ML20045H789
| ML20045H789 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/01/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045H790 | List: |
| References | |
| NUDOCS 9307210271 | |
| Download: ML20045H789 (7) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.179 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 November 14, 1990, 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 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; 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.
1 9307210271 930701 PDR ADOCK 05000280 P
. 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. 179, 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
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He bert N. Berk w, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July.1, 1993 L
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281.
SURRY POWER STATION. UNIT N0.-2 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.179 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 November 14, 1990,' 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 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; 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.
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 Cserating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.179, 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
,/
H rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 1, 1993
7..
s ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
179 TO FACILITY OPERATING LICENSE NO. DPR-32
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AMENDMENT NO.
179 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 4.4-2 TS 4.4-2 TS 4.4-3 TS 4.4-3 l
1
TS 4.4-2 b.
The leakage rate test will be performed at a pressure of at least 45.0 psig.
c.
The measured leakage rate Lam shall not exceed 75% of the design basis accident leakage rate (La) 0.1 weight l 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 Sections Ill.A.5(b), Ill.B.3, and lil.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 of Appendix J.
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 each weld seam and performing soap bubble and halogen leak tests.
Amendment Nos.179 and 179
TS 4.4-3 The containment is designed for a maximum pressure of 45 psig.
The containment is maintained at a subatmospheric air partial pressure which varies between 9 p:sia and 11 psia depending upon the cooldown capability of the Engineered Safeguards and will not rise above 45 psig for any postulated loss-l of-coolant accident.
The initial test pressure for the Type A test is 47.0 psig to allow for containment expansion and equalization. A review was performed to determine the effects of pressurizing containment above its design pressure of 45.0 psig. This review was based on the original containment test at 52 psig. During that test, the calculated stresses were found to be well within the allowable yleid strength of the structural reinforcing bars, therefore performance of the Type A test at 47 psig will have no detrimental effect on the containment structure.
All loss-of-coolant accident evaluations have been based on an integrated containment leakage rate not to exceed 0.1% of containment volume per 24 hr.
The above specification satisfies the conditions of 10 CFR 50.54(o) which stated that primary reactor containments shall meet the containment leakage test requirements set forth in Appendix J.
The limitations on closure and leak rate for the containment airiccks are required to meet the restrictions on containment integrity and containment leak rate. Surveillance testing of the airlock seals provides assurance that the overall airlock leakage will not become excessive due to seal damage during the intervals between airlock leakage tests.
References
)
FSAR Section 5.4 Design Evaluation of Containment Tests and inspections of Containment FSAR Section 7.5.1 Design Bases of Engineered Safeguards Instrumentation FSAR Section 14.5 Loss of Coolant Accident 10 CFR 50 Appendix J
" Primary Reactor Containment Leakage Testing for Water l Cooled Power Reactors" Amendment Nos.179 and 179
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