ML19332C160

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Amends 135 to Licenses DPR-32 & DPR-37,respectively,changing Tech Spec 3.1.A.3.c Re Pressurizer Safety Valve Setpoint Tolerance
ML19332C160
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/16/1989
From: Lainas C
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332C161 List:
References
NUDOCS 8911220375
Download: ML19332C160 (6)


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UN1TED STATES g

NUCLEAR REGULATORY COMMISSION 0

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ASHINGTON D. C. 20665

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VIRGIN! A ELECTRIC AhD POWER COMPANY i

00CKET NO. 50-280

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SURRY PCl,'EP STATION, UNIT NO.1 APENLMENT 10 FACILITY OPEP.ATING LICENSE Amendment No.135 License No. CPR-32 1.

The Nuclear Regulatory Consnission (the Commission) has icund thst:

A.

The application for amendment by Virginia Electric and Power Certpany (the licensee) dated Noventer 10, 1989, ccmplies with the standards and requirerrents of the Atcmic Energy Act of 1954, as amended (the Act) anc the Conunission's rules anc regulaticos set forth in 10 CFR Chapter I; L.

The facility will operate in ccnformity with the application, the provisions of the Act, ano the rules and regulations uf the Ccarission; C.

There is :casonable assurance (1) that the activities authorized by this amendnent can be concucted without endangering the he61th and safety of the public, and (ii) that such activities will be conducted in compliarce with the Comission's regulations; D.

The issuance of this amendment will nct be inimicci to the common oefense'and security or to the health and safety of the public; and E.

The issuance of this amendrrent is in accordance with 10 CFR Part-51 of the Cconission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operatine License

- ho. DPR-32 is hereby anended to reed as follows:

8911220375 891116 PDR ADOCK 05000280 P

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. 1 (B) Technical Specifications

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The Technical Specifications contained in Appendix A, as revised through Arendment. No.135., are hereby incorporated in the license.

The licensee shall i

operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Ik' ('s.,)/.-

/Cus C. Lainas, Assistant Director for Region 11 Reactor Division of Reactor Projects - 1/II J

Office of Nuclear Reactor Regulation Attechment:

Changes to the Technical Specifications Date of Issudnce:

November 16, 1989 i

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= NUCLEAR REGULATOR.Y COMMI5svN N'

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-VIRGINIA ELECTRIC AND PCWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NC. 2 AMENDMENT TO FACILITY CPERATING LICENSE trendment No.135 License No. DPR-37

'1.

' The Nuclear' Regulatory Consission (the Comission) has found tba:

g,W A.

The application for.amencment by Virginia Electric and Power Company (the licenste) dated Ncvember 10, 1989, complies with: the standards and requirements of the Atcsic Energy Act of 1954, as amended (the Act) and the Conunission's rules and regulations set forth'in 10 CFR Chapter I; E

B.

The f acility will operate in conformity with the application, the prov!sions of the Act, ano the rules and reguistions of the Consnission; -

C.

There is reasonable assurance (i) that the activittu authorir.ed

.by this.anendment can be conducted without endangering the health and safety of the public,.and (ii) that such activities will be concucted _in cocpliance with the Comn:ission's regulations; 3

The' issuance of this amendment will not be inimical: to the common I

D.

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

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J E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license snendment, and parograph 3.B of Facility Operating License H

No. OPR-37 is hereby amended to read as follows:

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(B) Technical Specifications 4

The Technical Specifications contairied in Appendix A.

-as revised through Amendnent No. 135, are hereby incorporated in the license.

The licensee shall 4

operate the facility in accordance with the. Technical Specifications.

I 3.

T51s license arnendment is effective as of the date of its issuance.

FOR ThE HUCLEAR REGULATORY COMMISSION h lff: s

'lu s C.. Lainas, Assistant Director for Region ll Rectors Division of Reactor Projects - I/II Office of Nuclear Reactor ReSulation Attachtr.ent:

Cher.ges.to the Technical Specifications Cate of Issuance: NoverrLer 16, 1989 4

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o ATTACHMENT TO LICENSE AMENDMENT

AMENDMENT NO. -135 FACILITY OPERATING LICENSE NO. DPR-32

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AMENDMENT NO.135 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281-Revise Apper. dix A as follows:

replace the following page of Appendix "A" l

1echnical Specifications with the erclosed page.

The revised page:is identified

' by amendment number.and contains c vertical line indicating the area cf change.

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Remove Fage-Insert-Page 3.1-4 3.1-4 i

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Three valves shall be operable when the reactor coolant average temperature ~is greater than 350'F,-the reactor is entical, or the R? actor Coolant Spstem is not connected to the Residual Heat Remo' val System.

Valve lift settings shali be maintained at 2485 psig N percent.'

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4 Reactor Coolant Loops r

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Loop stop valves shall not be closed in more than.one loop unless the -

Reactor Coolant System is connected to the Residual Heat lemoval-J System arid the Res; dual Heat Removal System is operable.

5.

Pressurizer The reactor shall be maintained suberitical by at least 1% until the a.

steam bubble 's established and the necessary sprays and at ! east 125 KW cf heaters are operable.

With the pressunzer inoperaole due to inoperaole pressunzer c.

heaters, restore the inoperaole neaters within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at q

least hot shutdown wdhin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the reactor coolant system

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temperature and pressure less than 350*F and 450' osig, respectively, within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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For the remainder of Cycle 10 operation for both units the valve lift I

5 settings shall be maintained at 2485 osig L percent.

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Amendment Nos. 135 & 135 i

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