Letter Sequence Other |
|---|
|
|
MONTHYEARML19322C6651979-02-0202 February 1979
Discusses Revised Procedure for Ofc of Executive Legal Director Involvement in Processing OL Amend Applications. Review of Safety Evaluations & Eias Re Proposed OL Amends Will Be Discontinued as of 790215
Project stage: Approval
ML19322C6631979-02-0202 February 1979
Forwards Memo Announcing Radical Change in Ofc of Executive Legal Director Activities Re OL Amend Applications
Project stage: Other
ML20140D1911986-01-22022 January 1986
Proposed Tech Specs,Clarifying Station Review Board Duties & Responsibilities
Project stage: Other
ML20140D1741986-01-22022 January 1986
Application for Amend to License NPF-3,changing Tech Specs to Clarify Station Review Board Duties & Responsibilities
Project stage: Request
ML20140D1451986-01-22022 January 1986
Forwards Application for Amend to License NPF-3,changing Tech Specs Clarifying Station Review Board Duties & Responsibilities.Separate Amend Application Being Prepared to Address Addl Administrative Changes.Fee Paid
Project stage: Request
ML20215K3801987-05-0404 May 1987
Requests Reissuance of Table 3.6-2, Containment Isolation Valves of Tech Spec 3/4.6.3,correcting Typos in 840911 Application to Amend License NPF-3
Project stage: Request
ML20237K8441987-08-28028 August 1987
Requests That Revised Tech Spec 6.5.1.6,submitted w/870122 License Amend Request,Reflects Station Review Board Responsibility to Review safety-related Aspects of Proposed Procedures,Mods,Tests & Experiments,Per NUREG-0103,Rev 4
Project stage: Other
ML20150B9711987-09-11011 September 1987
Discusses Plant Organizational Changes.Meeting W/E Butcher & Bryan Should Be Set Up
Project stage: Meeting
ML20237A6881987-12-0808 December 1987
Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends
Project stage: Other
ML20238E5701987-12-28028 December 1987
Provides Clarification to 860122 Application for Amend to License NPF-3 Re Station Review Board Responsibilities,Per 871127 & 1202 Telcons W/Aw Deagazio & Staff,Respectively, Revising Tech Specs 6.5.1.6(b) & 6.5.3.1(a),(b),(d) & (E)
Project stage: Supplement
ML20149J0571988-02-17017 February 1988
Provides Addl Clarification of License Amend Request Submitted on 860122 Involving Proposed Tech Spec 6.5.3.1(c). Clarified Administrative Control Will Require Technical Reviews on Each Mod Affecting Nuclear Safety
Project stage: Other
ML20150C4511988-03-0909 March 1988
Amend 109 to License NPF-3,revising Responsibilities & Authority of Station Review Board & Adding Section to Technical Review & Control
Project stage: Other
ML20150C4621988-03-0909 March 1988
Safety Evaluation Supporting Amend 109 to License NPF-3
Project stage: Approval
ML20150C4731988-03-0909 March 1988
Notice of Denial of Amend to License NPF-3 Re Deleting Requirement in Tech Spec 6.5.1.6.e Concerning Station Review Board Responsibility to Investigate & Rept Tech Spec Violations
Project stage: Other
ML20150B9671988-03-11011 March 1988
Requests That Encl 870911 Memo from J Scinto Be Included in Docket Files.Memo Relates to 870122 Application for Amend to License NPF-3 Re Organization Changes
Project stage: Other
1987-05-04
[Table View] |
Text
- _ _ - _ - _ _ _ _ _ _
TOLEDO 3
%ms EDISON Docket No. 50-346 DONALO C. SHELTON vce Presdent-NtrJear (419] 249 P399 License No. NPF-3 Serial No. 1418 Auguet 28, 1987 j
l United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Subject:
Station Review Board Responsibilities (TAC No. 61468)
Gentlemen:
On January 22, 1986, Toledo Edison submitted a License Amendment Request (Serial No. 1235) to your office requesting a revision to the Davis-Besse Operating License, Appendix A, Technical Specifications Sections 6.5.1.3, 6.5.1.6, 6.5.1.7, 6.5.3, G.8.2 and 6.8.3.
These changes were requested to revise and clarify the Station Review Board (SRB) responsibilities.
As stated in the Safety Evaluation accompanying the submittal:
"The safety function of the SRB is to advise the F1 wt Manager on all matters relating to nuck ar safety.
In perforutng these duties, the SRB has responsibilities, for reviews as outlir.ed in Section 6.5.1.6."
The proposed Technical Specification revision, howe' er, does not explicit.ly
)
state this. Please ensure that revised Technical ! specification 6.5.1.6, as issued with the License Amendment, reflects the SRB's responsibility "to review" the safety-related aspects of proposed procedures, modifica-tions, tests and experiments in cases where an unreviewed safety question does not exist. This review responsibility is corsletent with the approach of the existing Technical Specification wording and the B&W Standard Tech-nical Specifications, NUREG-0103, Revision 4.
As before, in cases where an unreviewed safety questic exists, the SRB will perform a technical as well as a safety review.
Very truly yours, j
CAB:MHL: pig ec: DB-1 NRC Resident Itgycter.
A B. Davis, Regional ' Administrator (.2' copies)
A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager pd[
,..~
THE TOLEDO E9ISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHt0 43652 8709080064 070828 PDR ADOCX 05000346 P
pyg
USNRG-05 M1 SEP -t4 A 4 53 3
- ~ - ~ ~ _ _ _
