| : 4) states that, to demonstrate technical adequacy of the probabilistic risk assessment (PRA), licensees should identify permanent plant changes (such as design or operational practices) that have an impact on those things modeled in the PRA, but have not been incorporated in the baseline PRA model. Please discuss Seabrook's approach to assessing plant changes not yet incorporated into the PRA model for this application.
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| Enclosure 3. The submittal indicates that the internal fire and seismic events portions of the Seabrook PRA have not been subjected to peer reviews or self-assessments.
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| The submittal does not indicate how the PRAs will be utilized (e.g., detailed evaluations, bounding analyses).
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| Please describe, in more detail, how fire and seismic events would be assessed in terms of the NEI 04-10 guidance.
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| If those portions of the PRA are to be used for detailed evaluations such as Step 12 of NEI 04-10, please demonstrate how they are technically adequate in accordance with Regulatory Guide 1.200 (Reference 4). 4. Attachment 1, Section 3.4, "Part 5 Seismic Events,"
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| states that the most recent 2005 upgrade to the Seabrook Seismic PRA (SPRA) did not include an update to the seismic hazard curve. The NRC issued Information Notice 2010-18, "Generic Issue [GI] 199, 'Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants,"'
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| on September 2, 2010, to nuclear power plants and independent fuel storage installations.
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| Gl-199 activities are being addressed in the recently issued Title 10 of the Code of Federal Regulations, Part 50, Section 50.54(f)
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| (50.54(f))
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| letters on items 2.1 and 2.3 of the Japanese Near-Term Task Force recommendations.
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| Please describe how NextEra ensures the Seabrook SPRA is technically adequate prior to completing the demanded seismic risk evaluation.
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| : 5. The following questions relate to facts and observations (F&Os) entries in Attachments A and B of the application which identifies gaps to Capability Category II of the American Society of Mechanical Engineers (ASME) PRA standard.
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| : a. For F&O HR-G4-1, clarify the use of "time windows" and confirm that NextEra specifies the point in time at which operators are expected to receive relevant indications.
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| : b. For F&O HR-G7-1, for multiple human actions in the same accident
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| : sequence, confirm that NextEra accounts for the influence of factors that could lead to dependence such as common practices and procedures.
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| : c. For F&O LE-C10-01 for LE-C10 and LE-C12, confirm that NextEra conducted the review to achieve Capability Category II and used conservative or a combination of conservative and realistic treatment for non-significant accident progression sequences.
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| : 6. Do the failure probabilities of structures,
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| : systems, and components that are in standby mode for extended
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| : periods, as modeled in the Seabrook PRA, include a standby related contribution and a cyclic demand-related contribution?
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| Please describe how you address the standby time-related contribution for extended surveillances. REFERENCES
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| : 1. Letter from K.T. Walsh (NextEra) to NRC, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program,"
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| dated May 28, 2013. (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13155A002)
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| : 2. Technical Specification Task Force (TSTF) Traveler 425, "Relocate Surveillance Frequencies to Licensee Controi-RITSTF
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| [Risk-Informed Technical Specification Task Force] Initiative 5b." (ADAMS Accession No. ML090850642)
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| : 3. NEI 04-10, Rev. 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies."
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| (ADAMS Accession No. ML071360456)
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| : 4. Regulatory Guide 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities."
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| (ADAMS Accession No. ML062060184)
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| K. Walsh If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov.
