ML20090D579
| ML20090D579 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/03/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20090D582 | List: |
| References | |
| NUDOCS 9203060294 | |
| Download: ML20090D579 (12) | |
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VIRGINTA ELECTRIC Af40 POWER COMPANY QLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. NPF-4 1. The Nuclear Regulatory Commission (the Commission) has iuund that: A. The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated January 8, 1992, as supplemented by letters dated January 31, February 10 and February 25, 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 1: 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. 9203060294 920303 PDR ADOCK 05000338 p PDR
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.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows: (2) Technical Specificatio.nl The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 154, are hereby incorporated in the license. VEPC0 shall operate the f acility in accordance with the Technical Specifications. 3. This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION h N ~ Hertert N. Berko, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Of fice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 3, 1992
i ) i ATTACHMENT TO LICENSE AMENDMENT NO. 154 I TO FACILITY OPERATING LICDM NO. NPF-4 l DOCKET NO. 50-333 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages es indicated. The revised 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 Paaes Insert Paoqi 2-1 2-1 2-2a 2-6 2-6 2-9 2-9 2-10 2-10 3/4 2-15 3/4 2-15 i-f i I-I .. L.. .......-.,,m.._..,.....- ,_,,.,--_..,.._,,._..,_.-._..,,,.7,..
t 2.0 SAFETY UMITS AND UMITING SAFETY SYSTEM SETTINGS 11 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits shown in Figures 2.11* for 3 loop l operation and 2.12 and 2.13 for 2 loop operation. APPLICABILtTY: MODES 1 and 2. t ACTION: Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, b6 in HOT STANDBY within 1 hour. REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig. APPLICABttlTY: MODES 1,2. 3. 4 and 5. ACT!ON: MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour, t MODES 3. 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig reduce the Reactor Coolant System pressure to within its limit within 5 minutes. l _For._ the period of operation until steam generator replacement, the combination _of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (Tavg) shall not exceed the limits shown in Figure 2.11a. NORTH ANNA UNIT 1 2-1 Arnendment No.154 i l - - ~ ,a,,_, .., ~ ~, - - .,w- ,n r. ,--wr,--nc., r .. - - ~ ~. - -.. .--a~-- -,,, -,, ~. - - .r------~~
Nominal 7,yg= 586.8'T Nerinel RCS flev = 289200 CPM 660 655 2400 psia 658 "'I' 2250 psia 540 $5! E50 2000 poia 'N 625 $523 [ $15 1860 psia ~ Ele - 525 688 - 595 < 5 98 585 188 475 8. .I .2 .5 4 .5 .s 7 .3 ,q 3, 3,3 3,; P0trC# tfeoctton or nomineei Figure 2.1 1 REACTOR CORE SATETY LIMIT % FOR TEREE LOOP OPERAT: ON NORTH ANNA - UNIT 1 22 Amendment flo, 46, $f, 84
Nominal Tavg - 586.8'F Nominal RCS Sow - 268,500 GPM 680 660 psia 640 " O psia C h620 Psia 4-t- psia -600 580 560 0 0.2 0.4 0.6 0.8 1 1.2 1.4 POWER (fraction of nominal) Figure 2.1 1a REACTOR CORE SAFETY UMITS FOR THREE LOOP OPERATION FOR THE PEROD OF OPERATICN UNTil STEAM GENERATOR REPLACEMENT NORTH ANNA UNIT 1 2 2a Amendment No. 154 i.
SAFETY LI:41TS AND LIMITlflG SAFETY SYSTEM SETTilG5 12. 2 LIMITING SAFETY SYSTEM SETTINGS EACTOR TRIP SYSTEi4 INSTRUMENTATION SETPOINTS 2.2.1 The reactor trip system instrumentation setpoints shall be set consistent with tne Trip Setpoint values shown in Table 2.2-1. APPLICABILITY: As shown for each channel in Table 3.3-1. ACTION: With a reactor trip system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, E declare the channel inoperable and apply the applicable ACTION state-a ment requirement of Specification 3.3.1.1 until the channel is restored W to OPERABLE status with its trip setpoint adjusted consistent t:th the Trip Setpoint value. T l NORTH ANNA - UNIT 1 2-5
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M - - h-p TABLE 3 2-1 Z DNB PARAMETERS 9 LIM'TS g 2 Loops in Operation 2 Loops in Operation ** 3 Loops in & Loop Stop & Isolated Loop C PARAMETER Ooeration Valves Onen Stoo Vahes Ckred 24 s 591*F Reactor Coolant System Tavg Pressurizer Pressure 2 2205 psig
- Reactor Coolant System 2 284,000 gpm * *
- l Total Flow Rate Eda P,J G.
5" a St o 3 l Limit not apphcable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute g or a THERMAL POWER step increase in es,ess of 10% RATED THERMAL POWER.
- Values dependent on NRC approval of ECCS evaluation for these mnditions.
E The value for the minimum allowable Reactor Coolant System Total Flow Rate is reduced to 268,500 gpm until steam g generator replacement. ~ s l "y
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