ML20076E168
| ML20076E168 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/08/1991 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076E170 | List: |
| References | |
| NUDOCS 9108160005 | |
| Download: ML20076E168 (8) | |
Text
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION I,. -\\
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WASHINoToN, D.c. 20b66 s s e
ylRGINIA ELECTRIC AND POWER COMPANY I
DOCKET NO. 50-280 SURRY POWER STATION UNIT NO. 1 2
AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 159 License No. OPR-32 1.
The Nuclear Regulatory Conmission (the Conmission) has found that:
1 A.
-The application for amendment by Virginia Electric and Power-l Company (the licen.ee) dated November 3,1989, as supplemented i
April 27,1990, ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission'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 Connission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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; 4
D.
The issuance of this amendment will not be inimical to the connon defense and security or to the he th and safety of the public; i
and-E.
The issuance of this amendment is in ccordance with 10 CFR Part 51 of the Cnnaission's regulations and all applicable requirements have been satisfied.
'2.
Accordingly, the -licer.se is amended by. changes to the Technical
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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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9108360005 910008 PDR ADOCK 05000200
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! 8 (D) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical i
Specifications.
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3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 0v I brbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of issuance: August 8, 1991 i
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,e UNITED STATES
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NUCLEAR REGULATORY COMMISSION 0,
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WASHINGTON, D C. 20666 g%
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION. UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING Q QtjSE S
Amendment No.158 i
License No. OPR-37
- 1..
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by. Virginia Electric and Power Company (the licensee) dated November 3, 1989, as supplemented April 27, 1990, complies with the standards and requirements of the Atomic Energy Act of 195
.as amended (the Act) and the Commission's rules and regulations se forth in 10 CFR Chapter It B.-
The facility will o>erate in conformity with the application, the provisions of t1e Act, and the reles and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment con be conducted without endangering the health and safety of the publ{c, and (ii) that such activities will be conducted in compliant.e 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.
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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2 (B) Technical Specifications The Technical Specifications contained in 'ppendix A, as revised through Amendment No.158, at e 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 C0!itilSS10N l0 v
Herbert N. Berkow, Director Project Directorate !!.2 Division of Reactor Projects - 1/l!
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 8, 1991 l
ATTACHMENT TO LICENSE AMENDMENT AMENPMENT NO. 159 FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT h0. 158 FACillTY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AliD 50-281 Revise Appendix A as follows:
Remove Page Insert Page TS 3.12-8 TS 3.12-8
e TS 3.12 8 l
t AT and Overtemperature AT trip settings shall be reduced by the equivalent of 2% power for every 1% quadrant to average power tilt.
C.
Inocerable Control Rods 1.
A control rod assembly shall be considered inoperable if the assembly cannot be moved by the drive mechanism or the assembly remains misaligned from its group step demand position by more than 3.24 steps during the " Thermal Soak" period, as defined in Section 3.12 E.1.b, or 112 steps otherwise during power operation. No tolerance limit is required in the shutdown modes, but a rod shall be considered inoperable if the rod position indicators do not verify rod movement upon demand. Additionally, a fulllength control rod shall be considered inoperable if its rod drop time is greater than 2.4 seconds to dashpot entry.
2.
With more than one inoperable control rod assembly, as defined in 3.12.C.1, determine within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that the SHUTDOWN MARGIN requirements of Specification 3.12.A.3.c are satisfied and be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
3.
If more than one control rod assembly in a given bank are out of I service because of a single failure external to the individual rod drive mechanism but remain trippable (i.e., programming circuitry), l the provisions of specifications 3.12.C.1 and 3.12.C.2 shall not apply. Either restore the affected assemblies to operable status in the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
4.
The provisions of Specifications 3.12.C.1 and'3.12.C.2 shall not apply during reactor physics tests in which the assemblies are intentionally misaligned.
5.
Power operation may contiriue with one rod inoperable provided that within one hour either:
a.
the rod is no longer inoperable 93 defined in Specification 3.12.C.1, or Amendment Hos 159 and 158
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