Letter Sequence Draft RAI |
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MONTHYEARML0615900102006-06-0808 June 2006
Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call
Project stage: Draft RAI
ML0616402512006-06-0909 June 2006
Tech Spec Page for Emergency Amendment 111 Allowed Outage Time Extension from 7 Days to 14 Days for Enclosure Air Handling Fan
Project stage: Acceptance Review
ML0616000222006-06-0909 June 2006
Issuance of Emergency License Amendment 111 Allowed Outage Time Extension from 7 Days to 14 Days for Enclosure Air Handling Fan
Project stage: Approval
2006-06-08
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Category:Memoranda
MONTHYEARML23053A0502023-02-22022 February 2023
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ML22306A0202022-11-0202 November 2022
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ML21062A1462021-04-21021 April 2021
Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation (2012 and 2015)
ML19057A3832019-03-0404 March 2019
Renewal of Full-Power Operating License for Seabrook Station, Unit No. 1
ML19058A2162019-03-0404 March 2019
Update to Proposed Issuance of a Final No Significant Hazards Consideration Determination and License Amendment Regarding Which a Hearing Has Been Requested (CAC No. MF8260; EPID L-2016-LLA-0007)
ML18226A2052018-09-28028 September 2018
Redacted, Submission of Alkali-Silica Reaction License Amendment Request Draft Safety Evaluation to Support Advisory Committee on Reactor Safeguards Review of Seabrook License Renewal (CAC No. MF8260; EPID L-2016-LLA-0007)
ML18243A4522018-08-31031 August 2018
License Renewal Application Memorandum
ML17278A1662017-10-0505 October 2017
Teleconference Meeting Summary Dated August 28, 2017 with Massachusetts Attorney General'S Office and Massachusetts Emergency Management Agency
ML17254A7522017-09-0606 September 2017
Alkali-Silica Reaction Issue Technical Team Charter Revision 2
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16056A3342016-03-0101 March 2016
Memorandum to File Regarding Transcript for 10 CFR 2.206 Petition from C-10 Research & Education Foundation Regarding Seabrook Station, Unit 1
ML15096A1682015-07-27027 July 2015
Memorandum to File from John Lamb, DORL, NRR No Significant Hazards Consideration Analysis and Categorical Exclusion Related to Proposed Exemption
ML14014A3782014-02-19019 February 2014
Alkali-Silica Reaction (ASR) Issue Technical Team Charter, Revision 1
ML13193A0742013-07-16016 July 2013
Request for Additional Information - Seabrook Station Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (Tac No. MF0837)
ML13128A5212013-06-10010 June 2013
Memo Position Paper -Assessment of Aci 318-71 as Design Basis for Category I Concrete Structures Affected by Alkalisilica Reaction at Seabrook Station.
ML13154A5052013-06-0404 June 2013
Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Seabrook
ML13099A2152013-04-18018 April 2013
Forthcoming Meeting with Nextera Energy Seabrook, LLC (Nextera) Regarding a Pre-Submittal for a Fixed Incore Detector License Amendment Request
ML13066A4882013-03-21021 March 2013
Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station
ML12242A3702012-09-0505 September 2012
Request for Deviation from the Reactor Oversight Process Action Matrix to Provide Increased Oversight of the Alkali-Silica Reaction Issue at Seabrook
ML12236A3852012-08-23023 August 2012
Memo Summary of NextEra Energy Seabrook Drop in Visit and Slides, August 22, 2012
ML12222A0392012-08-0909 August 2012
8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto
ML12213A0612012-08-0101 August 2012
8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol
ML12164A9012012-06-22022 June 2012
Summary of Telephone Conference Call Held on 5/24/12, Between the NRC and NextEra Energy Seabrook, LLC Concerning the Drai Pertaining to the Seabrook Station LRA
ML13196A2202012-06-0606 June 2012
Memo from B. Balsam, NRR and D. Logan, NRR to J. Susco, NRR on Summary of Section 7 Consultation Activities Related to the National Marine Fisheries Service'S Final Rule to List the Atlantic Sturgeon
ML12174A0152012-06-0404 June 2012
Draft Letter from J. Clifford, Region I to R. Nelson, NRR; Subject: Request for Technical Assistance, Seabrook Station Alkali-Silica Reaction
ML12174A0122012-06-0404 June 2012
Draft Letter from J. Clifford, Region I to R. Nelson, NRR; Subject: Request for Technical Assistance, Seabrook Station Alkali-Silica Reaction
ML12173A4632012-06-0404 June 2012
Draft Letter from D. Roberts, Region I to R. Nelson, NRR; Subject: Request for Technical Assistance, Seabrook Station Alkali-Silica Reaction
