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MONTHYEARML20096C6631984-08-27027 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
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
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
ML20215L8391987-05-0404 May 1987
Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d
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
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
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
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
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
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
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
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
1987-05-04
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TOLEDO
%mm EDISON A Carterer Erergy Ctyrery Docket No. 50-346 DONAU) C. SHELTON License No. NPF-3 vape aa-arwr si9)e4 m oo Serial No. 1474 March 7, 1988 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Subject:
License Amendment Application to Uncouple the 10CFR50, Appendix J Type A Testing and 10-year Inservice Inspection Intervals (TAC No. 66418)
Gentlemen:
The enclosed application requests that the Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A, Technical Specifications, be revised to reflect the changes attached. The proposed changes involve Section 4.6.1.2.a Containment Systems - Containment Leakage Surveillance Requirements, and Bases Section 3/4.6.1.2 Containment Leakage.
The proposed changes would allow the third Type A test (Containment Integrated Leak Rate Test) and the 10-year inservice inspections to be uncoupled and performed in separate refueling outages. This change is consistent with the request for exemption from 10CFR50, Appendix J previously submitted to the NRC on November 20, 1987 (Serial No. 1443, TAC No. 66700).
It should also be noted that, subsequent to NRC's concurrence with the first 10-year inservice inspection interval extension to the Spring 1989 outage on May 18, 1983 (Log No. 1-791), Toledo Edison has advised NRC of a further interval extension by letter dated October 15, 1987 (Serial No. 1-752).
This latter extension accounts for the interval extension due to the recent 18 month outage, as permitted by ASME Section XI, Article IWA-2400(c), in order to allow the end of the first 10-year interval to i
coincide with the sixth refueling outage which is currently scheduled for Fall 1989.
This extension would further separate the tine frames for the l
required performance of the third Type A test and the scheduled 10-year 1
inservice inspections.
Toledo Edison requests that the attached changes be issued and that the aforecentioned exemption be granted prior to power ascension to h.le 4 from the fifth refueling outage. Mode 4 entry from the refueling outage is presently scheduled for August 1988.
8803160135 880307 PDR ADOCK 05000346 P
DCD THE TOLEDO EDfSON COMPANY EDISON PLAZA 300 MADfSON AVENUE TOLEDO. OHt0 43652 YI A0 rec.@ t,a}cHErJ<
}
Docket No. 50-346 License No. NPF-3 Serial No. 1474 Page 2 Enclosed is a check for $150 as required by 10CFR170.12(c) for a License Amendment Application.
Very tr y yours,
/N kt %
RMC:Fam cc:
A. B. Davis, Regional Administrator (2 copies)
DB-1 NRC Resident Inspector A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager State of Ohio