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| Docket No. 50-443
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| ==Enclosure:==
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 13-03, APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTSF-425 NEXTERA ENERGY SEABROOK, LLC. |
| | SEABROOK STATION, UNIT 1 DOCKET NO. 50-443 By letter dated May 28, 2013 (Reference 1), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook Station, Unit 1 (Seabrook). |
| | The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TS Task Force] |
| | Initiative 5b," Revision 3 (Reference 2). The Federal Register notice published on July 6, 2009 (7 4 FR 31996), announced the availability of this TS improvement. |
| | The NRC staff has determined that the following additional information is necessary to complete its review. |
| | REQUEST FOR ADDITIONAL INFORMATION |
| | : 1. In Section 2.2 of the submittal, "Optional Changes and Variations," the licensee states in Item 3 that they propose relocation of surveillance frequencies for surveillances not covered by NUREG-1431, "Standard Technical Specifications Westinghouse Plants," |
| | and TSTF-425. The licensee further states that these changes will be evaluated using Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies" (Reference 3). Discuss what approach (risk, bounding, etc.) will be used and the estimated additional impact to risk, if any, these additions present. |
| | : 2. Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," Revision 1, (Reference 4) states that, to demonstrate technical adequacy of the probabilistic risk assessment (PRA), licensees should identify permanent plant changes (such as design or operational practices) that have an impact on those things modeled in the PRA, but have not been incorporated in the baseline PRA model. Please discuss Seabrook's approach to assessing plant changes not yet incorporated into the PRA model for this application. |
| | Enclosure |
| | : 3. The submittal indicates that the internal fire and seismic events portions of the Seabrook PRA have not been subjected to peer reviews or self-assessments. The submittal does not indicate how the PRAs will be utilized (e.g., detailed evaluations, bounding analyses). Please describe, in more detail, how fire and seismic events would be assessed in terms of the NEI 04-10 guidance. If those portions of the PRA are to be used for detailed evaluations such as Step 12 of NEI 04-10, please demonstrate how they are technically adequate in accordance with Regulatory Guide 1.200 (Reference 4). |
| | : 4. Attachment 1, Section 3.4, "Part 5 Seismic Events," states that the most recent 2005 upgrade to the Seabrook Seismic PRA (SPRA) did not include an update to the seismic hazard curve. The NRC issued Information Notice 2010-18, "Generic Issue [GI] 199, |
| | 'Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants,"' on September 2, 2010, to nuclear power plants and independent fuel storage installations. Gl-199 activities are being addressed in the recently issued Title 10 of the Code of Federal Regulations, Part 50, Section 50.54(f) |
| | (50.54(f)) letters on items 2.1 and 2.3 of the Japanese Near-Term Task Force recommendations. Please describe how NextEra ensures the Seabrook SPRA is technically adequate prior to completing the demanded seismic risk evaluation. |
| | : 5. The following questions relate to facts and observations (F&Os) entries in Attachments A and B of the application which identifies gaps to Capability Category II of the American Society of Mechanical Engineers (ASME) PRA standard. |
| | : a. For F&O HR-G4-1, clarify the use of "time windows" and confirm that NextEra specifies the point in time at which operators are expected to receive relevant indications. |
| | : b. For F&O HR-G7-1, for multiple human actions in the same accident sequence, confirm that NextEra accounts for the influence of factors that could lead to dependence such as common practices and procedures. |
| | : c. For F&O LE-C10-01 for LE-C10 and LE-C12, confirm that NextEra conducted the review to achieve Capability Category II and used conservative or a combination of conservative and realistic treatment for non-significant accident progression sequences. |
| | : 6. Do the failure probabilities of structures, systems, and components that are in standby mode for extended periods, as modeled in the Seabrook PRA, include a standby time-related contribution and a cyclic demand-related contribution? Please describe how you address the standby time-related contribution for extended surveillances. |
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| Sincerely, Ira/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Request for Additional Information cc w/enclosure:
| | REFERENCES |
| Distribution via Listserv DISTRIBUTION:
| | : 1. Letter from K.T. Walsh (NextEra) to NRC, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program," dated May 28, 2013. |
| PUBLIC RidsNrrDoriDpr Resource RidsNrrPMSeabrookResource LPLI-2 R/F RidsNrrDorllpl1-2 Resource RidsNrrLAABaxter Resource RidsAcrsAcnw_MaiiCTR Resource RidsRgn1 Mail Center Resource
