ML20113G814

Forwards Application for Amend to License NPF-3,revising TS Definition 1.8, Containment Integrity, TS 3/4.6.1.1, Containment Integrity & Bases, TS 3/4.6.1.2, Containment Leakage & TS 3/4.6.1.3, Containment Air Locks

ML20113G814
Person / Time
Site:	Davis Besse
Issue date:	05/01/1992
From:	Shelton D CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20113G815	List: ML20113G814 ML20113G817 ML20113G818
References
NUDOCS 9205120254
Download: ML20113G814 (3)

Text

. . _ _ . . _ ._ _ _ _ _ _ _ _ ___ _ _ . . - _ _ _ _ . _ -_

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= ENERGY

_ Donsid C. Shelton 300 Madison Avenue

' Vee Presdent Nuclear . Toledo, OH 436520001 DaveBesse (419)249 2300 Docket Number 50-346 License Number NPF-3 Serial Number 1971 May 1, 1992-

-United States ~ Nuclear Regulatory Commission.

Document Control Desk Vashington, D.C. 20555

Subject:

. License Amendment Application to Revise Technical Specifications Regarding Containment Air Lock Door Operability Requirements for Containment Integrity Gentlemen:

Enclosed is an application for an amendment to the Davis-Besse Nuclear

Power-Station (DBNPS), Unit Number-1 Operating License Number NPF-3, Appendix A, Technical Specifications to' reflect the changes attached.

The proposed changes;in.volve Technical Specification (TS) Definition 1.8, Containment Integrity;;TS 3/4.6.1.1, Containment Integrity and its

. Bases; TS 3/4.6.1.2, Containment Leakage; and TS 3/4.6.1.3, Containment Air Locks.

Technical Specification 3/4.6.1.1 (Containment Integrity) requires containment integrity to be' maintained, or in accordance with the Action statement, if-it cannot be restored within one hour, the plant must.-be shutdown.- In accordance with TS Definition 1.8 (Containment l}

Integrity),-the containment air locks must be operable in order to meet containment integrity requirements. Thus, if a containment air lock is inoperable then containment integrity is not met and in accordance with l1  : TS 3/4.6.1.1, restoration vould be required within one hour if a plant l

_ shutdown is to be avoided.- However, this is inconsistent with the TS L

3/4.6.1.3 (Containment Air' Locks) Action statement, which allows a I: 24-hour restoration time before commencing a shutdown. The proposed -

change to TS Definition 1.8c reflects that containment integrity is' satisfied as long as the requirements of TS 3/4.6.1.3 (Containment _ Air L

Locks),' including its Action statement, are satisfied.

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3 Docket Number 50-346-License Number NPP . Serial Number 1971

. .Page 2 A similar licensefamendment vas approved by the NRC and issued on July 1, 1991 for the Baltimore Gas and Electric Company Calvert Cliffs Nuclear Pover Plant Unit No. 1 (Docket No. 50-317, Amendment No. 156 (TAC No.-80112) to License No. DPR-53) and Unit No. 2 (Docket No.

50-318, Amendment No. 136 (TAC No. 80113) to License No. DPR-69). In addition, NUREG-0452, Revision 5, Standard Technical Specifications for Vestinghouse Pressurized Vater Reactors, has modified standardized wording regarding'these Technical Specifications similar to that being proposed by this License-Amendment Application. The Technical Specifications issued by the NRC for the following plants alse use similar vording: Palo Verde Nuclear Generating Station (NUREG-1287),

V.C. Summer Nuclear' Station (NUREG-0932), Seabrook Station (NUREG-1386), and Vaterford Steam Electric Station (NUREG-1117).

In addition, since Surveillance Requirements (SR) 4.6.1.1b and 4.6.1.2f regarding containment air lock operability testing are redundant to the requirements of TS 3/4.6.1.3, it is proposed that these SRs be deleted.

An additional change to TS 3/4.6.1.1 is proposed to clarify the SR 4.6.1.la.1 exception that includes components located within the Shield Building-(including the annulus and containment).

A change is slso proposed to the TS 3/4.6.1.3 (Containment Air Locks)

LAction statemen to prevent an unwarranted plant shutdown evolution

.vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As currently written, the DBNPS TS vould require a plant shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if one containment air lock door becomes inoperable or if the air lock door inter 3cek mechanist becomes inoperable. However, if a door in the same containment air lock is operable, closed and locked, then containment integrity is maintained, and the plant should be allowed to continue to operate. A related change is' proposed clarifying Bases 3/4.6.1.1. This change is proposed .

~considering the wording of NUREG-0103, Revision 4 (page 3/4 6-6L),-

Standard Techn( al Specifications for Babcock and Vilcox Pressurized Vater Reactors.

Two additional changes to TS 3/4.6.1.3 are proposed. The first proposed change is to revise SR 4.6.1.3a to add-a clarification'that each containment air lock shall be demonstrated operable within 72

. hours after,each opening. The present wording states."After each opening" with no time limit.specified. Testing within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each opening is consistent with 10 CFR 50, Appendix J requirements.

The second proposed change is to add a footnote to SR 4.6.1.3a and SR 4.6.1.3b which states that the provisions of Specification 4.0.2 are

-not applicable'to these SRs. These SRs are also 10 CFR 50, Appendix J requirements. -Specification 4.0.2 allows a 25% surveillance interval extension for performance of TS SRs. However, 10 CFR 50, Appendix J does not provide an extension.to the testing period, and the TS 4.0.2 provision cannot'be allowed for these SRs. These changes vill help prevent an inadvertent violation of the requirements of 10 CFR 50,

-Appendix J.-

. Docket Number 50-346 License Number NPF-3 -

Serial Number-1971 I

. 'Page 3 Toledo Edison requests that.this amendment be issued by the NF,C by ,

November 1, 1992. Should further information be required, please contact Mr. R..V. Schrauder, Manager - Nuclear Liconsing, at (419) 249-2366.

Very truly yours,

/ -

M. / 1m Enclosure cc: A. B. Davis, Regional Administrator, NRC Region I n J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis,-NRC Region III, DB-1 Senior Resident Inspector J..R. Villiams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

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