ML20004D158
| ML20004D158 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/19/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004D159 | List: |
| References | |
| NUDOCS 8106080492 | |
| Download: ML20004D158 (8) | |
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$1 UNITED STATES ls
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VIRGINIA ELECTRIC AND' POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION,' UNIT NO. 'i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6R License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 22, 1978, as supplemented January 9 and September 24, 1979, 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; 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 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 Commission!s regulations and all applicable requirements i
have been satisfied.
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2.
Accordingly, the lieerse.is amanded by changes the Technicti Spec 1rications as indicateo in the attachment to this license amendment, and paragraph 3.3 of Facility Operating License No. DPR-32 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, are hereby incorporated in the license. The licensse shall operate ths facility in-accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
F THE NUQLEA CGULATORY COMMISSION I
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/5teven A. Narga, Chi f Operating Reactors B nch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 19,1981 l
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WASHINGTON, D. C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT'NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 22, 1978, as supplemented January 9 and September 24, 1979, 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; 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 Connission'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 Commission's regulations and all applicable requirements have been satisfied.
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2-2.
Accordingly, the license is enended 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-37 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, 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 the date of issuance.
THE N CLE R REGULATORY COMMISSION q@tevenn.u 4'Vatga,; hief gut
/ Operating Reacto Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 19, 1981 4
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hTThCHMENT70'LICENSI'-h"ENDMENTS AMEND" Erit' r;0. 68TO FACILITY 0?ERATING LICENSE NO. DPR-32 AMENDMENT NO. 68TO NACIliTY OPERATIllG LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 4.4-1
- 4. 4-1 4.4-2 4.4-2 4.4-3 4.4-3 1-W e-
TS 4.4-1 4.4 ' CONTAINMENT TESTS Applicability Applies to containment leakage testing.
Objective To assure that leakage of 9.3 primary reactor containment and associated systems is held within allowable leakage rate limits; and to assure that periodic surveillance is performed to assure proper maintenance and leak repair during the service life of the containment.
Specification' A.
Periodic and post-operational integrated leakage rate tests of the containment shall be performed in accordance with the requirements of 10 CFR 50, Appendix J, " Reactor Contsinment Leakage Testing For Water Cooled Power Reactors."
B.
Testing Requirements 1.
Type A tests will be performed in accordance with the peak pressure test program as defined in paragraph III, of, Appendix J.
1 The absolute method of leakage rate testing will be used a.
as the method for performing the test. The make-up air method for verification of leakage test accuracy will t
l be used. Testing to be done in accordance with the guide-lines in ANSI N45.4-1972.
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Amendment Nos. 68 & 68
TS 4.4-2
- b. The leakage rate test will be performed at a pressurs.of at least 39.2 psig (P ).
- c. The measured leakage rate L,,shall not exceed 75% of the design basis accident leakage rate (La) of 0.1 weight percent per f
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 I
39.2 psig (Pa) in accordance with the provisions of Appendix J.
Section III. B. and C.
Also, 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 at least at the pesk calculated accident pressure to verify that they are properly 1
s ealed.
C.
Acceptance Criteria Type A, B and C tests will be considered to be satisfactory if the f
acceptance criteria delineated in Appendix J, Sections III.A.5(b)
III.B.3., and III.C.3 are met.
i D.
Retest Schedule The retest schedules for Type A, B, and C tests will be in accordance with Section III.D of Appendix J.
E.
Inspection and Reporting of Tests Inspection and reporting of tests will be in accordan'ce with Section V of Appendix J.
Amendment Nos. 68 & 68
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TS 4.4-3
. Basis The leaktightness testing of all liner velds was performed during construction by welding a structural steel test channel over each weld seam and performing soap bubble and halogen leak tests.
The containment The containment is designed for a maximum pressure of 45 psig.
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is maintained at a,subatmospheric air partial pressure which varies betwe'en 9 psia and 11 psia depending upon the cooldown capability of the Engineered Saf eguards and is not expected to rise above 39.2 psig for any postulated l
loss-of-coolant accident.
All loss-of-coolant accident evaluations have been based on an integrated containment leakage rate not to exceed 0.1 percent tf containment volume per 24 hr.
The above specification satisfies the conditions of 10 CFR 50.54(0) which states that primary reactor contain= cats shall neet the containment leakage test requirements set forth in Appendix J.
References FSAR Section 5.4 Design Evaluation of Containment Tests and Inspections of Containment FSAR Sections 7.5.1 Design Bases of Engineered Saf eguards Instrumentation FSAR Section 14.5 Loss-of-Coolant Accident
" Reactor Containment Leakage Testing for Nater-10 CFR 50 Appendix J Cooled Power Reactors,"
i Amendment Nos. 68 & 6e 1
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