ML20116F551
| ML20116F551 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/30/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116F554 | List: |
| References | |
| NUDOCS 9211100375 | |
| Download: ML20116F551 (5) | |
Text
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3 UNITED STATCS
/ i NUCLEAR REGULATORY COMMISSION
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VIRGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 MENOMENT TO FACILITY OPERATING LICENSE Amendment No.168 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated Octcber 26, 1992, 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 Commissior.'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 reauirements have been satisfied.
9211100375 921030 PDR ADOCK 05000338 P
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. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and-paragraph 2.0.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Spec.ifications The Technical Specifications contained in Appendices A and B, as j
revised through Amendment - No.168, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
@6 David
. Matthews, Acting Assistant Director for Region Il Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 30, 1992 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE NO, NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The re;ised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages Insert Pages 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 De
l TABLE 3 3 5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INmATING SIGNAL AND FUNCT10N RESPONSE TIME IN SECONDS Steam Flow in Two Stamm Lines-Hioh 6
Coincident wMh Stamm Line Pressure-Low a.
Safety injection (ECCS) s 13.0#/23.0##
b.
Reactor Trip (from SI) s 3.0 c.
Feedwater isolation s 8.0
- d. Containment isolation Phase 'A' s 18.0#/28.0##
- e. Auxiliary Feedwater Pumps s 60.0 i
f.
Essential Service Water System Not Appfcable
- 9. Steam Line isolation 8.0 7.
Containment Pressure-Hich-Hiah Containment Quench Spray s 60.0 a.
- b. Containment isolation-Phase 'B' s 60.0 8.
Containment Pressure-Intamediate Hich-Hiah a.
Staam Line isolation s 7.0 9.
Stamm Generator Water Level Low-Low a.
Auxiliary Feedwater Pumps s 60.0 10.
Station Blackout i
a.
Auxiliary Feedwater Pumps s 60.0
- 11. Main Feedwater Pumo Trb l
l a.
Auxiliary Feedwater Pumps s 60.0####
- 12. Steam Generator Water Level--Hiah-Hioh l
[-
a.
Turbine Trip-Reactor Trip s 2.5
- b. Foodwater Isolation s 11.0 l
NORTH ANNA-UNTT1 3/4 3-29
' Amendment No.168 l
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l TABLE 3 3 5 (Continued)
TABLE NOTATION Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish Si path and attainment of discharge pressure for centnfugal charging pumps, and Low Head Safety injection purnps.
Diesel generator siarting and sequence loading delays DQ1 included. Offsite power available.
Response time limt includes opening of valves to establish Si path and attainment of discharge pressure for centrdugal charging pumps.
Diesel generator starting and sequence loading delays included. Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centnfugal charging pumps.
The response times shown are based on the time from when the signal reaches the trip setting until the diesel generator is supplying the emergency bus.
Response time testing of the two relays in the auxiliary feedvater pump start circuit (Relays 3-CKT 1FWSA05 and 3-CKT-1FWSB05) due to a main feedwater pump trp is suspended for the duration of Cycle 9.
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1 NORTH ANNA-UNIT 1 3/4 3-30 Amendment No.168 l
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