ML20059E205
| ML20059E205 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/04/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20059E207 | List: |
| References | |
| DPR-16-A-142 NUDOCS 9009100089 | |
| Download: ML20059E205 (6) | |
Text
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GPU NUCLEAR CORPORATION 1
A.Np JERSEY CENTRAL POWER & LIGNT COMPANY DOCKET NO. 50-219 i
OYSTER CREEK NUCLEAR GENERATING STATION ANENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 142 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by GPU Nuclear Corporation, et al.,
(the licensee), dated February 20, 1990 as revised April 11, 1990 and superseded by application dated July 24, 1990 complies with the standards and requirements of the Atonic Energy Act of 1954, as amer,Ced (the Act), and the Commission's rules and regulations set l
forth in 10 CFR Chapter I; l
l B.
The facility will operate in conformity with the application,-
the provisions of the 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.
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9009100099 900904 fDR ADOCK 05000219 PDC
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2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, andparagraph2.C.(2)ofProvisionalOperatingLicenseNo.DPR-16ishereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in i
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGUL TORY COMMISSION
/
Jo
. Stolz, Directo '
Pr ject Directorate I vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 4, 1990 P
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, x, ATTACHMENT TO LICENSE AMENDMENT N0.142 l
PROVISIONAL OPERATING LICENSE NO. OPR-16 00CKET NO. 50-219 l
i Replace the following pages of the Appendix A Technical Specifications with
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the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page 4.7-2 Page 4.7-2 Page 4.7-3
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Page 4.7-4
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c.
Th3 cpecific gravity, fcr COth 6011, is grcat:r th2n or equal to 1.190 when correctev to 77'F.
The electrolyte temperature of every fifth cell (Diesel; every fourt,h cell) shall be recorded for surveillance review.
3.
At least once per 12 months, the diesel generator battery capacity shall be demonstrated to be able to i
supply the design duty loads (diesel start) during a i
battery service test.
t 4.
At least once per 24 months during shutdown, the following tests will be performed to verify battery
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capacity.
b a.
Battery capacity shall be demonstrated to i
be at least 40% of the manufacturers' rating when subjected to a battery capacity discharge test to be considered l
i operable.
l b.
Any battery which is demonstrated to have I
less than 85% of manufacturers ratings during a capacity discharge test shall be replaced during the subsequent refueling outage.
c.
station battery capacity shall be demonstrated to be able to supply the design duty cycle loads during a battery service test.
d.
Battery low voltage annunciators are i
verified to pick up at 115 volts a l' volt and to reset at 125 volts t i volt (Diesel; 112 volts 1 1 volt).
Basis:
The biweekly tests.of the diesel generators are primarily co ch0ck for failures and deterioration in the system since last use. The manufacturer has recommended the two week test interval, based on experience with many of their engines. One factor in determining this test interval'(besides checking whether or not the eagine l
starts and rune) is that the lubricating oil should be circulated through the engine approximately every two weeks.' The diesels should be loaded to at least 20% of rated power until engine and j
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generator temperatures have stabilised (about one hour).
The minimum 20% load will prevent. soot formation in the cylinders and injection nogales. Operation up to an equilibrium temperature ensures that there is no over-heat problem.
The tests also provide l
an engine and generator operating history to be compared with subsequent engine-generator test data to identify and correct any mechanical or electrical deficiency before it can result in a system failure.
l OYSTER CREEK 4.7-2 Amendment No.: )8,,W,$d e 142 l
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4 The test during refueling outages is more comprehensive, including procedures that are most effectively conducted at that time. These include automatic actuation and functional capability tests, to verify that ths generators can start and assume ic2d in less than 20 seconds *ad testing of the diesel generator lead sequence timers which provide protection from a possible diesel generator overload during LOCA conditions.
Thorough inspections will detect any signs of wear long before failure.
The manufacturer's instructions for battery care and maintenance with regard to the floating charge, the equalising charge, and the addition of water will be followed.
In addition, written records will be maintained of the battery performance., station batteries will deteriorate with time, but precipitous f ailure is unlikely.
The station surveillance procedures follow the recommended maintenance and testing practices of IEEE STD. 450 which have demonstrated, through experience, the ability to provide positive indications of cell deterioration tendencies long before such tendencies cause cell irregularity or improper cell performance.
The battery service test is a special capacity test to demonstrate the capability of the battery to meet the system design requirements. The Oyster Creek cesign duty cycle loads i
are determined by a LOCA subsequent to a loss of AC power.
The battery performance test is a capacity test on the battery to check it against the manufacturer's specified capacity and is
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used to determine when the battery has arrived at the end of its life.
IEEE standard 450-1975 recommends battery performance testing once per five years.
IEEE Standard 308-1974 recommends battery performance testing once per three years. The Oynter Creek Technical specifications require a performance test once per two years.
Both IEEE standards recommend decreasing the surveillance interval to annually when battery service life exceeds 854.
The diesel generator batteries are challenged every two weeks to perform the 20% load test.
This effectively performs an uninstrumented battery service test..The biweekly diesel start, when combined with the annual battery service test, provides an extensive amount of data on battery performance characteristics.
This test data negates the need to lower the battery performance test interval from biennially to annually.
The station batteries are required for plant operation, and performing the station battery performance test requires the reactor to be in COLO SHUTDOWN.
The guidance in IEEE 450-1975 would result in 3 performance tests to reach 854-service life, OYSTER CREEK 4.7.3 AMENDMENT NO.
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.fc11 owed by'3 perfccm:nco testo to completo b tt ry lifo. Tho guidance in IPEE 308-1974 would result in 5 performance tests to.
reach Uon service life, followed by 3 performance tests to cecplete battery life. _ The oyster, creek Technical 3pecifications require 8 performance tests to reach 854 service.
life, followed by 2 performance tests to complete battery life.
The requirement which would result in a reactor l shutdown for.no sole purpose'of performing a battery performance test during the last 15% of cattery life cannot be justified to increase battery test performance from ? to 3 in a 3-year period. Additionally, the-increase in battery performanco testing during the first 856 i
of battery service life would result in a greater level of battery reliability by identifying, and causing to be corrected, small.nomalies in cell performance thereby reducing battery failure probability.
The requirement to replace any battery in the next refueling outage which demonstrates less than 85% of manufacturers capacity dating a capacity discharge test provides additional-i assurance of-continued battery operability.
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I OYSTER CREEK 4.7-4
.2NDMENT No.: 142 t
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