ML19338D520
| ML19338D520 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/09/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19338D517 | List: |
| References | |
| NUDOCS 8009230390 | |
| Download: ML19338D520 (8) | |
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k UNITED STATES NUCLEAR REGULATORY COMMISSION g
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-COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION STATION UNIT 1-AMENDMENT TO~ FACILITY OPERATING LICENSE Amendment No. 57 License No. DPR-39 1.
The' Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated August 15, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations and all applicable requirements have been satisfiea.
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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. OPR-39 is hereby amended to read as follows:
.'(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as -revised through-Amendment N.o.' 57, are
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hereby -incorporated in.the license.
The. licensee shall operate.the facility:in.accordance with the Technical Specifications.
3.~ This license amendment is effective as of the date of its' issuance.
FOR THE-NUCLEAR REGULATORY COMMISSION
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e Operating Reactors (E ranch #1 Division of Licenshg Attachtrent:
Changes to the-Technical Specifications Date of Issuance: September 9,1980
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UNITED STATES j+
NUCLEAR REGULATORY COMMISSION a
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8 wAsWNGTON, D. C. 20555 L
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COMMONWEALTH EDIS0N COMPANY DOCKET 'O. 50-304 N
ZIONLSTATION UNIT.2 AMENDMENT T0' FACILITY OPERATING LICENSE.
Amendment No. 54 License-No. DPR 48 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 15, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the Act) and the Comission'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 Comission; C.- There is. reasonable. assurance (i) that the activities authorized by this armndment 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 Com'3sion's regulations and all applicable-requirements have'been satisfied.
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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.0perating License-
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No.- DPR-48 is hereby amended'to read as follows:
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,(2) Jechnical Specifications-
.The Technical: Specifications contained in Appendices iA and B, as. revised through Amendment No. '54, are.
- hereby incorporated in the license.1The licensee shall
.- operate ;the : faci.lity3.in.accordance with the Technical
' Specifications.
3.
This license amendment.is effective as of the date-of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ve he Operating Reacto ranch #1 Division of Licens
Attachment:
Changes to the-Technical Specifications Date of Issuance: September 9, 1980-s f
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- ATTACHMENT TO LICENSE-AMENDMENTS
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~ AMENDMENT NO.'57-~TO FACILITY OPERATING' LICENSE NO.=DPR-39
' AMENDMENT'NO. 54'TO' FACILITY'0PERATING LICENSE NO. OPR-48' DOCKET'NOS. 50-295 AND-50-304 Revise. Appendix A'as follows:
Insert Pages Remove Pages-178 178 194~
194 195-195 a
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l?. i' ~ 7. ServiceLUater system
- l14.8 7 Service water system (Table
.3-6)*
.A.
Three' service water pumps'1A, 18, 1C A.
Surveillance and testing of the' service
- (2A, '2B, 20) per unit shall.be operable water system shall be performed as whenever the reactor is Eoing from hot follows:
shutdown to hot-standby.
- 1. The service water pumps shall oe-operated each scnth.
Perfcrmance will oe acceptable if the pump starts upon actuation, operates fcr at least four hours,.and satisfies the cooling're-quirements necessary for the routine operation of the service water system.
- 2. The service water pump system power operated valves shall be stroked manually from the ccntrol room each scnth.
Performance will oe accept-
'aole if valve motien is indicated up:n actuation.
- Until completion of circulating water pump maintenance
- Until completion of circulating water pump maintenance program, scheduled for completion about December 31, program, scheduled for completion about December 31, 1931~, one service water pump may be out of service for 1981, the surveillance requirements of 4.8.7.C do not M
maintenance purposes. During this period, the required
. pertain to the service water pump out of service for O
number of operable pumps as stated in 3.8.7.A, 3.8.7.B, maintenance purposes.
U and '3.8.7.C may be reduced.by one for a single unit. pro-y vided the main 48-inch service water headers for each unit are cross-tied. While in the cross-tied mode, an g
optrating service water pump from the other unit with independent standby AC and DC power supply may be used M
to fulfill the requirements of 3.8.7.
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'JEE) 178 Amendment No.'57, Unit 1 y----
Amendment No. 54, Unit 2
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- TheLavailability
- of the systems is demon-into the primary. coolant system following '
strated by immediately~ demonstrating the a loss-of-coolant-accident and are. based 2
operability of;the components redundant to on the values used for the accident analysis.