| | (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13155A002) |
| : GNewman, NRR JEvans, NRR ADAMS Accession No* ML13338A141 | | : 2. Technical Specification Task Force (TSTF) Traveler 425, "Relocate Surveillance Frequencies to Licensee Controi-RITSTF [Risk-Informed Technical Specification Task Force] Initiative 5b." (ADAMS Accession No. ML090850642) |
| .. *via memorandum
| | : 3. NEI 04-10, Rev. 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." (ADAMS Accession No. ML071360456) |
| **via email OFFICE LPL1-2/PM LPL 1-2/LA APLAIBC LPL 1-2/BC (A) NAME Jlamb A Baxter** | | : 4. Regulatory Guide 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities." |
| HHamzehee* | | (ADAMS Accession No. ML062060184) |
| Jlamb DATE 12/6/1 3 12/06/13 10/08/13 12/11/13 OFFICIAL RECORD COPY}} | | * ML13338A141 *via memorandum **via email OFFICE LPL1-2/PM LPL 1-2/LA APLAIBC LPL 1-2/BC (A) |
| | NAME Jlamb A Baxter** HHamzehee* Jlamb DATE 12/6/1 3 12/06/13 10/08/13 12/11/13}} |
Letter Sequence RAI |
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TAC:MF1958, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Approved, Closed) |
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MONTHYEARSBK-L-13071, License Amendment Request 13-032013-05-28028 May 2013 License Amendment Request 13-03 Project stage: Request ML13206A0482013-08-12012 August 2013 1, Acceptance Letter Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for Relocation of Specific Frequency Requirements to a Licensee Controlled.. Project stage: Acceptance Review ML13338A1412013-12-11011 December 2013 Request for Additional Information for License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for Relocation of Specific Frequency Requirements to a Licensee Cont Project stage: RAI SBK-L-14007, Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency...2014-01-29029 January 2014 Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency... Project stage: Response to RAI ML14065A2642014-03-13013 March 2014 Request for Additional Information for License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for Relocation of Specific Frequency Requirements to a Licensee-Controlled Program Project stage: RAI SBK-L-14056, Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency...2014-03-26026 March 2014 Response to Request for Additional Information Regarding License Amendment Request 13-03, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency... Project stage: Response to RAI ML13212A0692014-07-24024 July 2014 Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Project stage: Approval 2014-01-29
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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024 Integrated Inspection Report 05000443/2024003 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24303A0352024-10-29029 October 2024 Operator Licensing Examination Approval IR 05000443/20244022024-10-17017 October 2024 Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only) L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024 Core Operating Limits Report for Reload Cycle 24 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes ML24254A2552024-09-25025 September 2024 Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24239A5382024-09-20020 September 2024 Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000443/20240052024-08-29029 August 2024 Updated Inspection Plan for Seabrook Station (Report 05000443/2024005) ML24232A1142024-08-21021 August 2024 Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024 Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024 Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent . IR 05000443/20240022024-08-0606 August 2024 Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001 L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024 Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024 Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite. ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld IR 05000443/20240102024-05-29029 May 2024 Biennial Problem Identification and Resolution Inspection Report 05000443/2024010 IR 05000443/20240112024-05-24024 May 2024 Age-Related Degradation Inspection Report 05000443/2024011 IR 05000443/20240012024-05-13013 May 2024 Integrated Inspection Report 05000443/2024001 L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio ML24046A0512024-05-0707 May 2024 Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report IR 05000443/20245012024-04-22022 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501 05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024 Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024 2023 Annual Environmental Operating Report L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24067A2622024-03-0808 March 2024 Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances) L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024 To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source ML24065A2522024-03-0505 March 2024 Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033) L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024 Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024 Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024 Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source IR 05000443/20230062024-02-28028 February 2024 Annual Assessment Letter for Seabrook Station (Report 05000443/2023006) L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024 Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024 Radiological Emergency Plan (Ssrep), Revision 82 IR 05000443/20230042024-02-12012 February 2024 Integrated Inspection Report 05000443/2023004 ML24009A1152024-01-29029 January 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) 2024-09-25