ML12174A0172012-06-0404 June 2012
Draft Letter from J. Clifford, Region I to R. Nelson, NRR; Subject: Request for Technical Assistance, Seabrook Station Alkali-Silica Reaction
ML12173A4622012-06-0404 June 2012
Draft Letter from D. Roberts, Region I to J. Jolicoeur, NRR; Subject: Request for Technical Assistance, Seabrook Station Alkali-Silica Reaction
ML1208600492012-03-23023 March 2012
Corrected Notice of Forthcoming Meeting with NextEra Energy Seabrook, LLC (NextEra) Regarding Seabrook Station Concrete Degradation
ML12054A7312012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 3
ML12054A7292012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 5
ML12054A7282012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 5
ML12054A7272012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 4
ML12054A7042012-02-16016 February 2012
DRAFT- from Darrell Roberts to John Jolicoeur Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 2
ML12054A7112012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 6
ML12054A7122012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 7 (2)
ML12054A7142012-02-16016 February 2012
DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 8 Comment
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DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 8 2010817
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DRAFT- from James Clifford to Robert Nelson Request for Technical Assistance Seabrook Station ALKALI-SILICA Reaction, Draft 3. Resolved
ML11354A1182011-12-22022 December 2011
12/8/2011 Summary of Meeting Between NRC Staff and the Nuclear Energy Institute to Discuss Current License Renewal Topics
ML11343A4482011-12-0909 December 2011
NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I
ML11327A0722011-11-30030 November 2011
Summary of Telephone Conference Call Held on November 22, 2011, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning the Response to the Request for Additional Information Pertaining to the Seabrook St
ML11304A1662011-11-0404 November 2011
Summary of Tele Conf Call Held on 3/3/11, Between the USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses
ML11304A1512011-11-0404 November 2011
Summary of Tele Conf Call Held on 4/8/11 Between USNRC and NextEra Energy Seabrook, Llc. Concerning Clarification of Information Pertaining to the Seabrook Station Request for Additional Information Responses
ML11304A1092011-11-0404 November 2011
Summary of Tele Conf Call Held on 5/31/11, Between the USNRC and Nextera Energy Seabrook, Llc., Concerning Clarification of Information Pertaining to the Seabrook LRA
ML11277A0462011-10-26026 October 2011
Summary of Public Meetings Conducted to Discuss the Dseis Related to the Review of the Seabrook Station License Renewal Application
ML11280A0452011-10-17017 October 2011
Summary of Telephone Conference Call Held on May 5, 2011, Between the U.S. Nuclear Regulatory Commission and NextEra Energy Seabrook, LLC, Concerning Clarification of Information Pertaining to the Seabrook Station LRA
2023-02-22
[Table view] |
Text
June 8, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 /RA by R. Ennis for/
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO.
MD2190)
The attached draft request for additional information (RAI) was transmitted by facsimile on June 8, 2006, to Mr. M. OKeefe, at FPL Energy Seabrook, LLC. This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The RAI is related to DNCs submittal dated June 7, 2006, regarding a one time Technical Specification change in the allowed outage time for the containment enclosure emergency air cleanup systems with one inoperable enclosure air handling fan. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-443
Enclosure:
As stated
June 8, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Victor Nerses, Senior Project Manager Plant Licensing Branch I-2 /RA by R. Ennis for/
Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO.
MD2190)
The attached draft request for additional information (RAI) was transmitted by facsimile on June 8, 2006, to Mr. M. OKeefe, at FPL Energy Seabrook, LLC. This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support a conference call with DNC in order to clarify certain items in the licensees submittal. The RAI is related to DNCs submittal dated June 7, 2006, regarding a one time Technical Specification change in the allowed outage time for the containment enclosure emergency air cleanup systems with one inoperable enclosure air handling fan. Review of the draft RAI would allow DNC to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.
