ML20006E071
| ML20006E071 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/02/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20006E072 | List: |
| References | |
| DPR-16-A-136 NUDOCS 9002160196 | |
| Download: ML20006E071 (6) | |
Text
.
y e
1 7a j6
'C' UNITED STATES T
=
c NUCLEAR REGULATORY COMMISSION L
A..... f) i waswiwoTON, D C. 20666 ~
GPU NUCLEAR CORPORATION g[D JERSEY CENTRAL POWER & LIGHT COWANY DOCKET NO. 50-219 t
OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.136 License No. DPR-16 1
1.
The Nuclear Regulatory Comission (the Comission) has found that:-
A.
The. application for amendment by GPU Nuclear Corporation, et a1.,
-(the licensee), dated December 4,' 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended i
(the Act), and the Comission's. rules and regulations set forth in 10 CFR Chapter I;
- t
-B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 nI.;h the Comission's regulations; D.
The issuance of this amendment will not be inimical-to:the comon 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, t
(
l'-
9002160196 900201
'h
- PDR1 ADOCK 05000219 l
- P-PDC
2 2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Provisional Operating License No. DPR.16 is hereby i
amended to read as follows:
(2) Technical Specifications The Technical _ Specifications contained in Appendices A and_B, as revised through Amendnent No.136, am hereby incorporated in the licen se.
GPU Nuclear Corporation. shall operate the facility in accordance with the Technical Specifications.
'3.
This license amendment is effective as of the date of issuance, to be inplemented within -30 days of issuance.
FOR THE NUCLEAR R GULATORY COMMISSION n F. Stolz, Direc or s
f roject Directorat
-4
/ Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 4
Date of Issuance:
February 2, 1990 l
.1 s
1 l
ll l
'1
I ATTACHMENT TO LICENSE' AMENDMENT NO.
136 PROYl$10NAL OPERATING LICENSE NO. DPR-16 7
DOCKET NO. 50-219 i
i L
. Replace the-following pages of the Appendix A Technical Specifications with the' enclosed pages as. indicated. - The revised pages are identified by t-amendment num>er and contain vertical lines indicating the areas of change.
Remove
,fnsert 3.7-1 3.7-1 3.7 3.7-2
.l i
-3.7-3 3.7-3 1
3 i
.l i
l i
'l l
i
g 4;
K '. O
- 3.7 AurILI Any - r2.rcTRICAL POWrR -
E
??
- Acelicabilitv: = Applies to the operating status of the auxiliary electrical
<ia-power supply.
.=
ob4eetive:
To assure the operability of the auxiliary electrical power supply.
~.
- sneeification:
A.
The reactor shall not be made critical unless all of the following requirements are satisfied:
1.
The following buses or panels energiaod.
4160 volt buses 1C and 3D in the turbine building a.
switchgear roca, b.
460 volt buses 1A2, 182,,1A21, 1821-vital MCC 1A2 and 152 in the reactor building switchgear; rooms.
1A3 and 183 at the intake structure; 1A21A,.1821A, 1A213, and 18218 and vital MCC 1AB2 on 23'6"-
elevation in the reactor building; 1A24 and 1824
~
at the stack.
c.
208/120 volt panels 3, 4, 4A, 45, 4C and VACP-1 in the reactor building switchgear room.
d.
120 volt protection panel 1 and 2 in the cable
- room, 125 volt DC distribution centers C and B, and' l
s.
panel D, Panel DC-F, isolation valve motor control center DC-1 and.125V DC motor control center DC-2.
.t. 24 volt D.C. power panels A and B in the cable room.
2.
One 230 KV line is fully operational and switch gear and both startup transformers are energized to carry
's power to the station 4160 volt AC buses and carry i
power to or away from the plant.
3.
An additional source of power consisting of one of the following is in service connected to feed the-appropriate plant 4160 V bus'or buses:
a.
A-second 230 KV line fully operational.
'i b.
One 34.5 KV line fully operational' E.
4.
station batteries B and C and an associated battery changer are operable. Switchgear control power for 4160 volt bus 1D and 460 volt buses 182.and 1B3 are provided by battery.B.-switchgear control power for 4160 volt bus 1C and 460 volt buses 1A2 and 1A3 are i
provided by battery C.
5.
Bus tie breakers BD and BC are in the open position.
B.
The reactor shall be placed in the cold shutdown position if the availability of power falls below that required by Specification A above, except that 1.
The reactor may remain in operation for a period OYSTER CREEK 3.7-1 Amendment No.:
/
p(, F, $f, g 5751f/TSCR182 136 L
. -. - ~.
E
,g'
} # :.
net,to exceed 7 d:yo in any 30 Cay period if a m
.startup transformer is out of service, None of
. the engineered safety' feature equipreac fed by the
< remaining transformer'may be out of service.