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23011A3082023-01-11011 January 2023 Request for Additional Information Regarding Relief Request 4RA-22-001 (L-2022-LLR-0074) ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22228A0552022-08-15015 August 2022 Request for Additional Information Steam Generator Tube Inspection Report Review ML22153A4152022-05-31031 May 2022 Request for Additional Information Re 120V Inverter LAR from TS Branch - Final ML22062B6642022-02-0707 February 2022 Request for Additional Information 120V Inverter LAR from the Electrical Branch ML22063A0002022-01-25025 January 2022 Requests for Additional Information from Risk Branch Regarding 120V Inverter LAR ML21245A4382021-10-0505 October 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise 120-Volt AC Vital Instrument Panel Technical Specification Requirements ML21097A2512021-04-0707 April 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Report Review for RFO 20 (EPID L-2020-LRO-0066) (Email) ML21054A0482021-02-23023 February 2021 Request for Additional Information Regarding Heat Flux Hot Channel Requirement Amendment Request ML20343A0942020-12-0303 December 2020 Request for Additional Information Regarding Seabrook (COVID-19) Part 73 Force-on-Force Exemption Request (L-2020-LLE-0219) ML20258A1502020-09-14014 September 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding One-Time Change to the AC Sources Operating TS ML20204A5422020-07-21021 July 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding Degraded Voltage Time Delay Setpoint ML20167A1842020-06-11011 June 2020 Request for Additional Information Related to Seabrook License Amendment Request Regarding TSTF-411 and TSTF-418 (L-2019-LLA-0237) ML20114E1592020-04-23023 April 2020 Email and Request for Additional Information Related to Seabrook License Amendment Request to Degraded Voltage Time Delay Setpoint (L-2020-LLA-0012) ML19296D9122019-10-23023 October 2019 NRR E-mail Capture - Request for Additional Information Related to Seabrook Inverter Amendment (L-2019-LLA-0216) ML18163A0352018-06-11011 June 2018 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML18121A3992018-05-0101 May 2018 NRR E-mail Capture - Request for Additional Information Regarding ASR Amendment Request ML18113A5292018-04-18018 April 2018 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML18058A0522018-02-27027 February 2018 Enclosurequest for Additional Information (Letter: RAI Regarding Florida Power and Light/Nextera Decommissioning Funding Plan Updates for St. Lucie, Units 1 & 2; Seabrook Station; Duane Arnold Energy Center; and Point Beach, Units 1 and 2) ML18026A8792018-01-29029 January 2018 Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application Docket No. 05-443 ML17332A3412017-11-29029 November 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption ML17261B2172017-10-11011 October 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17276B7572017-10-0202 October 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17214A0852017-08-0404 August 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction ML17201Q1072017-07-18018 July 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17139B8352017-05-24024 May 2017 Final Request for Additional Information Regarding Seabrook License Renewal Application - Set 26 ML17150A2862017-05-0505 May 2017 NRR E-mail Capture - Draft - Request for Additional Information Regarding ASR Amendment Request ML17088A6142017-03-29029 March 2017 Request for Additional Information for the Review of the Seabrook Station License Renewal Application ML16341B9022017-03-0707 March 2017 03/07/2016 Summary of Telecon Held on Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Request for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16342C4672017-03-0101 March 2017 12/01/2016 Summary of Teleconference Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook Concerning Requests for Additional Information Pertaining to the Seabrook Station License Renewal Application ML16337A0082016-12-0101 December 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment Seabrook Station, License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16326A0372016-11-30030 November 2016 Requests for Additional Information for the Review of the Seabrook Station License Renewal Application ML16326A0092016-11-18018 November 2016 NRR E-mail Capture - Request for Additional