ML19345B169

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Amend 1 to License NPF-7,changing One Tech Spec Re Leak Testing of Certain Pressure Isolation Valves Prior to Entering Mode 2 Rather than Mode 4
ML19345B169
Person / Time
Site: North Anna Dominion icon.png
Issue date: 11/17/1980
From: Youngblood B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19345B170 List:
References
NUDOCS 8011260251
Download: ML19345B169 (4)


Text

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o, UNITED STATES

[3),- %n ' i NUCLEAR REGULATORY COMMISSION c

WASHINGTON, D. C. 20555

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v VIRGINIA ELECTRIC AND POWER C0f/PANY

,00CKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 Af'ENDMENT TO FACILITY CPERAflNG LICENSE License No. NPF-7 Amendment tu. 1 1.

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

A.

The application for amendment to the Virginia Electric and Power Company (licensee), dated November 4,1980, for the North Anna Power Station, Unit No. 2 complies with the standards and requirements of the Atcmic Energy Act of 1954, as amended (the Act) and the Comission's regulations :et forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the license, as amended,

- the provisions of the Act and the regulations of the Comission, C.

There is reasonable assurance (i) that the activities authorized by this amendmc.t 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 common 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 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changing the following Technical Specification contained in Facility Operating License f!PF-7 to read:

4.4.6.2.2 b.

Prior to entering Mode 2 whenever the plant has been in COLD SHUT DOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.

80112e0951

i f-2.C.(2) Technical Specifications i

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' The Technical Specifications contained in Appendix A and B, as revised through Amendment No. 1, are hereby incorporated into the license.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLE,AR REGULATORY COMMISSION m

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B. J. Youngblood,' Chief l

Licensing Branch No. 1 Division of Licensing Attach e.it:

Page 3/4 4-18 to Technical Specification Appendix A Date of Issuance: ggy y 7 gg i

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ATTACHMENT TO LICENSE AMEN 0 MENT N0. 1 FACILITY OPERATING LICENSE N0. NPF-7 DOCKET N0. 50-339 Change the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by the Amendment Number and contains vertical lines indicating the area of change.

Page 3/4 4-18

P REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring 'the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c.

Measurement of the CONTROLLED LEAKAGC to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 + 20 psi at least once per 31 days with the modulating valve fulTy open.g The provisions of Specification 4.0.4 are not applicable for entry into MODE 4.

d.

Performance of a Reactor Coolant System water inventory balance at least once per_72 hours.

e.

Monitoring the reactor head flange leakoff temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

At least once per 18 months.

b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in-the previous 9 months.

c.

Prior to returning the valve to s2rvice following maintenance, repair or replacement work on tha valve.

d.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valvre actuation due to automatic or manual l

action or flow through the valve.

Amendment No. 1 NORTH ANNA - UNIT 2 3/4 4-18 i

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