ML20032A707
| ML20032A707 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/19/1981 |
| From: | Phyllis Clark JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20032A708 | List: |
| References | |
| NUDOCS 8111020223 | |
| Download: ML20032A707 (7) | |
Text
OYSTER CREEK NUCLEAR GENERATING STATION s
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(609)693-6000 P O BOX 368
- FORKED RIVER e NEW JERS -
08731
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October 19, 1981
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fg h p;_p>g Director, Nuclear Reactor Regulation Q
Nuclear Regulatory Commission Q.-
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Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 97 In accordance with 10 CFR 50.59 and 10 CFR 50.90, Jersey Central Power 6 Light Company, owner and operator of the Oyster Creek Nuclear e
Generating Station, Provisional Operating License No. DPR-16, requests changes to Appendix A of that license.
The subject Technical Specification Change Request involves Table 3.1.1 and Section 3.1 and 3.7.
Tabic 3.1.1 shall be revised to reficct changes in the Diesel Generator Load Sequence Timers for the Service.
Water Pump and the Closed Cooling Water Pump and the notes to the specification requirements for protective instrumentation.
Section 3.7 Bases shall be revised to remove the Service Water Pump and Lhe Closed Cooling Water Pump from the list of loads to be curtailed during the postulated lo s-of-coolant accident. The bases shall also be changed to reflect the revised diesel generator fuel oil consumption values.
Section 3.1 Bases shall also be revised to reficct tripping off the Closed Cooling Water and Service Water Pumps during LOCA.
The Technical Specification Change Request has been reviewed and approved by the Plant Operations Review Committee and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.
It is requested that the effective date of this Technical Specification Change Request be thirty days after being approved by the NRC.
We have determined that this submittal is Class II per 10 CFR 170.22 and have enclosed a check for $1,200 pursuant to that section.
40 7 J[J Very truly yours,
- & f a X G { Q s.J + H"',y Philip,. Clark
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- Vice President-Nur car Jersey Central Power 6 Light Company Enclosure 8lil1020 M P
JERSEY CENTRAL POWER 6 LIGIT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO DPR-16 Technical Specification Change Eequest No. 97 Docket No. S0-219 Applicant submits, by this Technical Specification Change Request No. 97 to the Oyster Creek Nuclear Generating Station Technical Specifi-cations, a change to Specifications Table 3.1.1, 3.1 Bases and 3.7 Bases.
By:
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Vice P;6sident - Nuclear Jersey Cedtral Power G Light Company Sworn and subscribed to before me this 19th day of October, 1981.
. hb,LL:<w /9. ;;d /w I PHYLLIS A. KABIS NOTARY PUBLIC OF NEW JER$EY My Comminion Empires Aug.16,1984 3
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4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN Tile MATTER
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DOCKET NUMBER 50-219 JERSEY CENTRAL POWER S LIGliT COMPANY )
CERTIFICATION OF SERVICE This is ':o certify that a copy of Technical Specification Change Request No. 97 for the Oyster Creek Nuclear Generating Station Technical Specification, filed with the U.S. Nucicar Regulatory Commission on October 19, 1981, has this 19th day of October, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail addressed as follows:
The Honorable Jorge A. Rod Mayor of Lacey Township P.O. Box 475 Forked River, N. J.
08731 By:
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Vice Presi nt - Nuclear Jersey Central Power 6 Light Company DATEb: October 19, 1981
GYOTER CREEK L<~c],V NUCLEAR GENERATING STATI@N irm
]nn (609)693-6000 P O DOX 368
- FORKED RIVER
- 08731 1.-
October 19, 1981 The lionorable Jorge A. Rod Mayor of Lacey Township P.O. Box 47S Forked River, N. J.
08731
Dear Mayor Rod:
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Enclosed herewith is one copy of Technical Specification i
Change Request No. 97 for the Oyster Creek Nuclear Generating Station Technical Specifications.
These documents were filed with the U.S. Nuclear Regulatory Commission on October 19, 1981.
Very truly yours, l
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bu Philip R. Cl rk Vice President - Nuclear i
Jersey Central Power T, Light Company Ir Enclosure l
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Jersey Central Power S Light Company Oyster Creek Nuclear Generating Station I
(Docket No. 50-219)
Provisional Operating License DPR-16 Applicant hereby requests the Commission to change Appendix A of the above captioned license as follows:
1.
Sections to be changed:
a.
Section 3.1 Bases b.
Table 3.1.1 M c.
Tabic 3.1.1 Notes o, z, aa, and bb d.
Section 3.7 Bases 2.
Extent of changes:
a.
Tabic 3.1.1 Protective Instrumentation Requirements.
