Letter Sequence Request |
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MONTHYEARML19322C6631979-02-0202 February 1979
Forwards Memo Announcing Radical Change in Ofc of Executive Legal Director Activities Re OL Amend Applications
Project stage: Other
ML19322C6651979-02-0202 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
ML20096C6401984-08-27027 August 1984
Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Request
ML20096C6631984-08-27027 August 1984
Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid
Project stage: Request
ML20096C6821984-08-27027 August 1984
Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Other
ML20101N4281984-12-11011 December 1984
Amend 79 to License NPF-3,changing Tech Spec Table 3.6-2 Re Containment Isolation Valve to Allow for Modified Steam Generator Blowdown & Drain Sys
Project stage: Other
ML20101N4481984-12-11011 December 1984
Safety Evaluation Supporting Amend 79 to License NPF-3
Project stage: Approval
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
ML20140D1911986-01-22022 January 1986
Proposed Tech Specs,Clarifying Station Review Board Duties & Responsibilities
Project stage: Other
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
ML20215L8391987-05-0404 May 1987
Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d
Project stage: Other
ML20215L8351987-05-0404 May 1987
Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d Re Auxiliary Feedwater Sys as Result of 850609 Loss of Feedwater Event. Supporting Documentation Encl
Project stage: Request
ML20215L8141987-05-0404 May 1987
Forwards Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d to Reflect Mods to Steam Line Piping to Auxiliary Feed Pump Turbine Following 850609 Loss of Feedwater Event.Fee Paid
Project stage: Request
ML20216H6041987-06-25025 June 1987
Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys
Project stage: Other
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
ML20236H0211987-10-27027 October 1987
Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods
Project stage: Other
ML20236G9801987-10-27027 October 1987
Application for Amend to License NPF-3,revising Tech Spec Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods.Fee Paid
Project stage: Request
ML20236Y3421987-12-0808 December 1987
Forwards Application for Amend to License NPF-3,revising Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage.Fee Paid
Project stage: Request
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
ML20150B0321988-03-0707 March 1988
Forwards Application for Amend to License NPF-3 Changing Tech Spec Section 4.6.1.2.a to Allow Third Type a Test & 10-yr Inservice Insps to Be Uncoupled & Performed in Separate Refueling Outages.Fee Paid
Project stage: Request
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
ML20150C4621988-03-0909 March 1988
Safety Evaluation Supporting Amend 109 to License NPF-3
Project stage: Approval
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
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
ML20148B1781988-03-14014 March 1988
Amend 110 to License NPF-3,revising Tech Specs to Permit Extension of Range of RCS Pressure Instrument on Auxiliary Shutdown Panel to 3,000 Psig from 2,500 Psig & Tech Spec 3.3.3.5,Table 3.3-9,Item 3
Project stage: Other
ML20151X2411988-04-29029 April 1988
Forwards Discussion of & Proposed Revs to Tech Specs for Resolution of NRC Comments Concerning Deletion of Auxiliary Feedwater Pump Turbine Inlet Steam Pressure Interlock Operability Requirements,Per 880406 Telcon
Project stage: Other
1987-06-25
[Table View] |
Text
i-d Tottoo
%mmEDISON DONAM) C. SHELTON
- w. pmen-w Docket No. 50-346 License No. NPF-3 Serial No. 1375 May 4, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 Gentlemen:
On December 11, 1984 the Nuclear Regulatory Commission (NRC) issued Amend-ment No. 79 (Log No. 1659) to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1.
This amendment revised Table 3.6-2, Containment Isolation Valves, of the Appendix A, Technical Specifications to allow for the modified steam generator blowdown and drain system.
Toledo Edison had submitted its License Amendment Request concerning these revisions on September 25, 1981 (Serial No. 738), as modified by letters dated September 26, 1983 (Serial No. 988), and September 11, 1984 (Serial No. 1081).
One of these revisions (Serial No. 1081), to Table 3.6-2, Containment Isolation Valves, concerned the addition of closure time requirements for the existing valves MS 603 (Penetration No. 57) and MS 611 (Penetration No. 60). However, when the requested closure time requirements were added by the NRC Staff in Amendment No. 79, the two previously existing "#" signs (denoting not subject to Type C leakage testing) following the valve numbers were inadvertently left off. This deletion was not requested by Toledo Edison, nor was it discussed in the NRC's Safety Evaluation to Amendment No. 79.
Recognizing this, a discussion was held on June 19, 1986, between the NRC, Office of Nuclear Reactor Regulation, Davis-Besse Project Manager and i
Toledo Edison. The NRC Staff requested that Toledo Edison formally submit a request to correct these typographical errors, however, this submittal was not to be a License Amendment Request.
8705110177 870504 I
PDR ADOCK 05000346 P
PDR
'l y THE TOLEDO EDfSON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
Do'ckat Ns. 50-346 License No. NPF-3 Serial No. 1375 Page 2 To correct this typographical error, Toledo Edison requests that the NRC re-issue Table 3.6-2, page 3/4 6-18, of Technical Specification 3/4.6.3 adding the "#" signs to valve numbers MS 603 and MS 611.
This request concerns the correction of typographical errors with regards to a previous application dated September 11, 1984 (Serial No. 1081).
Therefore, no license application fee per 10 CFR 170.12(c) is required.
Very trul
- ours, f
'[
DCS: CAB:plf cc: DB-1 NRC Resident Inspector A. B. Davis, Regional Administrator (2 copies)
A. W. DeAgazio, NRC/NRR DB-1 Project Manager
