ML14162A409

Request for Additional Information Concerning Alternative Accident Source Term Design Bases (TAC No. MF3197)(L-12-306)

ML14162A409
Person / Time
Site:	Perry
Issue date:	06/24/2014
From:	Ellen Brown Division of Operating Reactor Licensing
To:	Harkness E FirstEnergy Nuclear Operating Co
Eva Brown, NRR/DORL 415-2315
References
L-13-306, TAC MF3197
Download: ML14162A409 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 24, 2014 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY -A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097

SUBJECT:

PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION CONCERNING ALTERNATIVE ACCIDENT SOURCE TERM DESIGN BASES (TAC NO. MF3197)(L-13-306)

Dear Mr. Harkness:

By application dated December 6, 2013, as supplemented by a letter dated February 27, 2014 (Agencywide Document Access and Management System (ADAMS) Accession Nos.

ML13343A013 and ML14059A221 ), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request for the Perry Nuclear Power Plant. The proposed amendment would revise the Updated Safety Analyses Report to reflect updated radiological calculations using an alternative accident source term for the applicable design bases event and to revise the technical specification definition of DOSE EQUIVALENT IODINE-131.

The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. Phil Lashley of your staff on May 20, 2014, it was agreed that FENOC would provide a response within 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

E. Harkness If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2315.

Sincerely, IRA/

Eva A. Brown, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440

Enclosure:

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

REQUEST FOR ADDITIONAL INFORMATION ALTERNATIVE SOURCE TERM DESIGN BASES FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-440

1. For those changes to the current licensing basis (CLB) parameters used in the affected dose consequence analyses, provide additional information describing for each affected design basis accident, all the basic parameters used in the dose consequence analyses.

For each parameter, please indicate the CLB value, the revised value where applicable, and the basis for any changes made to the CLB values. The U.S. Nuclear Regulatory Commission (NRC) staff requests that this information be presented in separate tables for each accident evaluated.

2. On page 7 of the submittal evaluation, FirstEnergy Nuclear Operating Company addressed the impact of the proposed changes on the radiological habitability of the Technical Support Center. However, the application appears to be silent on the impact of those changes on the calculations supporting the establishment of numeric thresholds for emergency action levels (EALs) related to readings on: (1) radiological effluent radiation monitors, and (2) the in-containment high range radiation monitor readings used in the fission product barrier matrix EALs. In addition to the source term change and core inventory changes, the NRC staff notes that you have proposed changes in other analysis assumptions (e.g., filter removal efficiencies, containment leakage rates, drywell flows, containment spray credit, etc.) that could potentially affect the validity of the previous EAL thresholds. Explain the impact of the changes on these EAL thresholds.

3. Address whether any nonsafety-related systems and components are credited in the accident source term (AST) analyses. If so,:

a. Describe the independence (electrical and physical separation) of these systems from the safety-related systems. Provide a detailed discussion on why a fault on the non-Class 1E electrical circuit will not propagate to the Class 1E electrical circuit.

b. Describe the redundancy of these systems and how these systems meet the single failure criterion.

4. Address whether any loads are being added to the emergency diesel generators (EDGs). If so, describe their impact on the capability and capacity of the EDGs.

Also, describe changes, if any, being made to the EDG loading sequence to support this license amendment request.

5. Discuss why there are no changes to the Environmental Qualification profiles as a result of the full implementation of the AST.

Enclosure

ML14162A409 *by memo NRR-106 OFFICE LPLII-2/PM LPLIII-2/LA EEEB/BC* ARCB/BC* NSIR/BC* LPLIII-2/BC NAME EBrown SRohrer JZimmerman UShoop JAnderson TTate DATE 6/13/14 6/12/14 5/5/2014 3/27/14 5/20/2014 6/24/14