Revised the Diesel Generator Load Sequence Timers for the Service Water pump and the Closed Cooling Water pump.
b.
Table 3.1.1 Protective Instrumentation Requirements.
Revised the note applicable only to the Service Water pumps. Added notes for clarifying the tripping of the Closed Cooling Kater and Service Water pumps.
c.
Section 3.7 Auxiliary E1cetrical Power.
Delete the Reactor Building Closed Cooling Water Pump and the Service Water Pump from the Bases.
d.
Section 3.1 Protective Instrumentation.
Revised the Bases to reficct the changes in Table 3.1.1.
3.
Change Requested:
The requested change is on the attached revised Technical Specification pages 3.1 6a, 3.1-11a, 3.1-13, 3.1-14, and 3.7-3.
4.
Discussion:
Technical Specification Tabic 3.1.1 cites the requirements for protective instrumentation. The Diesel Generator Load ~
Sequence Timers for the Service Water Pump and the Closed Cooling Water Pump, Table 3.1.1 M.4 and 3.1.1 M.5 respectively, are presently included in the subject specification. The load sequence timers prevent the simultaneous starting of the emergency core cooling and large auxiliary system loads under the postulated loss-of-coolant accident conditions. These sequential time delay relays are provided in order to minimi:e the voltage drop across
-the emergency buses and to protect against a potential diesel generator overload.
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4.
Discussion:
(cont'd)
The purpose of this Technical Specification Change Request is to revise the requirements for the Service Water Pump and Closed Cooling Water Pum,. time delay relays 'in the Technical Specifications. The justification for this change is Amendment 42 of the Licensing Application which determined that these pumps were not required during the postulated accident condition.
This change is reflected in Section 3.1 Bases and is desired in order to accommodate a modification which will remove by tripping their circuit breakers, the Service Water Punps and the-Closed Cool.ing Water-Pumps from the Diesci Generator Load Sequence during a loss-of-coolant accident. This will decrease the loading on the diesel generator and thereby enhance the ability of the diesel generator to provide power to the required safety loads during the postulated loss-of-coolant accident.
The basis of Technical Specification 3.7 will also be affected by this change request. The basis states that within eight hours following a loss-of-coolant accident, numerous loads will be curtailed.
This change consists of deleting the Reactor Building Closed Cooling Water and Service Water pumps from the list of loads to be curtailed.
This is due to the fact that these pumps are not required during the loss-of-coolant accident.
This change request includes revised diesel generator fuel consumption values in the basis of Technical Specification 3.7.
This revision reficcts the addition of the Site -Security System loads to the load requirements contained in Amendment 32 of the Licensing Application. Also included in this change request is the decreased i
l fuel consumption due to the removal of the Reactor Building Closed Cooling Water and Service Water pumps during a loss-of-coolant accident. The derivation of these values is included in the attached Tabic 1.
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and the requirements of Table 3.1.1 are met.
In order to maintain reliability of core monitoring in that quadrant where an APRM is inoperable, it is permitted to remove the operahic APRM from service for calibration and/or test provided that 'the same core protection is maintained by alternate means.
In the rare event that Travelling In-core Probes (TIPS) are used to meet the requirements 3.1.B or 3.1.C, the licensee may perform an analysis of substitute LPRM inputs to the APRM system using spare (non-APRM input) LPRt detectors and change the APRM system as permitted by 10 CFR 50.39.
Under assumed loss-of-coolant accident conditions and under certain loss of offsite power conditions with no assumed loss-of-coolant accident, it is inadvisabic to allow the simultaneous starting of emergency core cooling and heavy load auxiliary systems,in order to minimi:e the voltage drop across the emergency buses and to protect against a potential diesel generator overload. The diesel generator load sequence time delay relays provide this protective function and are set accordingly. The repetitive accuracy rating of the tirer mechanism as well as parametric analyses to evaluate the maximuu acceptable tolerances for the diesel loading sequence timers were considered in the establishment of the appropriate load sequencing.
Manual actuation can be accomplished by the operator and is considered appropriate only when the automatic load sequencing has been completed. This will prevent simultaneous starting of heavy load-auxiliary systems and protect against the potential for diesel generator overload.
i Also, the Closed Cooling Water and Service Water pump circuit breakers will trip whenever a loss-of-coolant accident condition exists. This j is justified by Amendment 42 of the Licensing, Application which determined that these pumps were not required during this accident condition.
Reference:
(1)
NEDO-10189 "h; Analysis of Functional Common >bde Fai' lures in GE BWR Protection and Contru.'. Instrumentatio'n", L. G. Frederick, l
et. al., July 1970.
Change No.,6' Amendment No. p; }5,, 44 l
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