ML20059L692

Amend 68 to License DPR-21,revises Surveillance Requirements for Local Leak Rate Testing Which Are Included in TS Section 4.7.A,to Remove 5% L Limit

ML20059L692
Person / Time
Site:	Millstone
Issue date:	11/10/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059L690	List: ML20059L687 ML20059L692 ML20059L694
References
NUDOCS 9311170292
Download: ML20059L692 (5)

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UNITED STATES i

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NUCLEAR REGULATORY COMMISSION f

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NORTHEAST NELEAR ENERGf COMPANY l

DOCKET N0. 50-245 i

MILLSTDNE NUCLEAR POWER STATION. UNIT 1 i

8M[NQtiENT 10 FACILITY OPERATING t.lCINSI i

Amendment No. 68 i

j License No. DPR-21 l

2 1.

The Nuclear Regulatory Conunission (the Commission) has found that:

i A.

The application for amendment by Northeast Nuclear Energy Company l

(the licensee), dated September 1, 1993, complies with the j

i standards and requirements of the Atomic Energy Act of 1954, as l

amended (the Act), and the Commission's rules and regulations set forth in 10 CfR Chapter I; j

2 B.

The facility will operate in conformity with the application,.the j

provisions of the Act, and the rules and regulations of the j

Commission; q

l C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health.

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; i

and j

E.

The issuance of this amendment is in accordance with 10 CfR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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o 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-21 is hereby amended to read as follows:

i (2) Technical - Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be j

implemented within 30 days of issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Direc i

oject Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 10, 1993 a

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ATTACHMENT TO LICENSE AMENDMENT NO.

68 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following page of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 7-6 3/4 7-6 B 3/4 7-8a l

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SURVEILLANCE REQUIREMENT (Continued) 4.7 CONTAINMENT SYSTEMS 4.7.A.3.e.(1)(a) A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests.

i (b) Any one main steam line isolation valve 11.5 scf/hr at 25 psig.

f.

Continuous leak rate monitor:

(1)

When the primary containment is inerted, the containment shall be continuously monitored for gross leakage by review of the inerting system makeup requirements.

(2)

This monitoring system may be taken out of service for the purpose of maintenance or testing but shall be returned to service as soon as practical.

The interior surfaces of the drywell shall be visually inspected g.

each operating cycle for evidence of deterioration.

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Millstone Unit ]

3/4 7-6 Amendment No. 68 0111 I

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4.7 CONTAINMENT SYSTEMS BASES 3

The combined leakage rate for all penetrations and valves subject to Type B l

and C tests is limited to 607. of the allowable test leak rate, in accordance with 10CFR50 Appendix J.

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i Millstone Unit 1 B 3/4 7-Ba Amendment No. 68 0112 f

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