ML20107J998
| ML20107J998 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/18/1996 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20107K003 | List: |
| References | |
| NUDOCS 9604250370 | |
| Download: ML20107J998 (8) | |
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-4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 f
.....p VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-280 SURRY POWER STATION. UNIT NO 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 208 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 20, 1995 as supplemented March 14, 1996, 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; l
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B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the Commission; 1
C.
There is reasonable assurance (1) 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; l
D.
The issuance of this amendment will not be inimical to the common
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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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9604250370 960418 DR ADOCK 0500 0
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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 Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications j
The Technical Specifications contained in Appendix A, as revised I
through Amendment No. 208, are hereby incorporated in the i,
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 j
Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18,1996 l
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31 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 l
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 208 License No. DFR-37 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 November 20, 1995 as supplemented i
March 14, 1996, 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 Ccamission; l
l 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 i
defense and security or to the health and safety of the public; l
and l
E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Commission's regulations and all applicable requirements j
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 Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised l
through Amendment No. 208, are hereby incorporated in the t
license. The licensee shall operate the facility in accordance with the Technical Specifications.
j 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
)
FOR THE NUCLEAR REGULAT0,RY COMMISSION P
Eugene V. Imbro, Director Project Directorate 12-1 Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 18,1996 l
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l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 208 TO FACILITY OPERATING LICENSE N0 DPR-32 AMENDMENT NO. 208 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 4.4-1 TS 4.4-1 i
TS 4.4-2 TS 4.4-2 TS 4.4-3 TS 6.6-11 TS 6.6-11 TS 6.6-12 f
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Ni TS 4.4-1 4.4 CONTAINMENT TESTS Applicability Applies to containment leakage testing.
Objective l
l To assure that leakage of the 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 Containment Leakage Testing for Water Cooled Power Reactors."
B. Containment Leakage Rate Testing Requirements
- 1. The containment and containment penetrations leakage rate shall be demonstrated by performing leakage rate testing as required by 10 CFR 50 Appendix J, Option B, as modified by approved exemptions, and in accordance with the guidelines contained in Regulatory Guide 1.163, dated September,1995. Leakage rate
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acceptance criteria are as follows:
An overall integrated leakage rate ofless than or equal to La,0.1 percent by a.
weight of containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at calculated peak pressure (Pa).
b.
A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C testing when pressurized to Pa.
Prior to entering an operating condition where containment integrity is required the as-left Type A leakage rate shall not exceed 0.75 La and the combined leakage rate i
of all penetrations subject to Type B and C testing shall not exceed 0.6 La.
- 2. 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.
i Amendment Nos. 208 and 208
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4 TS 4.4 2 I
The containment is designed for a maximum pressure of 45 psig. The containment is maintained at a subatmospheric air partial pressure consistent with TS Figure 3.8-1 depending upon the cooldown capability of the Engineered Safeguards and will not rise above 45 psig for any postulated loss-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 4
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 yield 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 i
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 te:t requirements set forth in Appendix J.
The limitations on closure and leak rate for the containment airlocks 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 UFSAR Section 5.4 Design Evaluation of Containment Tests and Inspections of Containment UFSAR Section 7.5.1 Design Bases of Engineered Safeguards Instrumentation UFSAR Section 14.5 Loss of Coolant Accident 10 CFR 50 Appendix J
" Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors" Amendment Nos. 208 and 208
1 TS p.6-il I
C. Special Reoorts In the event that the Reactor Vessel Overpressure Mitigating System is used to mitigate a RCS pressure transient, submit a Special Report to the Commission within 30 days.
l The report shall describe the circumstances initiating the transient, the effect of the l
l PORVs or the administrative controls on the transient and any corrective action l
necessary to prevent recurrence.
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l EQOTNOTES 1.
A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
l 2.
This tabulation supplements the requirements of Section 20.2206 of 10 CFR Part 20.
3.
A single submittal may be made for a multi-unit station. The submittal should combine i
those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
Amendment Nos. 208 and 208