ML20127H130
| ML20127H130 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/15/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127H135 | List: |
| References | |
| NUDOCS 9301220215 | |
| Download: ML20127H130 (8) | |
Text
-__
j # "*%k UNITED STATES NUCt. EAR REGULATORY COMMISSION 3
(
y psmNG TON. D. C. 20555 e
\\..../
Ql)0VESNE LIGHT COMPANY OH10 EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-331 BEAVER VALLEY POWER STATION. UNIT N0. 1 AMEN 0 MENT 10 FACJLITY OPERATING LICENS1 Amendment No.169 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light company, et al. (the licensee) dated July 15, 1991, as modified by letters dated September 30, 1991, December 13, 1991, and November 2, 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 o3erate in conformity with the application, the provisions of tae 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.
9301220215 930115 DR ADOCK 0300 4
1 i 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 140. DPR-66 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment tio.169, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Inis license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE f1VCLEAR REGULATORY COMMISS10f1 Walter R. Butler, Director Project Directorate 1-3 Division of Reactor Projects - 1/11 Office of fluclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 15, 1993
'4--
ATTACHMENT -TO LICENSE AMENDMENT NO.169 E6(ILITY OPERATING Ll CENSE N0. DPR-66 QQLKfT NO. 50-334 Rep. ice the following pages of Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number aci contain vertical lines indicating the areas of change, Remove ipsert 3/4 4-4a 3/4 4-4a 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 3/4 4-27a 3/4 4-27a B 3/4 4-la.
B 3/4 4-la 4
w t
.o. - -.
w
-e e
w-e
.n-i
REACTOR COOLANT SYSTEM REACTOR COOLANT PUMP STARTUP LIMITING CONDITION FOR OPERATION 3.4.1.6 If both OPPS PORV's are not OPERABLE, an idle reactor coolant pump in a non-isolated loop shall not be started, ut.less :
1.
The actual pressurizer water level is less than 60 percent 3
(840 f t ),
and
-[
2.
The secondary water temperature of each steam generator is less than 25'F above each of the in-service RCS cold leg temperatures.
g APPLICABILITY:
When the temperature of one or more of the o ;'
non-isolated loop cold legs is less than or equal to the enable temperature set forth in Specification 3.4.9.3.
m ACTION:
Withthepressurizerwaterlevelgreaterthanorequalto60 percent [
or the temperature of the steam generator in the loop ansociated with the reactor coolant pump being started greater than or equal to 25'r l above the cold leg temperature of the other non-isolated loops, suspend the startup of the reactor coolant pump.
SURVEILLANCE REQUIREMENTS 4.4.1.6.1 The pressurizer water volume and the secondary water temperature of the non-isolated steam ganarators shall be determined l within ten minutes prior to starting a reactor coolant pump.
')
The secondary water temperature is to be varified by direct measurement of the fluid tamparature, or contact temperatura readings on the steam gener.stor sacondary, or blowdown piping af ter purging of stagnant water within the piping.
BEAVER VALLEY - UNIT 1 3/4 4-4a Amendment No. 160,169
DPR46 MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: INTERMEDIATE SHELL PLATE B6607-2 RT AFTER 16 EFPY : 1/4T, 224*F NDT 3/4T,188'F 2500 f
L TEST LIMIT 2000 cr> f 750 E
i y,,,
HEATUP RATES TO 60 'F/HR x 1250 c.
UNACCEPTABLE
/
CRITICAllT/
O1000 OPERATION
/
LIMIT FOR THE h
SERVICE PERIOD 5 750 UP TO 16 EFPY (BASED ON 500 CEPTABLE OPERATION HYDROSTATIC 250 i
TEST TEMP.
