ML20244A608
| ML20244A608 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/07/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20244A610 | List: |
| References | |
| NUDOCS 8904180097 | |
| Download: ML20244A608 (9) | |
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Io UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
'+,.....,o VIRGINIA ELECTRIC AND POWER COMPAllY 3
s DOCKET N0. 50-280 SURRY PCJER STATION, UNIT NO. 1 1
AMEN 0 MENT TO FACILITY OPERATING LICENSE I
Amendment No.124 License No. DPR l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated June 10, 1988, 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 Consnission; C.
There is reasonable assurance (1) tha'. the activit%s authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such act.ivities will be conducted in compliance with the Commission's regulations; l
D.
The issuance of this amendment will not be innnical to the comon l
defense and security or to the hea.lth and safety of the public; L
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-32 is hereby amended to read as follows-i l
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-2 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anendment No.124, 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.
I FOR THE NUCLEAR REGULATORY COMMISSION' l
l erbert H. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II 1
Office of Nuclear Reactor Regulation l
Attachment:
' l Changes to the Technical Specifications 1
Date of Issuance: April 7, 1989 4
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY GPERATING LICENSE l
Amendment No. 124 License No. DPR-37
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'1.-
The Nuclear Regulatory Comission!(the Commission) has found that:
A.
The application for amenoment by Virginia Electric and Power Coinpany (the IR:nsee) dated June 10,.198.8, complies with the standards and requirements o.f 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, i
the~ provisions of the Act, and the' rules and regulations of the Comission; j
C.
There is reasonable assurance (i) that the activities authorized' by this amendment can be conducted without endangering the health and safety of theLpublic, 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 defense and security or to the. hea,lth 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 Appendix A, as revised through Arendment No.124, 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 1
l'
,erbert H. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation j
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 7, 1989 l
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h' ATTACHMENT TO LICENSE A!!ENDMENT AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. DPR-32 i
i ANENDMENT N0.124 FACILITY OPERATING' LICENSE NO. DPR-37 DOCKET NOS'. 50-280 AND 50-281
. Revise Appendix A ds follows:
l Remove Pages Insert Pages
.f TS 3.7-26
.TS 3.7-2a TS 3.7-9b.
TS'3.7-9b
.TS 3.7-22 TS 3.7-22 TS-4.1-8a' TS'4.1-84 l
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.TS 3.7-2a 3.
The requirements of Specification 3.0.1 and 6.6.2 are not applicable.
F.
The accident monitoring. instrumentation 'for its associated operable components listed in TS Table 3.7-6 shall be, operable E
in accordance with the' following:
1.
With the number of operable accident monitoring instrumen-tation channels less than the total number of channels l
shown in TS Table 3.7-6, either restore the inoperable channel (s) to operable status within 7 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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j 2.
With the number of operable accident monitoring instrumen-tation' channels less than the minimum channels operable requirement of TS Table 3.7-6, either restore the inoper-able channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be-in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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i Amendment Nos. 124 and 124 l
TS 3'7-9b 3,
control room, The supply lines installed from the containment penetrations to the n
hydrogen. analyzers have Category 1 Class.IE heat. tracing applied..
The' heat tracing system receives the same transferable emergency f
s power as is provided. to the. containment hydrogen analyzers.
The heat. trace system is de-energized during normal system operation.
Upon receipt of a safety injection signal (Train A or Train B), the system is automatically started, after a preset time delay, to bring the piping process temperature to 250*F 10*F within 20 minutes.
1 Each heat trace ~ircuit is equipped with an RTD to provide c
individual circuit readout, over temperature alarm and' cycles the
.f circuit to maintain the process temperature via the solid state control modules.
The hydrogen analyzer heat trace system. is equipped with h'igh temperature, loss of D.C. power, loss of A.C. power, loss of control i
power and failure of automatic initiation alarms.
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Amendment Nos. 124 and 124 l
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TS 3.7 22 6
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Amendmenj: Nos.124 and 124
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