L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)

Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)

ML17357A013
Person / Time
Site:	Beaver Valley, Davis Besse, Perry
Issue date:	12/23/2017
From:	Halnon G FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EPID L-2017-LLR-0088, L-17-372
Download: ML17357A013 (3)

Text

FENOG 341 Wite PondDrive Fnfd rJii&l NEIEd,I OpafittrgootrryEny Akron, Ohio 44i20 Grqory H. Halnon Vrbe PrcsrUen \ Reg ulatory Afairs December 23, 2017 L-17-372 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Gommission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50412, License No. NPF-73 Davis-Besse Nudear Power Station Docket No. 50-346, License No. NPF-3 Perry Nuclear Power Flant Docket No. 50-440, License No. NPF-58 Response to Request for Additignal lnformation Reqardinq Rgquest to Use ASME Code Case N-513-$. (EPID 000976/05000334/L-201 7-LLR-0088.

00092010S000346/1..-201 7-LLR-0088. 000976/05000412/L-201 7-LLR-0088. and 0 00976/05000440/L-20 1 7-LLR-00881 By letter dated August 11, 2017 (Accession Number ML17227A324), FirstEnergy Nuclear Operating Company (FENOC) requested Nuclear Regulatory Commission (NRC) approval to use ASME Code Case N-513-4, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping, Section Xl, Division 1," with limits on leakage for the evaluation and temporary acceptance of flaws in moderate energy piping in lieu of certain ASME Code, Section Xl, requirements.

By e-rnail dated Becember 11,2017, the NRC requested additional information to complete its review of the FENOC request. The FENOC response to the NRC request for information is attiached to this letter.

There are no regulatory commitrnents contained in this submittal. lf there are any questions or if additional information is required, please contiact Mr. Thomas A. Lentz, Manager - FIeet Licensing, at (330) 315-6810.

Since ry H. Halnon

Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Perry Nuclear Power Plant L-17-372 Page 2

Attachment:

Response to Request for Additional lnformation Regarding Request to Use ASME Code Case N-513-4 CC:

NRC Region t Adrninistrator NRC Region lll Administrator NRC Resident lnspector - Beaver Valley NRC Resident Inspector - Davis-Besse NRC Resident lnspector - Perry NRC Project Manager- FENOC Fleet Director BRPIDEP Site BRP/DEP Representative Utitity Radiological Safety Board

Attachment L-17-372 Response to Request for Additional lnformation Regarding Request to use o**?fJJ? N-513-4 "gii-The NRC staffs request for additional information is provided below in bold text, followed by the FENOG response.

Request for Additional lnformation Section 5, n'Propssed Alternative and Basis for Use," of the propssed alternative in the licensee's August 11, 2017, letter states, "The critical leakage rate is determined as the highest leakage rate that can be tolerated and will be based on the allowable loss of inventsry or the maximum leakage that can be tolerated relative to room flooding, among others." Confirm that the critical leakage rate will be based on the most limiting condition. For example, if the maximum allowed flooding is 50 gallons per minute (gpm) and the maximum allowed loss of inventory is 25 gpm, 25 gpm is the critical leakage rate.

Response

The critical leakage rate will be determined based on the most limiting condition, as described in the example.