ML103090308

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Request for Additional Information Related to the Review of the Seabrook Station, License Renewal Application
ML103090308
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 11/18/2010
From: Richard Plasse
License Renewal Projects Branch 2
To: Freeman P
NextEra Energy Seabrook
Richard Plasse, 415 1427
References
TAC ME4028
Download: ML103090308 (7)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555"()001 November 18, 2010 Mr. Paul Freeman Site Vice President clo Mr. Michael OKeefe NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION (TAC NO ME4028)

Dear Mr. Freeman:

By [[letter::L-2010-101, Comment (1) of Larry Nicholson, on Behalf of Florida Power & Light Co., on Proposed NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants; Branch Technical Position (BTP) 7-19, Guidance for .|letter dated May 25, 2010]], NextEra Energy Seabrook, LLC (NextEra) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the Operating License NPF-86 for Seabrook Station, Unit 1 (Seabrook) for review by the U.S.

Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.

The request for additional information was discussed with Mr. Rick Cliche, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or bye-mail at richard.plasse@nrc.gov.

Sincerely, Ri~Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

As stated cc w/encl: Distribution via Listserv

Seabrook Station License Renewal Application Request for Additional Information Set 3 RAJ 2.3.3.15-1 License renewal application (LRA) drawing PID-1-FP-LR20270 shows that sprinkler systems at locations C-4 to H-4 are out of scope (i.e., not colored in red). The staff requests that the applicant verify whether these sprinkler systems installed in various areas of the plant are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an aging management (AMR) in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAJ 2.3.3.15-2 LRA drawing PID-1-FP-LR20274 shows that several yard fire hydrants and post indicator valves are out of scope (i.e., not colored in red). The staff believes that yard fire hydrants and post indicator valves have the fire protection intended functions required to be compliant with 10 CFR 50.48 as stated in 10 CFR 54.4. The fire hydrants and post indicator valves also serve as the pressure boundary for the fire protection water supply system. Further, NUREG-0896,

'Safety Evaluation Report related to the operation of Seabrook Station, Units 1 and 2," dated March 1983, Section 9.5.1.5, "Fire Detection and Suppression:' on page 9-47, states that it ***

Yard hydrants are provided at intervals of 250 ft along the fire protection water supply loop, approximately 40 ft from the buildings. The lateral to each yard hydrant is provided with an isolation valve to facilitate hydrant maintenance and repairs without shutting down any part of the fire water supply system... "

The staff requests that the applicant verify whether the yard hydrants and post indicator valves are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAJ 2.3.3.15-3 Section 9.5.1.6, "Fire Protection of Specific Plant Areas;' of the Seabrook Station Safety Evaluation Report (NUREG-0896), dated March 1983, on page 9-48, states that"... the applicant committed to provide oil collection systems for each reactor coolant pump in accordance with Section 111.0 Appendix R..:' LRA Section 2.3.3.15 did not discuss scoping and screening results of reactor coolant pump (RCP) oil collection systems and their associated components.

The staff requests that the applicant verify whether the RCP oil collection systems and their associated components are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If RCP oil collection systems and their associated components are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

ENCLOSURE

- 2 RAI 2.3.3.15-4 Section 9.5.1.6, "Fire Protection of Specific Plant Areas;' of the Seabrook Station Safety Evaluation Report (NUREG-0896), dated March 1983, on pqge 9-52, "Cable Spreading Room;'

states that..... A manual smoke ventilation system has been provided to exhaust the cable spreading room in the event of a fire..:' LRA Section 2.3.3.15 did not discuss scoping and screening results of the cable spreading room (CSR) manual smoke ventilation system and its associated components.

The staff requests that the applicant verify whether the CSR manual smoke ventilation system and its associated components are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If the CSR manual smoke ventilation system and its associated components are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.15-5 Section 9.5.1.6, "Fire Protection of Specific Plant Areas;' of the Seabrook Station Safety Evaluation Report (NUREG-0896), dated March 1983, on page 9-53, "Switchgear Rooms;' states that"... The Division I and Division 1/ switchgear rooms are separated from each other and from other plant areas by 3-hour-fire-rated wall and floor/ceiling assemblies. Automatic fire detection is provided by ionization smoke detectors. Manual protection is provided by standpipe and hose stations and portable extinguishers.. ;' LRA Section 2.3.3.15 did not discuss scoping and screening results of Division I and Division II switchgear rooms' standpipe and hose stations.

The staff requests that the applicant verify whether the Division I and Division II switchgear rooms' standpipe and hose stations are in the scope of license renewal in accordance 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If the Division I and Division II switchgear rooms' standpipe and hose stations are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI 2.3.3.15-6 Section 9.5.1.6, "Fire Protection of Specific Plant Areas:' of the Seabrook Station Safety Evaluation Report (NUREG-0896), dated March 1983, on page 9-53,"Safety-Related Battery Rooms;' states that"...Hose stations and portable fire extinguishers are available in the areas for fire manual suppression.. :' LRA Section 2.3.3.15 did not discuss scoping and screening results of safety-related battery rooms hose stations.