Docket No. 50-443
Enclosure:
As stated DISTRIBUTION:
Public AHowe RidsNrrDraAadb LPL1-2 RidsNrrPMVNerses RidsNrrLACRaynor Accession No.: ML061590010 OFFICE LPL1-2/PM LPL1-2/LA DRA/BC LPL1-2/BC NAME VNerses: CRaynor LMrowca DRoberts DATE 6/8/06 6/8/06 OFFICIAL RECORD COPY
DRAFT REQUEST FOR ADDITIONAL INFORMATION SEABROOK STATION, UNIT NO 1 (TAC NO. MD2190)
By letter dated June 7, 2006, FPL Energy Seabrook, LLC (FPLE or the licensee) submitted License Amendment Request No. 05-10, requesting a change to the Technical Specifications (TSs) for Seabrook Station, Unit No. 1 (Seabrook). The proposed change would revise TS 3.6.5.1, Containment Enclosure Emergency Air Cleanup Systems to increase the TS allowed outage time (AOT) with one inoperable enclosure air handling fan (EAHF) from 7 days to 14 days, on a one-time basis. The extension would allow continued operation of Seabrook while repairs and related testing of the inoperable EAHF (EAH-FN-31B)1A) are completed. The Nuclear Regulatory Commission (NRC) staff requests the following additional information to complete its review.
- 1. Section 5.0 page 7 states that the probabilistic risk assessment (PRA) model is a full scope model. This statement implies to the staff that all initiating events, including internal fires and floods, are included in the model. However, page 9 states that fires and internal flooding are not included. Regulatory Position 2.3.2 of Regulatory Guide 1.177 states "For changes to TS requirements defined for the power operation mode, the scope of analysis should include internal fires and flooding if appropriate (e.g., when the subject TS equipment is located in areas identified as vulnerable to fires and flood)."
The licensee is requested to provide a basis as to why internal fires and flooding risk is not relevant to the proposed TS change, or to provide applicable quantitative or qualitative analyses of these risks during the proposed extension of the limiting condition of operation 3.6.5.1, including any compensatory measures which may be necessary to reduce the likelihood of such events. Specifically, the staff is concerned about fires or floods in areas of the plant which could disable the remaining operable EAHF, either directly impacting the fan, directly interrupting normal AC power, or causing a loss of offsite power and failure of the diesel generator supporting the fan.
- 2. Section 5.0 page 9 identifies that the containment enclosure emergency air cleanup system is modeled in the PRA, and the success criteria of the system is for one train to operate for the 24-hour mission time. The submittal does not address the severe accident mitigation functions provided by the system in the PRA model, and the failure effects if the system is unavailable. The licensee has identified in Section 3.0 page 4 two specific design functions of the system: 1) control of radiological releases following a loss of coolant accident, and 2) area and equipment cooling for selected safety-related components. The licensee is requested to confirm how the PRA models the EAHFs, by providing a comparison of the design basis functions with the PRA modeled functions, and justify that any differences would not impact the incremental conditional core damage probability (ICCDP) and incremental conditional large early release probability (CLERP) results.
Enclosure
- 3. Section 5.0 page 10 provides the quantitative results of the internal events ICCDP analysis, and compares the calculated risk of completing repairs while operating over a 14-day period (1.31E-6 ICCDP), compared to the risk of shutting down to conduct repairs (1.5E-6 ICCDP). The staff is unable to confirm the validity of the analyses.
Specifically, the licensee identified that the 14-day ICCDP for on-line repair is 1.31E-6, which represents the delta risk above the nominal full power risk over 14 days. The staff infers that the seven day ICCDP would be 50% of this value, or approximately 6.5E-7.
The licensee states (page 10) that if it were to shut down the plant to repair the inoperable EAHF, an additional ICCDP risk of 2.0E-7 to 3.0E-7 would be incurred for shutting down and returning to power. The staff calculates that the total risk of operating for 7 days, then shutting down to repair the EAHF and return the unit to service, would involve 8.5E-7 to 9.5E-7 ICCDP, which is inconsistent with the licensee's estimate of 1.5E-6. The licensee is requested to provide a more detailed basis for its ICCDP value of 1.5E-6 for shutting down to make repairs.