1
- therfailed.~one,:as well as the-operability (4)
.of the inter-related. systems and the standby.AC and.DC power supplies.that feed The: limits for the accumulators,;and their: -
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" them. ' The continued ' availability = of these pressure and volume' assure the required
- components during the. repair period is amount of water injection with the required
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demonstrated by repeating'these' tests daily.
boric acid _ concentration.following a loss-of-coolant accident, and:are based on_the C Assuming's reactor has been. operating at values used for the accident analyses.-(4);
full rated power for ;at least 100 days, the magnitude:of'the decay heat decreases after The five component cooling system pumps t
/init)ating hot shutdown.
Thus, the require-and three heat exchangers are located in the-Taent for core cooling in case of a postu-Auxiliary Building and are a shared system lla-ted loss-of-coolant accident while.in the between Units I and II.
The-components are-
) hot. shutdown condition is.significantly accessible for. repair l af ter a loss-of-coolant ~
reduced below the requirements for a pos-
. accident.
During the recirculation phase:
tulated loss-of-coolant accident during following a loss-of-coolant accident on a
. power operation.
Putting a reactor in unit, only one component cooling pump and
.the hot-shutdown condition significantly heat exchanger-is required for minimum safe -
u reduces the potential consequences of a guard of that unit.
Therefore..a minimum loss-of-coolant accident, and also allows requirement of 4 component cooling pumps and more free access to some of the engineered three heat exchangers forstwo operating units "TEd safeguards components in order to effect providea. sufficient redundancy. (5)
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i 65E3 repairs A total of six service-water pumps.are-(__3 Failure to complete repairs within an ins.talled; only one service waterfpump is l loss-of-coolantaccident.-(6)gapostulated J N.D additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of going to the hot required immediately.followin
-Isee p. 195)
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-shutdown condition is considered indicative
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of a requirement for major maintenance and therefore in such a case, the reactor is to The hydrogen purge system is. designed-to
- _ EB58" be put.into the cold shutdown condition.
purge' combustible gases from.the containment.
$55) following a loss-of-coolant accident -(7)(8).
The limits for the boron injection tank The containment hydrogen. sampling system is :
'5dd and refueling water storage tank insure used to determine.the effectiveness -of this -
3ED the required amount of water with the system.
j 4.
required boron concentration for injection 1 94 Amendment No. 57, Unit 1 Amendment.No.-54, Unit 2-
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h A hydrogen recmbiner systen is being installed to If during this seven (7) day period a third remove the hydrogen and oxygen gases that. accumulate service water purnp becomes inoperable, the unit 7:
in the containment atnosphere following a loss-of-will be brought to hot shutdown'within four (4) coolant accident. (9) The system operability require-hours unless one of the. inoperable purrps are ment becomes effective following successful pre -
returned to operable status. %e requirement operational testing. %is equipnent shall be installed for independent standby IC 'and DC power.suglies by the first refueling outage on Unit 1, if delivery for an operating service water purp fr m the-s:hedules permit.
other unit precludes the possibility of losing two service water pumps dedicated to the same
%e equipnent used in evaluating the post loss of unit because of the failure of a corrmon power coolant accident condition is required to provide
- supply, monitocincj of the reactor, primary containnent(10) and radiation effect to the environs, both on site and off site. % e required equipment has been built and tested to meet the expected conditions where the conditions will be other than normal operating (1) FSAR Chapter 9 corditions.
(2) FSAR Section 6.2 (3) FSAR Section 6.2.3
- Until completion of circulating water pump maintenance (4) FSAR Section 14.3 program, scheduled for completion about December 31, (5) FSAR Section 9.3 1981,-one service water pump at a time may be taken out of service to perform maintenance on the associated cir-l(6)FSARSection9.6andFSARAnswertoQuestion culating water pump.
In order to work on a circulating 8
'9.1 water pump, an intake plenum must be drained. The intake (7) FSAR Section 14.3.6 (8) PSAR Answer to Question 9.9 plenum is a common reservoir for a service water pump and (9) FSAR Section 6.8 a circulating water pump. This leaves five service (10) FSAR Section 7.5.3 water pumps in service, which will provide sufficient coverage for any postulated loss of coolant accident coincident with a loss of offsite power and any other single failure of an active components. With this temp-orary. specification, should a second service water pump -
become inoperable, it must be returned to operable status within seven (7) days or the unit will be brought to hot
. shutdown.
Amendment No. 57, Unit 1 195 Amendment No. 54, Unit 2
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