ML20082M869

From kanterella
Jump to navigation Jump to search
Amends 196 & 196 to Licenses DPR-32 & DPR-37,respectively, Revising Section 4.4.D of TS Permitting Approved Exemptions to Cilrt Frequency Requirements
ML20082M869
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/18/1995
From: Matthews D
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20082M873 List:
References
NUDOCS 9504240408
Download: ML20082M869 (6)


Text

,

pa ltf C t.

UNITED STATES NUCLEAR REGULATORY COMMISSION

!. E WASHINGTON, D.C. 20665-0001

%,...../

VIRGINIA ELECTRIC AND POWER COMPANY t

DOCKET NO. 50-280 t

SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.1%

License No. DPR-32 l

1.-

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

A.

The application for amendment by Virginia Electric and Power l

Company (the licensee) dated February 14, 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; i

B.

The facility will operate in conformity with the application, the l

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

Commission; C.

There is reasonable assurance (1) that the aciivities 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, 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 E.

The issuance of this amendment is in accordance with 10 CFR Part i

i 51 of the Commission's regulations and all applicable requirements I

have been satisfied.

i I

l 9504240408 950418 PDR ADOCK 05000280 P

PDR,

i

1 j

1 J 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 Operating License No. DPR-32 is hereby amended to read as follows:

(B)

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

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

j l

3.

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

1 FOR THE NUCLEAR REGULATORY COMISSION i

t,'

'ct f i

David B. Matthews, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

i Changes to the Technical Specifications Date of Issuance: April 18, 1995 l

b

'Op'.

UNITED STATES y e-j j

NUCLEAR REGULATORY COMMISSION l

%,*****/.

WASHINGTON, D.C. 20646 0001 1

l VIRGINIA' ELECTRIC AND POWER COMPANY j

DOCKET NO. 50-281 SURRY POWER STATION. UNIT No. 2 ANENDNENT TO FACILITY OPERATING LICENSE Amendment No.1%

License No. DPR-37 l

1.

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

i A.

The application for amendment by Virginia. Electric and Power Company (the licensee) dated February 14, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as i

amended (the Act) and the Commission's rules and regulations set

[

forth in 10 CFR Chapter I; i

B.

The facility will operate in confomity with the application, the

}

provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized i

by this amendment can be conducted without endangering the health i

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

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 i

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.

l r

._m,

.m.,,,

L 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-37 is hereby amended to read as follows:

(B)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 1%, 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 COPMISSION 4

David B. Natthews, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 18, 1995 l

f i

if ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

1%

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

1%

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

Remove Pace Insert Paae TS 4.4-2 TS 4.4-2 e

m i-

i'

~-

TS 4.4-2 b.

The leakage rate test will be performed at a pressure of at least 45.0 psig.

i c.

The measured ledage rate Lam shall not exceed 75% of the design basis accident leakage rate (La) 0.1 weight percent -

per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure Pa.

~

2.

Type B and C tests will be performed at a pressure of at least 45.0 psig in accordance with the provisions of Appendix J, Section Ill.B and C. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after use of the personnel airlock, the seals will be tested to at least 45 psig to verify that they are properly sealed.

C.

Acceptance Criteria Type A, B, and C tests will be considered to be satisfactory if the acceptance criteria delineated in Appendix J, Secilons Ill.A.5(b), Ill.B.3, and Ill.C.3 are met.

D.

Retest Schedule The retest schedules for Type A, B, and C tests will be in accordance with Section Ill.D Appendix J, except as modified by NRC-approved exemptions.

E.

Inspection and Reporting of Tests inspection and reporting of tests will be in accordance with Section V of Appendix J.

F.

The provisions of Specification 4.0.2 are not applicable.

Basis The leak tightness testing of all liner welds was performed during construction by welding a structural steel test channel over eech weld seam and performing soap bubble and halogen leak tests.

Amendment Nos.195 and 196

...