Information Re. Nextera/Fpl LAR to Adopt TSTF-545 - CACs MF8203, MF8204, MF8208, and MF8209 ML16301A4282016-11-14014 November 2016 Requests for Additional Information for the Review of the License Renewal Application ML16319A4222016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to ILRT License Amendment ML16319A4212016-11-10010 November 2016 NRR E-mail Capture - Need for Supplement to EAL License Amendment ML16230A1062016-10-0303 October 2016 Request for Additional Information Request to Extend Containment Leakage Test Frequency ML16230A5332016-09-22022 September 2016 Request for Additional Information Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 ML16258A0222016-09-19019 September 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Alkali-Silica Reaction ML16187A2032016-07-0808 July 2016 Requests For Additional Information For The Severe Accident Mitigation Alternatives (SAMA) Review Of The Seabrook Station License Renewal Application (TAC No. Me3959)- Enclosure ML15328A1392015-12-0404 December 2015 November 23, 2015, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Nextera Energy Seabrook, LLC, Concerning Requests for Additional Information Pertaining to the Seabrook Station ML15251A3332015-10-0202 October 2015 Request for Additional Information Related to the Review of the Seabrook Station, Unit 1, License Renewal Application-SET 25 ML15224A5662015-08-28028 August 2015 Request for Additional Information Related to the Review of the Seabrook Station License Renewal Application-Set 24 ML15131A3382015-06-0505 June 2015 Request for Additional Information Regarding License Amendment 14-03, Changes to Technical Specification 3.3.3.1,Radiation Monitoring for Plant Operations ML15043A2212015-02-24024 February 2015 Request for Additional Information for the Spring 2014 Steam Generator Tube Inspections ML14363A3672015-01-0909 January 2015 Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements ML14358A0732014-12-24024 December 2014 Request for Additional Information for License Amendment Request 13-05. Fixed Incore Detector System Analysis Methodology 2024-07-12
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 11, 2013 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874
SUBJECT:
SEABROOK STATION, UNIT 1- REQUEST FOR ADDITIONAL INFORMATION FOR LICENSE AMENDMENT REQUEST 13-03, "APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK-INFORMED JUSTIFICATIONS FOR RELOCATION OF SPECIFIC FREQUENCY REQUIREMENTS TO A LICENSEE-CONTROLLED PROGRAM" (TAC NO. MF1958)
Dear Mr. Walsh:
By letter dated May 28, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13155A002), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook Station, Unit 1 (Seabrook). The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control- RITSTF [Risk-Informed TS Task Force]
Initiative 5b," Revision 3 (ADAMS Accession No. ML090850642). The Federal Register notice published on July 6, 2009 (74 FR 31996), announced the availability of this TS improvement.
The NRC staff has determined that additional information is necessary to complete its review.
The request for additional information (RAI) is enclosed. A draft of these questions was previously sent to Mr. Gary Kilby of your staff on October 24, 2013, with an opportunity to have a teleconference to ensure that the licensee understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. A conference call was held on November 25, 2013, and Mr. Kilby agreed that NextEra would respond to the RAI by January 31, 2014. Please note that if you do not respond to the RAI by January 31, 2014, the NRC staff may reject your request for relief under the provisions of Title 10 of the Code of Federal Regulations, Section 2.1 08, "Denial of application for failure to supply information."
K. Walsh If you have questions, you can contact me at 301-415-3100 and/or John.Lamb@nrc.gov.
Jo~
J:) ~
. Lamb, Senior reject Manager Pia t icensing Branch 1-2 Divi on of Operating Reactor Licensing Offi e of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
Request for Additional Information cc w/ enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST 13-03, APPLICATION TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTSF-425 NEXTERA ENERGY SEABROOK, LLC.
SEABROOK STATION, UNIT 1 DOCKET NO. 50-443 By letter dated May 28, 2013 (Reference 1), NextEra Energy Seabrook, LLC (NextEra) submitted license amendment request (LAR) 13-03 for Seabrook Station, Unit 1 (Seabrook).
The proposed change is to the Seabrook technical specifications (TS). Specifically, the proposed amendment would modify the TS by relocating specific surveillance frequencies to a licensee-controlled program with implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved TS Task Force Standard TS change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TS Task Force]
Initiative 5b," Revision 3 (Reference 2). The Federal Register notice published on July 6, 2009 (7 4 FR 31996), announced the availability of this TS improvement.
The NRC staff has determined that the following additional information is necessary to complete its review.
