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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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TG*.EDO
%esEDISON 00NALO C. SHELTON Vce Presnicro-Nucier (419]249 2399 Docket No. 50-346 License No. NPF-3 Scrial No. 1436 December 8,1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555
Subject:
License Amendment Application For Modification To The Appendix J.
Type A Supplemental Verification Test (TAC No. 66419)
Gentlemen:
1 The enclosed application requests that the Davis-Besse Nuclear Power I
Station, Unit No. 1 Operating License, tsppendix A, iechnical I
Specifications be revised to reflect the change attached. The proposed j
chang 2 involves Section 3/4.6,1.2, Containment Systems, Containment l
Leakage, Specification 4.6.1.2c.3.
1 The proposed change rould affect the Technical Specification requirement which sectes that the accuracy of each Type A test shall be verified by a supplemental test and shall be determined in conformance with the criteria specified in Appendix J cf 10CFR50 using the methof.s and provisions of ANS1 N45.5-1972.
Specifically, Technical Specification 4.6.1.2c.3 presently requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total esseured leakage at P,.?8 psig.
This is contrary to the a
provisions of ANSI N45.4e1972 A pendix C and is not consistent with the NRC position that the rate at which gas is injected or bled from containroent be between 0.75 and 1.25 L,
As presertly written, if the initial Type A test leakage was zero, a v$11d supplemental test could not be performed under the requirements of 10CFR50 Appendix J and ANSI N45.4-1972.
The enclosed proposed change will make the wording consistent with 10CFR50 Appendix 3, and ANSI N45.4-1972. The propoaed change is identical to the corresponding Technical Specification issued fer the Palo Verde j
/~[ pf kyN M
I B712110257 871208 PDR ADOCK 05000346 l
P PDR THE TOLEDO EDISON COMPANY EOISON PLAZA 300 MAO; SON AVENUE TOLEDO. OHIO 43350
r' Docket No. 50-346 o
License No. NPF Serful No~. 1436 Page 2 Nuclear Generating Station Unit No. 1 (reference NUREG-1133, dated May,
-1985). Additionally, this change will provide satisfactory resolution of NRC Inspection Report.0 pen Item 50-346/84029-02.
Toledo Edison requests that this amendment be' issued by June 1, 1988 and effective 30 days thereafter to support perfortnance cf the third Type A, Integrated Leak Rate Test (ILRT) during the fifth refueling outage.
Enclosed is a check for $150 as required by 10CFR170.12 (c) for 'a License Amendment Application.
Very er 1 yours,
/\\/%
D cc: DB-1 NRC Resident Inspector A. B. Dav's, Regional Administrator (2 copies)
A. W. DeAgazio, NRC/NRR Davis-Besse Project Manager State of Ohio l
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