'I 2.
The reactor may remain in' operation for a period
-not to.excaed.7~ days if 125 VDC Motor control.
[
Center DC-2 is'out of service, provided the 1.
requirements of' specification 3.8 are met.
o t
l-L C.
Standby Diesel Generators t
l 1.
The reactor shall not be made'eritie31 unless both diesel generators are operable and capable of feeding their designated 4160 volt buses.
.e 2.
If one diesel generator becomes inoperable during j
power operation, repairs shall be initiated immediately and the other diessi shall be. operated at least one hour every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at greater than 20% rated power until repaire are completed..The reactor may remain in operation for'a period not i
to exceed 7 days in any 30-day period if a diesel generator'is out of service.- During the repair L
period'none of the engineered safety features normally fed by the operational diesel generator may be out of service.or the reactor shall be placed in the cold shutdown condition.
3.
If both. diesel generators become inoperable daring j
power operation, the reactor shall be placed in the cold shutdown condition.
o 4.
For the diesel. generators to be. considered operable there shall be a minimum of 14,000 4
gallons of diesel' fuel in the standby diasel generator fuel tank.
RAERg:
The general objective is to assure an adequate supply of. power with at least one active and one standby source of. power available for operation of equipment required for a safe plant' shutdown, to maintain the plant in a safe shutdown cond1*lon d
to operate the required engineered safety feature equipmenc iollowing an accident.
-AC power for shutdown and operation of engineered safety feature equipment can be provided by any of four active (two 230 KV and two 34.5-KV lines) and either of two standby (two diesel i
generators) sources of power. Normally all six sources are I
available. However,"to provide for maintenance and repair of equipment and still have redundancy of power sources the requirement o2-one' active and one standby source of power was established. The plant's main generator is not given credit as a
[
source since it is not available during shutdown.
I
- OYSTER CREEK-3.7-2 Amendment No.*
% f!I,,99', J41I 136 5751f/TsCRls2
- -1 i
---__--_-_-_.---_,-_-.------d-.-_--.._u-
. Lii 'O;
>*~
,1
/'.
f4
.Th3 plcnt 125V DC System consi3to of three b2tt:rios cnd escocictsd'
. distribution system._ Batteries B and C are designated as the safety o
related subsystems while battery A is_ designated as a non-safety related subsystem.
Safety related loads are supplied by batteries B and C, each with two. associated full capacity chargers, one charger on each battery is ~ in' service at all times with the second charger available in the event i
p of charger' failure.. These. chargers are active soure.s and supply the normal 125V DC coquirements with the batteries and standby sources. -(1) l' L
In applying the minimum requirement of~one active and one standby source 1
of AC power, since both 230 KV lines are on the same set of towers, either one or both 230 KV lines are considered-as a single active source.
,N The probability analysie in Appendix "La of the FDSAR was based on one~
y O'
diesel and shows'that even'with only one diesel the probability of
~
requiring engineered safety features at the same time as the second diesel fails is quite small.
This analysis used information on peaking diesels when synchronisation was required which is not the case for oyster Creek.- Also the daily test of the second diesel when one is temporarily out of-service tends to improve the reliability as does the.
fact that synchronisation is not required.
As indicated in Amendment 18 te the Licensing Application, there are p
numerous sources of diesel fuel which can be obtained within 6 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> snd the heating boiler feel in a 75,000 gallon tank on the site l
-could also be used. As indicated in Amendment 32 of the Licensing Application and including the Security System loads, the load requirement i
for the loss of offsite power would require 12,410 gallons for a throa day supply.
For the case of loss of offsite power plus loss-cf-coolant.
I plus bus failura 9790 gallons would be required for a three day supply.
In the case of loss of offsite power plus lorg-of-coolant with both, diesel generators starting the load requirements (all equipment-operating) shown there would not be three days' supply.
However, not.all.
of this load is requirad for three days and, after uvaluation of the conditions, loads not required on tht diesel will be curtailed.
It is
. reasonable to expect that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> conditions can be evaluated and the-following loads curtailed:
1.
One' Core Spray Punip I
2.- One Core Spray Booster Pump.
'3.
One control Rod Drive Pump 4.
One Containment Spray Pump 5.
One Emergency Service Water Pump With these pieces of equipment taken off at 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the incident it would require a total consumption of 12,840 gallons for a three day supply..Therefore, a minimum technical specification requirement of 14,000 gallons of diesel fuel in the standby diesel generator fuel tank will exceed the engineered safety features operational requirement after an accident by approximately 94.
References:
(1)
Letter, Ivan R. Finfrock, Jr. to the Director of Nuclear Reactor Regulation dated April 14, 1978.
OYSTER CREEK 3.7-3 Amendment No.:
W,f/f,SM M 136 5751f/TSCR182 f
v.
.2