ML20137T790
| ML20137T790 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/04/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137T796 | List: |
| References | |
| NUDOCS 8602180434 | |
| Download: ML20137T790 (5) | |
Text
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UNITED STATES 3'
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 s
GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET N0. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE 1
1 Amendment No. 99 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated November 7, 1985, complies with the standards and require-ments of the Atomic Energy Act of 1954, as arrended (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 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 Comission's regulations and all applicable requirements have been satisfied.
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D 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 Provisional Operating License.
No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in' Appendices A and B,-
as revised through Amendment No. 99, are hereby incorporated
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in the license. GPU Nuclear Corporation 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 NU LEAR REGULATORY ptNISSION k4 i
John
. Zwolinski, Director BWR P ject Directorate #1 Division of.BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 4,1986
ATTACHMENT TO LICENSE AMENDMENT NO. 99 PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET N0. 50-219 Revise Appendix A Technical Specifications b~y removing the page identified below and inserting the attached page. The revised page is identified by the captioned amendment number and contain vertical lines _ indicating the area of-change.
REMOVE INSERT 3.7-2 3.7-2 3.7-3 3.7-3 1
3.7-2
)
None of the engineered safety-feature equipmeint fed by the remaining transfomer may be out of service.
C.
Standby Diesel Generators 1.
The reactor shall not be made critical unless both diesel generators are operable and capable of feeding their designated 4160 volt buses.
2.
If one diesel generator becomes inoperable during power operation, repairs shall be initiated imediately and the other diesel 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 repairs are completed.
The reactor may remain in operation for a period not to exceed 7 days in any 30-day period if a diesel generator is out of service. During the repair period none of the engineered safety features nomally fed by the operational diesel generator may be out of service or the reactor shall be placed in the cold shutdown condition.
3.
If botn diesel generators become inoperable during power operation, the reactor shall be placed in the cold shutdown condition.
4.
For the diesel generators to be considered operable there shall be a minimum of 14,000 gallons of diesel fuel in l
the standby diesel generator fuel tank.
Bases:
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 condition and to operate the required engineered safety feature equipment following 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 standoy (two diesel generators) sources of power.
Normally all six sources are available.
However, to provide for maintenance and repair of equipment and still have redundancy of power sources the requirement of 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. The plant 125V DC power is normally supplied by two batteries, 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 of charger failure.
These chargers are active sources and supply the normal 125V DC requirements with the batteries and standby sources. (1)
In applying the minimum rquirement of one active and one standby source of AC power, since botn 230 KV lines are on the same set of towers, either one or both 230 KV lines are considered as a single active source.
Amendment No. g3, y3,99
3.7-3 The probability analysis of Appendix "L" of the FDSAR was based on one 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 synchronization 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 synchronization is not required.
As indicated in Amendment 18 to the Licensing Application, there are 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 /> and the heating boiler fuel in a 75,000 gallon tank on the site could also be used. As indicated in Amendment 32 of the Licensing Application and including the Security System loads, the load requirement for the loss of offsite power would require 12,410 gallons for a three day supply. For-the case of loss of offsite power plus loss-of-coolant plus bus failure 9790 gallons would be required for a three day supply.
In the case of loss of offsite power plus loss-of-coolant with botn diesel generators starting the load requirements (all equipment operating) shown there would not De three days' supply. However, not all of this load is required for three days and, after evaluation of the conditions, loads not required on the 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 Pump j
2.
One Core Spray Booster Pump 3.
One Control Rod Drive Pump 4.
One Containment Spray Pump 5.
One Emergency Service Water Pump j
With tnese 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 tne incident it would require a total consumption at 12,840 gallons for d' 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 af ter an accident by approximately 9t.
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References:
i (1) Letter, Ivan R. Finfrock, Jr. to tne Director of Nuclear Reactor Regulations dated April 14, 1978.
Amendment No.55, g,99 I
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