ML082600576: Difference between revisions

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#REDIRECT [[L-08-241, Copy of Applicable Portions of the NRC & Davis-Besse Improved Technical Specifications Conversion Website - Chapters 1.0, 2.0 and 5.0 & Sections 3.3, 3.5, 3.7, 3.8, & 3.9 & Response to Request for Additional Information Related to Update to]]
| number = ML082600576
| issue date = 08/26/2008
| title = Copy of Applicable Portions of the NRC & Davis-Besse Improved Technical Specifications Conversion Website - Chapters 1.0, 2.0 and 5.0 & Sections 3.3, 3.5, 3.7, 3.8, & 3.9 & Response to Request for Additional Information Related to Update to
| author name = Allen B S
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000346
| license number = NPF-003
| contact person =
| case reference number = L-08-241, NUREG-1430, TAC MD6398, TAC MD6399, TAC MD6400
| document type = Letter
| page count = 3
| project = TAC:MD6398, TAC:MD6399, TAC:MD6400
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:FENOC"EN % 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President
-Nuclear Fax: 419-321-7582 August 26, 2008 L-08-241 10 CFR 50.90 ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001
 
==SUBJECT:==
Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Copy of Applicable Portions of the U.S. Nuclear Regulatory Commission and Davis-Besse Nuclear Power Station Improved Technical Specifications Conversion Website -Chapters 1.0, 2.0, and 5.0 and Sections 3.3, 3.5, 3.7, 3.8, and 3.9, TAC No. MD6398 and Response to Request for Additional Information Related to Update to B&W Plants Standard Technical Specifications NUREG-1430, TAC Nos. MD6399 and MD6400 By letter dated August 3, 2007, as supplemented by letters dated October 29, 2007, May 16, 2008 (2 letters), July 23, 2008, and August 07, 2008, FirstEnergy Nuclear Operating Company (FENOC) submitted an application to amend the Technical Specifications of Davis-Besse Nuclear Power Station, Unit 1 (DBNPS), revising the current Technical Specifications (CTS) to the Improved Technical Specifications (ITS)consistent with the Improved Standard Technical Specifications (ISTS) as described in NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants," Revision 3.1, and certain generic changes to the NUREG.As part of the NRC review of the Davis-Besse ITS submittal dated August 3, 2007, NRC questions were provided using the NRC and DBNPS ITS Conversion Website. The NRC and DBNPS ITS Conversion Website was developed specifically to expedite NRC review and minimize the time delay between review and posting of NRC questions, development and posting of FENOC responses, and acceptance and closure of each identified NRC question by the responsible NRC reviewer.Attachment 1 of this letter provides a copy of applicable portions of the U.S. Nuclear Regulatory Commission (NRC) and DBNPS ITS Conversion Website suitable for posting on the DBNPS docket, Docket No. 50-346. FENOC provided this information on the NRC and DBNPS ITS Conversion Website. FENOC used this information in NJ -12 Davis-Besse Nuclear Power Station L-08-241 Page 2 of 3 development of the Davis-Besse ITS supplemental submittal letter dated August 07, 2008. This information also documents the NRC review process for approving the requested amendments to the DBNPS Facility Operating License.Attachment 1 is arranged by section. Each section is arranged chronologically by the dates of the original NRC questions, and includes the applicable NRC questions, FENOC response, and any attached electronic documentation, except the draft ITS submittal markup pages. Draft ITS markup pages are not included since the changes were provided in the Davis-Besse ITS supplemental submittal letter dated August 07, 2008. This letter provides the questions for those Volumes included in the August 07, 2008 letter: Volume 3, Chapter 1.0 -Use and Application, Revision 1;Volume 4, Chapter 2.0 -Safety Limits, Revision 1;Volume 8, Section 3.3 -Instrumentation, Revision 1;Volume 10, Section 3.5 -Emergency Core Cooling Systems (ECCS), Revision 1;Volume 12, Section 3.7 -Plant Systems, Revision 1;Volume 13, Section 3.8 -Electrical Power Systems, Revision 1;Volume 14, Section 3.9 -Refueling Operations, Revision 1; and Volume 16, Chapter 5.0 -Administrative Controls, Revision 1.The applicable portions of the NRC and DBNPS ITS Conversion Website for the remaining Vo!umes (Volumes 5, 6, 7, 9, 11, and 15) were provided by letter dated May 16, 2008.Two questions from the website are not included in Attachment
: 1. The question numbers are 200712171517 and 200802121126.
Both questions are associated with an NRC letter dated June 18, 2008. In that letter, the NRC staff requested additional information to complete the application review. Copies of these website questions will be provided with FENOC's written response to the NRC's request in a separate letter.In addition, by letter dated February 22, 2008, the NRC staff requested additional information related to two beyond scope items. FENOC provided responses to the same NRC requests on the NRC and DBNPS ITS Conversion Website, and the questions were subsequently closed by the NRC. The FENOC responses to the NRC staff's questions are contained within the applicable dialogue response in Attachment 1.Attachment 2 provides the NRC staff's questions, with a reference to the appropriate dialogue response.
Davis-Besse Nuclear Power Station L-08-241 Page 3 of 3 There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing, at (330) 761-6071.I declare under penalty-of perjury that the foregoing is true and correct.Executedon 4Yaj,4- 26,, -Sincerely, Barry S. A1176, Vice President-Nuclear Attachments:
: 1. Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved Technical Specification (ITS)Conversion Website.2. Response to Request for Additional Information Related to Update to B&W Plants Standard Technical Specifications NUREG-1430 cc: (all w/o Attachment)
NRC Region III Administrator NRR Project Manager NRC Resident Inspector Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)Utility Radiological Safety Board}}

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