OF 351*F)
Ob 60 100 150 200 250 300 353 400 450 500 INDICATED TEMPERATURE ('F)
FIGURE 3.4 2 Beaver Valloy Unit 1 Ranctor Coolant System Heatup Limitations Applicable for the First 18 EFPY BEAVER VALLEY - UNIT 1 3/4 4-24 Amendment No. m,169 l
SYAAN M %\\W N 3) B M NGH1V/ M M M P M W P W H ^
v'
~ ~ ' ~
~,
t DPR-66 MATERIAL PROPERTY BASIS CONTROLLING MATERIAL: INTERMEDIATE SHELL PLATE B6607-2 RT AFTER 16 EFPY : 1/4T, 224'F NDT 3/4T,188 'F 2500 2250 2000 5 1750 I
E UNACCEPTABLE OPERATION 1500
$1250 a-t 0 000 1
COOLDOWN 2
750 z
RATES 'F/HR 7
ACCEPTABLE 20Dr e
V OPERATION 500 ;gp=
P
==
250 1
l I
O O
50 100 160 200 250 300 350 400 450 500 INDICATED TEMPERATURE (*F)
FIGURE 3.4-3 Beavor Valley Unit 1 Retetof Coolant System Cooldown Limitations ApplicA for the First 16 EFPY BEAVER VALLEY-UNIT 1 3/4 4-25 Amendment No. Is7,169 (NEXT PAGE IS 3/4 4-27)
w l
REACTOR COOLANT SYSTEM OVERPREESURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:
Two power operated relief valves (PORVs) with a nominal trip l a.
setpoint of less than or equal to 432 psig, or b.
A reactor coolant system vent of greater than or equal to 3.14 square inches.
APPLICABILITY:
When the temperature of one or more of the non-isolated RCS cold legs is less than or equal to an enable temperature of 329'F.
l ACTION:
With one PORV inoperable, either restore the inoperable PORV a.
to OPERABLE status within 7 days or depressurize and vant the RCS through a 3.14 square inch vent (s) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.
Refer to Technical Specification 3.4.1.6 for further limitations, b.
With both PORV's inoperable, depressurize and vent the RCS through a 3.14 square inch vent (s) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; maintain the RCS in a vented condition until both PORVs have been restored to OPERABLE status.
c.
The provisions of specification 3.0.4 are not applicable.
SURVEILLANCE REQUI!U:MDrr 4.4.9.3.( Each PORV shall be demonstrated OPERABLE BY:
BEAVER VALLEY - UNIT 1 3/4 4-27a Amendment No. 150. 169
4 1/4.4 REACTOR COOLANT SYSTEM BASES J/4.4.1 REACTOR COOLANT LOOPS, (continued) of Appendix G by (1) restricting the water level in the pressurizer l and thereby providing a volume for the primary coolant to expand into and (2) by restricting starting of the RCPs to when the secondary l water temperature of each steam generator is less than 25'F above each of the RCS cold leg temperatures.
Power is removed from the isolated loop stop valves (hot leg and cold leg) to ensure that no reactivity addition to the core can occur while the loop is isolated due to inadvertent opening of the isolated loop stop valves.
Isolated loop startup is limited to Modes 5 and 6 in accordance with the NRC SER on N-1 loop operation.
Verification of the isolated loop boron concentration prior to opening the isolated loop stop valves provides a reassurance of the adequacy of the shutdown margin in the remainder of the system.
Restoration of power to the hot leg stop valve allows opening this valve to complete the recirculation flowpath in conjunction with the ralief line bypassing the cold leg stop valve and ensures adequate mixing in the isolated loop.
This enables the temperature and boron concentration of the isolated loop to be brought to equilibrium with the remainder of the systen.
Limiting the temperature differentict between the isolated loop and the remainder of the system prior tc opening the cold leg stop valve prevents any significant reactivity stfacts due to cool water addition to the core.
Startup of an idle loop will inject cool water from the loop into the core.
The reactivity transient resulting from this cool water injection is minimized by delaying isolated loop startup until its temperatura is within 20*F of the operating loops.
Making the reactor subcritical prior to loop startup prevents any powar spike which could result f rom this cool water induced reactivity transient.
3/4.4.2 and 3/4.4.3 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 345,000 lbs. per hour of saturated steam at the valve set point. The relief capacity of a single safety valve is adequate to BEAVER VALLEY - UNIT 1 B 3/4 4-la Maendment No. IED,169
_ _._--_ - -__-__ -