ML20086E318

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Amends 200 & 200 to Licenses DPR-32 & DPR-37,respectively, Changing as Found Test Acceptance Criterion for Pressurizer Safety Valves from Plus or Minus 1% to Plus or Minus 3%
ML20086E318
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/29/1995
From: Matthews D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20086E321 List:
References
NUDOCS 9507110320
Download: ML20086E318 (6)


Text

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t UNITED STATES j

j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20066-0001

'+9.....,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. DPR-32 1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated January 24, 1995, complies with the 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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the her.lth 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.

4 9507110320 950629 PDR ADOCK 05000280 p

PDR

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i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:

(B)

Technical Soecifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No. 200, are hereby incorporated in the licer.se. The licensee shall operate the facility in accordance with the Technical Specifications.

l 3.

This license amendment is effective as of its date of issuance and shall l

be implemented within 30 days.

I FOR THE NUCLEAR REGULATORY COMMISSION g n_

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David B. Mat ews, Director F roject Directorate 11-1

['ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 29, 1995 1

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t UNITED STATES l_

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NUCLEAR REGULATORY COMMISSION l

t WASHINGTON, D.C. 205tpo01 L

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VIRGINIA ELECTRIC AND POWER COMPANY l

DOCKET NO. 50-281 l

SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 200 License No. DPR-37 f

1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated January 24, 1995, complies with the 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 1

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 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 changes to the Technical Specifications as indicated in the atta.hment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-37 is hereby amended to read as follows:

(B)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 200, 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 COMMISSION O

} W.

s m,

1 David B. Matthews, Director

[ Division of Reactor Projects - I/II ProhetDirectorateII-I Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications j

Date of Issuance: June 29, 1995

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 200 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 200 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Paae Insert Paae TS 3.1-3 TS 3.1-3 y - _, _ _.. - _..

.--e.

TS 3.1-3 a

i e.

Reactor power shall not exceed 50% of rated power with only two pumps in operation unless the overtemperature AT trip setpoints have been changed in accordance with Section 2.3, after which power shall not exceed 60% with the inactive loop stop valves 3

)

open and 65% with the inactive loop stop valves closed.

t f.

When all three pumps have been idle for > 15 minutes, the first pump shall not be started unless: (1) a bubble exists in the i

pressurizer or (2) the secondary water temperature of each steam generator is less than 50*F above each of the RCS cold leg temperatures.

2.

Steam Generator

)

A minimum of two steam generators in non-isolated loop shall be operable when the average reactor coolant temperature is greater than j

350 F.

i 3.

Pressurizer Safety Valves i

Three valves shall be operable wnen the head is on the reactor a.

4 vessel and the reactor coolant average temperature is greater than 350 F, the reactor is critical, or the Reactor Coolant System is not connected to the Residual Heat Removal System.

4 b.

Valve lift settings shall be maintained at 2485 psig ii percent

  • i The as-found tolerance shall be 13% and the as-left tolerance shall be a

l 11 %.

1

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I Amendment Nos.

200 4

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