Text

Amends 193 & 174 to Licenses NPF-4 & NPF-7,respectively, Revising NA-1&2 TS 4.6.1.2.a to Permit Approved Exemptions to Containment Integrated Leak Rate Frequency Requirements
	ML20083M568
Person / Time
Site:	North Anna
Issue date:	05/15/1995
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20083M571	List: ML20083M568;
References
	NUDOCS 9505190325
	Download: ML20083M568 (8)
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 0001 A...../

VIRGINIA ELECTRIC'AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.193 License No. NPF-4 1.

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

A.

The application for-amendment by Virginia Electric and Power Company-et al., (the licensee) dated March 2,1995, complies with the standards and requirements of the Atomic Energy Act of-1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

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; 4

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, and E.

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

l 9505190325 950515 PDR ADOCK 05000338 P

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2.

Accordingly,.the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Soecifications The Tec'hnical Specifications contained in Appendices A and'B, as revised through Amendment No.193, 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 its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COM ISSION L WHAM

$ / David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 15, 1995 l

l' ATTACHMENT TO LICENSE AMENDMENT NO.193 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following page of'the Appendix "A" Technical Specifications with the enclosed page as indicated.

The revised page is identified by amendment number and containsvertical lines indicating the area of change.

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N CONTAINMENT SYSTEMS CONTAINMENT LE AKAGE -

LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a An overall integrated leakage rate ofless than or equal to L.,0.1 percent by weight a.

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at the calculated peak containment pressure P.,

greater than or equal to 44.1 psig.

b.

" A combined leakage rate of less than or equal to 0.60 L for all penetrations and a

valves subject to Type B and C tests, when pressurized to P., greater than or equal to 44.1 psig.

APPLICABILITY-MODES 1,2,3, and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C -

tests exceeding 0.60 L., restore the overall integrated leakage rate to less than 0.75 L, and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 L prior to increasing the Reactor Coolant System temperature above 200*F.

a SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of either ANSI N45.4-1972 for leakage rate point data analysis or ANSI /ANS-56.8-1987 for mass point data analysis with a minimum test duration of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a.

Type A (Ovem11 Integrated Containment 1.eakage Rate) tests shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, except as modified by NRC-approved exemptions.

b.

Type B and C tests shall be conducted with gas at P., greater than or equal to 44.1 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks.

2.

Penetrations using continuous leakage monitoring systems.

NORTH ANNA TINIT 1 3/46-2 Amendment No.1^',108, ! !0, 4M,193 e

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' VIRGINIA-ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2

AMENDMENT TO FACILITY OPERATING LICENSE.

Amendment No.174 License No. NPF-7--

1.

The Nuclear Regulatory Comission (the Comission) has-found that:

A.

The application for amendment by' Virginia Electric and Power Company et al., (the licensee) dated March 2,1995,. complies with the

'3 standards and requirements of.the Atomic Energy Act of 1954,=as amended '(the Act),-and.the Comission's rules and regulations set

'forth in 10 CFR Chapter I; B.

The facility will' operate in conformity with the application, the provisions of the. Act, and the rules and regulations of the Comission; C.

'There is reasonable assurance (i) 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 Comission's regulations;.

D.

The issuance of this amendment will not be inimical to the comon l

defense and security or to the health and safety of. the public; and E.

The issuance of this amendment is in accordance'with:10 CFR Part 51 j

of the Comission's regulations and all applicable requirements have been satisfied.

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l l 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A'and B, as revised through Amendment No.174

, are hereby incorporated in the L

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

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

4 FOR THE NUCLEAR REGULATORY COMMISSION i

Ad LSA4H/ wad M [ David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 15,1995

ATTACHMENT TO LICENSE AMENDMENT N0. 174 TO FACIllTY OPER6 TING LICENSE N0. NPF-7 QQQKET N0. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and containsvertical lines indicating the area of change.

Remove Paaes Insert Paaes 3/4 6-2 3/4 6-2 j

l 8

CONTAINMENT SYSTEMS

- CONTAINMENT LEAKAGE ~

LIMITING CONDITION FOR OPERATION.

q 3.6.1.2 Containment leakage rates shall be limited to:

An overall integrated leakage rate ofless than or equal to L.,0.1 percent by weight l

a.

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at the calculated peak containment pressure P.,

greater than or equal to 44.1 psig.

b. -

A combined leakage rate of less than or equal to 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P., greater than or equal to 44.1 psig.

APPLICABILITY:

MODES 1,2,3, and 4.

ACTION:

- With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., restore the overall integrated leakage rate to less than 0.75 L, and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 L, prior to increasing the Reactor Coolant System temperature above 200 F.

SURVEILLANCE REQUIREMENTS l

4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of either ANSI N45.4-1972 for leakage rate point data analysis or ANSI /ANS-56.8-1987 for mass point data analysis with a minimum test duration of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

a.

Type A (Overall Integrated Containment Leakage Rate) tests shall be conducted in accordance with :he requirements specified in Appendix J to 10 CFR 50, except as modified by NRC-approved exemptions.

b.

Type B and C tests shall be conducted with gas at P., greater than or equal to 44.1 psig, at intervals no greater than 24 months except for tests involving:

1.

Air locks.

4 2.

Penetrations using continuous leakage monitoring systems.

NORTH ANNA - UNIT 2 3/46-2 Amendment No. 92,94, M, !54,174

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ML20083M568

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