REQUEST FOR ADDITIONAL INFORMATION
- 1. In Section 2.2 of the submittal, "Optional Changes and Variations," the licensee states in Item 3 that they propose relocation of surveillance frequencies for surveillances not covered by NUREG-1431, "Standard Technical Specifications Westinghouse Plants,"
and TSTF-425. The licensee further states that these changes will be evaluated using Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies" (Reference 3). Discuss what approach (risk, bounding, etc.) will be used and the estimated additional impact to risk, if any, these additions present.
- 2. Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," Revision 1, (Reference 4) states that, to demonstrate technical adequacy of the probabilistic risk assessment (PRA), licensees should identify permanent plant changes (such as design or operational practices) that have an impact on those things modeled in the PRA, but have not been incorporated in the baseline PRA model. Please discuss Seabrook's approach to assessing plant changes not yet incorporated into the PRA model for this application.
Enclosure
- 3. The submittal indicates that the internal fire and seismic events portions of the Seabrook PRA have not been subjected to peer reviews or self-assessments. The submittal does not indicate how the PRAs will be utilized (e.g., detailed evaluations, bounding analyses). Please describe, in more detail, how fire and seismic events would be assessed in terms of the NEI 04-10 guidance. If those portions of the PRA are to be used for detailed evaluations such as Step 12 of NEI 04-10, please demonstrate how they are technically adequate in accordance with Regulatory Guide 1.200 (Reference 4).
- 4. Attachment 1, Section 3.4, "Part 5 Seismic Events," states that the most recent 2005 upgrade to the Seabrook Seismic PRA (SPRA) did not include an update to the seismic hazard curve. The NRC issued Information Notice 2010-18, "Generic Issue [GI] 199,
'Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants,"' on September 2, 2010, to nuclear power plants and independent fuel storage installations. Gl-199 activities are being addressed in the recently issued Title 10 of the Code of Federal Regulations, Part 50, Section 50.54(f)
(50.54(f)) letters on items 2.1 and 2.3 of the Japanese Near-Term Task Force recommendations. Please describe how NextEra ensures the Seabrook SPRA is technically adequate prior to completing the demanded seismic risk evaluation.
- 5. The following questions relate to facts and observations (F&Os) entries in Attachments A and B of the application which identifies gaps to Capability Category II of the American Society of Mechanical Engineers (ASME) PRA standard.
- a. For F&O HR-G4-1, clarify the use of "time windows" and confirm that NextEra specifies the point in time at which operators are expected to receive relevant indications.
- b. For F&O HR-G7-1, for multiple human actions in the same accident sequence, confirm that NextEra accounts for the influence of factors that could lead to dependence such as common practices and procedures.
- c. For F&O LE-C10-01 for LE-C10 and LE-C12, confirm that NextEra conducted the review to achieve Capability Category II and used conservative or a combination of conservative and realistic treatment for non-significant accident progression sequences.
- 6. Do the failure probabilities of structures, systems, and components that are in standby mode for extended periods, as modeled in the Seabrook PRA, include a standby time-related contribution and a cyclic demand-related contribution? Please describe how you address the standby time-related contribution for extended surveillances.
REFERENCES
- 1. Letter from K.T. Walsh (NextEra) to NRC, "Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program," dated May 28, 2013.
(Agencywide Documents Access and Management System (ADAMS) Accession No. ML13155A002)
- 2. Technical Specification Task Force (TSTF) Traveler 425, "Relocate Surveillance Frequencies to Licensee Controi-RITSTF [Risk-Informed Technical Specification Task Force] Initiative 5b." (ADAMS Accession No. ML090850642)
- 3. NEI 04-10, Rev. 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." (ADAMS Accession No. ML071360456)
- 4. Regulatory Guide 1.200, Revision 1, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities."
(ADAMS Accession No. ML062060184)
- ML13338A141 *via memorandum **via email OFFICE LPL1-2/PM LPL 1-2/LA APLAIBC LPL 1-2/BC (A)
NAME Jlamb A Baxter** HHamzehee* Jlamb DATE 12/6/1 3 12/06/13 10/08/13 12/11/13