ML20247N436
| ML20247N436 | |
| Person / Time | |
|---|---|
| Site: | Surry  (DPR-32-A-126, DPR-37-A-126) |
| Issue date: | 05/18/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247N443 | List: |
| References | |
| NUDOCS 8906050355 | |
| Download: ML20247N436 (8) | |
Text
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E WASHINGTON, D. C. 20G55 49.....,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. DPR-32 1.
The Fuclear Regulatory Comission (the Commission) has found that:
A.
The application for amenenent by Virginia Electric and Power Company (the licensee) dated April 26, 1988, as supplemented July 18, 1988, complies with the stJndards and re Energy Act of 1954, as anended (the Act)quirenents of the Atomic 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 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 oefense 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 attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
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1 (B) Technical Specifications
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The Technical Specifications contained in Appendix A, as revised through Amendment No. 126., 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation Attachrent:
Changes to the Technical
- Specifications Date of Issuance: flay 18,1989
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.126
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License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 26, 1988, as supplemented July 18, 1988, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic 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 (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 conpliance 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 4
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 attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
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(B) Technical Specifications The Technical Specifications contained in Appendix A, as. revised through Amendment No.126, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION H rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II 1
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 18,1989
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages TS 1.0-5 TS 1.0-5 TS 3.8-1 TS 3.8-1 TS 4.4-3 TS 4.4-3 i
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-TS 1.0-5
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- operational activities provided that they. 'are'.under l,-
' administrative control' and are capable of being - closed immediately if required.
'2.
Blind flanges are installed where required.
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3.
The equipment access hatch is_ properly closed and sealed.
4.
At-least one door in the personnel airlock is properly closed
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and. sealed.
5.
All automatic containment. isolation valves are operable or are deactivated and secured in their closed position under administrative control.
6.
The - uncontrolled containment leakage satisfied Specification 4.4.
k I.
Reoortable Event A Reportable Event shall be any of those conditions specified in I
i Section 50.73 to 10 CFR Part 50.
Amendment flos.126 and 126 i
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W TS 3.8-1 4 -
9
'3.8 CONTAINMENT s
Acolicability Applies to the integrity and operating pressure of the reactor containment.-
Obiective To define the limiting operating status of the reactor containment for unit operation.
Specification A.
Containment Intearity and Ooeratina Pressure 1.
The containment integrity, as defined in TS Section 1.0, shall not. be violated unless the reactor is in the cold shutdown
. condition.*
l 2.
The reactor containment shall not be purged whenever the Reactor Coolant System temperature is above 200*F.
3.
The inside and outside isolation valves in the steam jet air ejector suction line shall be locked, sealed or otherwise secured closed whenever the Reactor Coolant System temperature is above 200*F.
4.
The Reactor Coolant System temperature and pressure must not exceed 350*F and 450 psig, respectively, unless the air partial pressure in the containment is at a value equal to, or below, that specified in TS Figure 3.8-1..
5.
The containment integrity shall.not be violated when the reactor vessel head is unbolted unless a shutdown margin greater than 5 percent ak/k is maintained.
- In the event of failure of the personnel airlock inner door seal to meet the leakage test acceptance criteria, the outer personnel airlock door may be opened for a period of time not to exceed fifteen minutes with an annual cumulative time not to exceed one hour per year to allow access for the repair and retest of the inner door.
Amendment Nos.126 and 126
TS 4.4-3 Basis The leak tightness testing of all liner welds was performed during con-struction by welding a structural steel test channel over each weld seam and performing soap bubble and halogen leak tests.
The containment is designed for a maximum pressure of 45 psig.
The con-tainment is maintained at a subatmospheric air partial pressure which varies between 9 psia and 11 psia depending upon the cooldown capability of the Engineered Safeguards and is not expected to rise above 39.2 psig for any postulated loss-of-coolant accident.
All loss-of-cool' ant accident evaluations have been based on an integrated containment leakage rate not to exceed 0.1% of containment voltme per 24 hr.
The above specification satisfies the conditions of 10 CFR 50.54(0) 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 airlocks are required to meet the restrictions on containment integrity and containment leak rate.
Surveillance testing of the airlock seals provides assurance C at 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 Inspec-tions 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
" Reactor Containment Leakage Testing for Water Cooled Power Reactors" Amendment Nos.126 and 126
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