ML20236Y342

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

ML20236Y342
Person / Time
Site:	Davis Besse
Issue date:	12/08/1987
From:	Shelton D TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236Y344	List: ML20236Y342 ML20236Y357 ML20236Y377
References
1436, TAC-66419, NUDOCS 8712110257
Download: ML20236Y342 (2)

Text

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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 provisions of ANSI N45.4e1972 aA 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 M

B712110257 871208 PDR ADOCK 05000346

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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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