ML20207L786
| ML20207L786 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/12/1999 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207L788 | List: |
| References | |
| NUDOCS 9903180275 | |
| Download: ML20207L786 (6) | |
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j NUCLEAR REGULATORY COMMISSION C-WASHINGTON. D.C. 2055MXm1 p
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ylRGINIA ELECTRIC AND POWER COMPANY POCKET NO. 50-280 SURRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 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 September 24,1998, 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.
9903180275 990312 PDR ADOCK 05000290 Y
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I 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. 219, 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
rt erkow, Director i
P oject Directorate 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the Technical Specifications Date of issuance:
March 12,1999
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 l
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l VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281
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i SURRY POWER STATION. UNIT NO. 2 AMENDMENT TO FACl(ITY OPERATING LICENSE 1
l Amendment No. 219 l
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 j
licensee) dated September 24,1998, 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 j
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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2-2.
Accordingly, the license ic amended by changes to the Technical Specifications as indicated in the attachment to W.M license amendment, and paragraph 3.8 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 through Amendment No. 219, 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 bert N Ber ow, Director.
Project Directorate 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 12,1999 I
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. ATTACHMENT TO LICENSE AMENDMENT NO. ' 219 TO FACILITY OPERATING LICENSE NO. DPR-32 LICENSE AMENDMENT NO 219 TO FACILITY OPERATING LICENSE NO. DPR DOCKET NOS. 50-280 AND 50-26]
Revise Appendix A as follows:
~ Remove Pace Insert Paae TS 4.1-8a TS 4.1-8a i
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TABLE 4.1-1(Continued)
MINIMUM FREOUENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS -
Channel Description '
Check Calibrate' Test Remarks
~
-32.s Auxiliary Feedwater 1
- a. Steam Generator Water Level Low-Low S
- R M(1) -
1)De auto start of the turbine dnven pump is not included in the monthly test, but is tested within 30 days prior to each startup.
l
.t
- b. RCP Undervoltage -
S R.
N.A.(l)
- 1) The actuation logic and relays are tested within 30 da'ys prior to each startup.
-i.
- c. S.I.
(All Safety injection surveillance requirements)
- d. Station Blackout -
N.A.
R N.A.
)
- e. Main Feedwater Pump Trip N.A.
N.A.
R
[
- 33. Loss of Power
- a. 4.16 KV Emergency Bus Undervoltage N.A.
R M
(Loss of Voltage) i
- b. 4.16 KV Emergency Bus Undervoltage N.A.
R M
(Degraded Voltage) p
- 34. Deleted
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- 35. Manual ReactorTrip N.A.
N.A.
R De test shall independently verify the operability of the j
.g undervoltage and shunt trip attachments for the manual
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reactor trip function. The test shall also verify the operability of the bypass breaker trip circuit.
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- 2: 36. ReactorTrip Bypass Breaker N.A.
N.A.
M(1 ),-
- 1) Remote manual undervoltage trip immediately aftr r R(2) placing the bypass breaker into service, but prior io commencing reactor trip system testing or required N
maintenance.
-4 G
- 2) Automatic undervoltage trip.
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- 37. Safety injection input to RPS N.A.
N.A.
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- 38. Reactor Coolant Pump Breaker Position Trip
'N.A.
N.A.:
R r
.