The staff requests that the applicant verify whether the safety-related battery rooms' hose stations are in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If safety-related battery rooms' hose stations are excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

- 3 RAI 2.3.3.15-7 Section 9.5.1.6, "Fire Protection of Specific Plant Areas:' of the Seabrook Station Safety Evaluation Report (NUREG-0896), dated March 1983, on page 9-53, "Emergency Diesel Generator Rooms;' states that"... The floor trench containing fuel oil piping in each diesel generator room is provided with an automatic deluge system to combat a fire in the trench:'

LRA Section 2.3.3.15 did not discuss scoping and screening results of automatic deluge system in the diesel generator room floor trench containing fuel oil piping.

The staff requests that the applicant verify whether the automatic deluge system in question is in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR 54.21(a)(1). If the automatic deluge system is excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI2.3.3.15-8 Tables 2.3.3-22 and 3.3.2-22 of the LRA do not include the following fire protection components:

fire hose stations, fire hose connections, and hose racks yard fire hydrants strainers tubing spray nozzles diesel fire pump engine-heat exchanger bonnet, shell, tubes, and exhaust silencer floor drains for fire water dikes and curbs for oil spill confinement The staff requests that the applicant verify whether the fire protection components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21 (a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.

RAI2.4.1-1 Please clarify if there are any trash racks, basket strainers, traveling screens or any other debris prevention/removing mechanisms that are part of the Intake Transition Structure that would be required to be in scope of license renewal in accordance with 10 CFR 54.4. If so, also identify the applicable aging effects and the aging managing program (AMP) related to these components.

RAI2.4.1-2 Please confirm whether the following components credited for flood protection per updated final safety analysis report (UFSAR) Section 3.4.1.1 would be required to be in scope of license renewal in accordance with 10 CFR 54.4. If so, also identify the applicable aging effects and the AMP related to these following components, otherwise, justify the exclusion from the scope of license renewal:

-4

  • The rolling steel door in the Fuel Storage Building (located at elevation 20 feet 6 inches MSL),
  • The double doors into the entrance vestibule of the Equipment Vault section of the Primary Auxiliary Building (located at elevation 20 feet 8 inches MSL).

RAI2.4.1-3 LRA Section 2.4.1 states that only the foundations of the fire protection water storage tanks are included in the scope of license renewal and subject to an AMR. Please provide additional information on the structural configuration of the tanks and the foundations, specifically. if there is any steel framing attached to the tanks that would provide additional support consistent with 10 CFR 54.4(3).

RAI2.4.6-1 Please confirm the inclusion of the structural bellows in the scope of license renewal, as applicable, and subject to an AMR per 10 CFR 54.21 (a)(1 )(i) and provide the location where they are covered. Otherwise, justify the exclusion from the scope of license renewal.

RAI2.4.6-2 LRA Section 2.4.6 states that the BORAFLEX utilized in the region 2 racks is not credited with the neutron-absorbing capacity in the criticality analyses and therefore will not be managed for reduction of neutron-absorbing. However, UFSAR Section 9.1.2.1 states that the "Region 2 spent fuel racks contain BORAFLEX as a neutron absorbing material to assure a Keff < 0.95."

Please clarify this discrepancy and confirm the inclusion or justify the exclusion of the BORAFLEX from the scope of license renewal and subject to an AMR.

November 18, 2010 Mr. Paul Freeman Site Vice President c/o Mr. Michael O'Keefe NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, N H 03874

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE SEABROOK STATION LICENSE RENEWAL APPLICATION (TAC NO ME4028)

Dear Mr. Freeman:

By [[letter::L-2010-101, Comment (1) of Larry Nicholson, on Behalf of Florida Power & Light Co., on Proposed NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants; Branch Technical Position (BTP) 7-19, Guidance for .|letter dated May 25, 2010]], NextEra Energy Seabrook, LLC (NextEra) submitted an application pursuant to Title 10 of the Code ofFederal Regulations Part 54, to renew the Operating License NPF-86 for Seabrook Station, Unit 1 (Seabrook) for review by the U.S.

Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.

The request for additional information was discussed with Mr. Rick Cliche, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or bye-mail at richar<!J?jasse@nrc.gov.

Sincerely, IRA!

Richard Plasse, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

See Next Page ADAM S Accession No' M L 103090308 OFFICE LA:DLR lPM:RPB2:DLR NAME IKing RPlasse DATE 11/8/10 11/15/10 OGC MSpencer 11/15/10 IBC:RPB2:DLR PM:RPB2:DLR DWrona RPlasse 11/18/10 11/18/10 OFFICIAL RECORD COPY

Letter to Paul Freeman from Richard Plasse dated November 18, 2010.

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REVIEW OF THE SEABROOK STATION, LICENSE RENEWAL APPLICATION (TAC NO ME4028)

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