ML13261A043

Requesty for Additional Information Regarding License Amendment Request for Extended Power Uprate

ML13261A043
Person / Time
Site:	Peach Bottom
Issue date:	09/18/2013
From:	Richard Ennis Plant Licensing Branch 1
To:	Pacilio M Exelon Generation Co
Ennis R, NRR/DORL/LPL1-2, 415-1420
References
TAC ME9631, TAC ME9632
Download: ML13261A043 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 18, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR EXTENDED POWER UPRATE (TAC NOS. ME9631 AND ME9632)

Dear Mr. Pacilio:

By letter dated September 28,2012, as supplemented by letters dated February 15, 2013, May 7, 2013, May 24, 2013, June 4, 2013, June 27, 2013, July 30, 2013, July 31, 2013, August 5,2013, August 22,2013, August 29,2013, and September 13, 2013 (Agencywide Documents Access and Management System Accession Nos. ML122860201, ML13051A032, ML13129A143, ML13149A145, ML13156A368, ML13182A025, ML13211A457, ML13213A285, ML13217A431, ML13240A002, ML13241A418, and ML13260A076, respectively), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would authorize an increase in the maximum power level from 3514 megawatts thermal (MWt) to 3951 MWt.

The requested change, referred to as an extended power uprate, represents an increase of approximately 12.4 percent above the current licensed thermal power level.

The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The RAI questions were provided in draft form to Mr. Kevin Borton of your staff via e-mails on August 6, 2013, and August 26, 2013. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.

A conference call between the NRC staff and the Exelon staff was held on September 17, 2013, to discuss the questions. During the call, Mr. Borton stated that Exelon would provide a response to the RAI questions within 30 days of the date of this letter.

Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108.

M. Pacilio - 2 If you have any questions, please contact me at (301) 415-1420.

Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT EXTENDED POWER UPRATE EXELON GENERATION COMPANY, LLC PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 By letter dated September 28, 2012, as supplemented by letters dated February 15, 2013, May 7,2013, May 24,2013, June 4,2013, June 27,2013, July 30,2013, July 31,2013, August 5,2013, August 22,2013, August 29,2013, and September 13, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML122860201, ML13051A032, ML13129A143, ML13149A145, ML13156A368, ML13182A025, ML13211A457, ML13213A285, ML13217A431, ML13240A002, ML13241A418, and ML13260A076, respectively), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would authorize an increase in the maximum power level from 3514 megawatts thermal (MWt) to 3951 MWt. The requested change, referred to as an extended power uprate (EPU), represents an increase of approximately 12.4 percent above the current licensed thermal power level.

The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific request for additional information (RAI) is addressed below.

Reactor Systems Branch (SRXB)

Reviewer: Ben Parks SRXB RAI-29 With regard to the overpressure analyses performed in support of the requested EPU, provide the number of safety relief valves (SRVs) and safety valves (SVs) assumed available, including setpoints and assumed lift setpoint tolerances. Confirm whether the EPU safety analyses bound conditions associated with the proposed SRV and SV lift setpoint tolerance increases that were requested by Exelon's license amendment request for PBAPS, Units 2 and 3, dated June 10,2013 (ADAMS Accession No. ML131750144).

SRXB RAI-30 to the application dated September 28, 2012, describes proposed modifications to PBAPS associated with the EPU. Condensate storage tank (CST) modifications are described in Enclosure ge to Attachment 9. Section 3.1 of Enclosure ge describes the addition of a CST standpipe to "ensure a CST dedicated usable volume for the HPCI [high pressure coolant injection] and RCIC [reactor core isolation cooling] pumps for SBO [station blackout], A TWS

[anticipated transient without scram1, and Appendix R events." This section refers to Enclosure

- 2 Section 2.3.5, "Station Blackout," of the Power Uprate Safety Analysis Report (PUSAR1) and states that "[t]he CST volume needed for SBO at EPU conditions is approximately 94,570 gallons." Provide the EPU SBO analysis that concludes that this is the CST inventory required for mitigation.

Electrical Engineering Branch (EEEB)

Reviewer: Swagata Som EEEB RAI-16 On page 2-135 in Section 2.3.5 of the PUSAR, the licensee states that "[e]valuation of the PBAPS Class 1E Battery Capacity has shown that PBAPS has adequate battery capacity to support decay heat removal during a SBO for the required coping duration." Page 2-134 of the PUSAR indicates that SBO was re-evaluated for the proposed EPU using the guidelines of NUMARC 87-00, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors" and NRC Regulatory Guide (RG) 1.155, "Station Blackout."

Explain the design duty cycle of Class 1E battery to support all SBO loads for the required SBO coping duration. Confirm that the PBAPS Class 1E batteries and alternate alternating current sources will have adequate capacity and capability during the plant power uprated condition to support SBO loads for the entire SBO coping duration consistent with RG 1.155 and NUMARC 87-00.

Health Physics and Human Performance Branch (AHPB)

Reviewer: Molly Keefe AHPB RAI-6 On pages 2 and 3 of Attachment 3 to the supplement dated May 24, 2013, the licensee described changes to current operator actions related to emergency or abnormal operating procedures that will occur as a result of the proposed EPU. Specify what controls are in place to assure the following:

a) Cues exist that alerts the operator to action in a timely manner.

b) Tasks are within the capability of all PBAPS operators.

c) Operator feedback capability exists to determine whether the actions are complete and effective.

d) Training content, method, and frequency are determined and implemented.

e) The location and accessibility of required displays and controls are considered.

1 A proprietary (i.e., non-publicly available) version of the PUSAR is contained in Attachment 6 to the application dated September 28,2012. A non-proprietary (i.e" publicly available) version of the PUSAR is contained in Attachment 4 to the application dated September 28, 2012.

-3 f} List the controlled procedures that guide the operator's actions for the cited changes to operator actions.

AHPB RAI-7 Given the number of new operator actions, please discuss how the impacts of the EPU and associated plant modifications were identified and what, if any, analysis was done to understand impacts to operator workload.

M. Pacilio -2 If you have any questions, please contact me at (301) 415-1420.

Sincerely,

/ra!

Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278

Enclosure:

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