ML20065S031
| ML20065S031 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/04/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065S034 | List: |
| References | |
| NUDOCS 8210290416 | |
| Download: ML20065S031 (9) | |
Text
{{#Wiki_filter:e =q l 1 /' gee. jo, UNITED STATES NUCLEAR REGULATORY COMMISSION e ,,( ", v/ j wAsMNGTQN. D. C. 205$5 ~ k.'.';'.. / e VIRGINIAELECTRICANDPOWERCOMPArg l DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 [ License No. NPF 4 1. The Nuclear Regulatory Commission (the Ccmission) has found that: A. The application for amendment by Virginia Electric and Power Company (the licensee) dated June 8, 1982, complies with the standards and requirements of the Atomic Energy Ac1: 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 applications, the provisions of the Act, and the rules and regulations of e I the Commission; 1 C. There is reasonable assurance (i) that the activities authorized by this amer.dment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission'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. ISSIGFAT17) O'4TGIIIA C tified Bf 8 "a' e i L 8210290416 821004 l PDR ADOCK 05000338 P PDR l - - m. ,. m - - ~, ~. - n. - -. - - - a
- -. n. n 2-2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the. license. The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license enendment is effective as of the date of its issuance. l FOR THE NUCLEAR REGULATORY COMMISSION '-&L Robert A. Clark, Chief. j Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical i Specifications Date of Issuance: October 4, 1982 i I f w=w 4e se e ee e e.we k T's -e4 O E m
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 42 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 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. Pages 2-8 2-9 2-10 3/4 2-15
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-.. ~ - 7 I TABLE 2.2-1 (Continued)_ 8 g REACTOR TRIP SYSTEt1 INSTRUMENTATION TRIP SETPOINTS R FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E J-
- 13. Steam Generator Water
> 18% of narrow range instrument > 17% of narrow range instrument l 5 Level--Low-Low span-each steam generator span-each steam generator h
- 14. Steam /Feedwater Flow
< 40% of full steam flow at < 42.5% of full steam flow at i Mismatch and Low Steam -RATED THERMAL POWER coincident TiATED THERMAL POWER coincident ( Generator Water Level with steam generator water level with steam generator water level > 25% of narrow range instru- > 24% of narrow range instru-5 ment span--each steam generator ment span--each steam generator 9 g
- 15. Undervoltage-Reactor
> 2905 volts-each bus > 2870 volts-each bus l g Coolant Pump Busses
- 16. Underfrequency-Reactor
> 56.1 Hz - each bus f 2, Coolant Pump Busses > 56.0 Hz - each bus m
- 17. Turbine Trip A.
Low Trip System > 45 psig > 40 psig Pressure B. Turbine Stop Valve > 1% open > 0% open Closure &L
- 18. Safety Injection Input Not Applicable Not Applicable f
from ESF ? N
- 19. Reactor Coolant Pump "ot Applicable Not Applicable i
Breaker Position Trip i ~n 4 G s t D
TABLE 2.2-1 (Continued) 2o h REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS fl0TATION (Continued) ? C g Operation with 3 Loops Operation with 2 Loops Operation with 2 Loops f q (no loops isolated)* (1 loop isolated)* ( ) l ~ ( ) K) 1.113 K K = = = j j I ) l f( I ) K K 0.0132 K = 2 2 2 l K ( ) K l 3 3 3 I ) 0.000628 K = = D p and fi (AI) is a function of the indicated difference between top and bottom detectors a 4 of the power-range nuclear ion chambers; with gains to be selected based on measured g instrument response during plant startup tests such that: i -q between - 35 percent and + 7 percent, f (AI) = 0 l (1) forq$q arepercentRATEDTHERMALPOWERinlhetopandbottom halves of' Nnd qhre respectively, and qt + 9 (wher the c is total THERMAL POWER in b percent of RATED THERMAL POWER). (ii) for each percent that the magnitude of (q -q exceeds - 35 percent. 'the AT trip setpoint shall be automaticalfy rebu)ced by 1.21 percent of its value at RATED Ti!ERMAL P0HER. E F (iii) for each percent that the magnitude of (q -q exceeds + 7 percent, the AT trip setpoint shall be automaticalky rebu)ced by 1.09 percent of j ll g its value at RATED THERMAL POWER. 5 Values dependent on NRC approval of ECCS evaluation for these operating conditions. am s C
f-I c g TABLE 2.2-1 (Continued) z REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS e Eg NOTATION B NOTE 1: Overtemperature AT 1 AT [K -K 1 (T-T')+K (P-P')-f (AI)] + H g j 2 3 j ,1 + t b 2-where: AT Indicated AT at RATED THERMAL POWER = g 1 i T Average temperature, "F = 4 T: Indicated T at RATED THERMAL POWER.1 582.8'F = avg P Pressurizer pressure, psig = 2235 psig (indicated RCS nominal operating pressure) P' = m 1+rjS j, 3= The function generated by the lead-lag controller for T dynamic compensation avg Tj & T2 = Time constants utilized in the lead-lag controller for Tavg 'l = 25 secs, 2 = 4 secs. + T h* Laplace transform operator (sec-I) g S = 2n .O ,~, I i t g c i 6 F i
.,m_-- 4 ? f P 5 TABLE 2.2-1 (Continued) j A [ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS I e l ? NOTATION (Continued) E { '33 ~ i Note 2: Overpower AT < AT [K -K T-K6(T-T")-f(AI)3 g 4 5 1+r3, 2 S h D g Where: AT, Indicated AT at RATED THERf4AL POWER l = Average temperature. *F J i T = i I f T" Indicated T at RATED THERMAL POWER 1 582.8 F = avg I l 1.088 g K = 4 0.02/ F for increasing average temperature f i K = 5 t 0 for decreasing average temperatures K = 5 0.00119 for T > T"; K6 = 0 for T 1" l T K = 6 l t T 3 3 The function generated by the rate lag controller for T,yg l = 1+1 S dynamic compensation l 3 [ 3 Time constant utilized in the rate lag controller for T,yg 1 = g 1 = 10 secs. 3 a Laplace transform operator (sec-I) } S = ( Ei f(AI)= 0 for all al 2 5 Note 3: The channel's maximum trip point shall not exc'eed its computed trip point by more than 2 percent span. E N + f l s, I i I a r i
t TABLE 3.2-1 4 S DNB PARAMETERS g ~ LIMITS b 2 Loops In Operation ** 2 Loops In Operation ** 5 3 Loops In & Loop Stop & Isolated Loop ] PARAMETER Operation Valves Open Stop Valves Closed Reactor Coolant System T < 587 F avg Pressurizer Pressure > 2205 psig* Reactor Coolant System > 278,400 gpm 'f Total Flow Rate sb N. 0 k r 8"
- Limit not applicable during either a THERMAL POWER ramp increase in excess. of 5% RATED THERMAL POWER a
{ ,F per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER. t
- Values dependent on NRC approval of ECCS evaluation for these conditions
$1 s t bn 4
7- _%~- .-mem- __ war l. l POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTION e LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following relationship: 2.14] [K(Z)] [F)(Z)]g = (i))(P )(1.03)(1 + a))(1.07) 7, / Where: 4 F)(Z) is the normalized axial power distribution from thimble a. j at core elevation Z. b. P is the fraction of RATED THERMAL POWER. c. K(Z) is the function obtained from Figure 3.2-2 for a given core height location. I), for thimble j, is determined from at least n=6 incore d. flux maps covering the full configuration of permissible 4 rod patterns above P,% of RATED THERMAL POWER in accordance a with: I h n ~ j 13 1 l ? Where: Meas L p R = ij [F (Z)] j and [F )(Z)] Max s the maxh value of the nomalized g l axial distribution at elevation Z from thimble j in map i which had a measured peaking factor without uncertainties or densification allowance of F q l l NORTH ANNA - UNIT 1 3/4 2-16 Amendment No. 3, 5, 78, 22, 37, 3 9 ti m -m a ~ .4+ C v w--[ --- 1 JAMh ; EPr +4#' = e b}}