ML20247N016
| ML20247N016 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/24/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247N013 | List: |
| References | |
| NUDOCS 8906050224 | |
| Download: ML20247N016 (2) | |
Text
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'k UNITED STATES i
j NUCLEAR REGULATORY COMMISSION g
casHWGTON, D. C. 20555 d.....
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION L
.RELATED TO AMENDMENT NO. 130 TO FACILITY OPERATING LICENSE N0. DPR-46
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NEBRASKA'PUBLIC POWER DISTRICT COOPER NUCLEAR STATION
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DOCKET NO. 50-298
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1.0 -INTRODUCTION By letter dated January 27, 1989 the Nebraska Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-46 for the Cooper Nuclear. Station. The proposed amendment would change the Technical Specifications to specify-revised Limiting Conditions for Operation and Surveil-lance Requirements for the 250 VDC batteries. The 250 VDC System supplies power to essential motor operated valves, instruments and control circuits.
2.0 DISCUSSION.
The original 250'VDC' lead-acid batteries at Cooper Nuclear Station are being
.. replaced during-the 1989 Cycle 12 refueling outage due to age and deterioration.
The licensee.is replacing the lead-acid batteries with lead-calcium batteries having.a higher ampere-hour rating. The existing 200 ampere chargers are also being replaced.with chargers of the same capacity. The sizing. criteria for new battery and charge new installations were selected on the basis of system load profiles prepared by the licensee's contractor and verified by the licensee..
In~ support of these changes, the licensee has requested changes to the Technical
. Specifications as follows:
m A..
In Specification 4.9.A.4.a.3 (weekly pilot cell surveillance test),
change the 125 VDC battery pilot cell minimum voltage from 2.0 to 2.15 Volts, and the temperature-corrected minimum specific gravity from 1.190 to 1.195.
B.
In specification 4.9.A.4.b.2 (quarterly surveillance test of all cells),
change the minimum to voltage for each cell from 2.0 Volts to 2.15 Volts.
In addition, a requirement for a minimum average specific gravity of 1.200 l
for a11' connected cells would be added.
C.
In Specification 4.9.A.4.d (once-per-cycle battery capacity tests) an annual battery service test has been added with a performance discharge test required in lieu of the battery service test 1) every fifth year,
- 2) when the battery shows signs of degradation, and 3) when the battery has been in use for seventeen years.
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8906050224 890524 PDR ADOCK 05000298 P
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s-D.
The b'ases for Specification 3.9 have been modified to include a
~ reference to the new testing that is being added for the 250 Volt
. batteries.
The IEEE Battery Working Group has prepared draft Standard Technical Specifi-cations for battery installations at BWR facilities. The IEEE draft criteria recommends (1).'a minimum float voltage of 2.13 for the weekly and quarterly u
tests, (2) a minimum cell specific gravity of 1.195 for the the weekly pilot cell surveillance, (3) a minimum individual cell specific gravity of 1.190 for i
the quarterly surveillance, (4) a minimum average specific gravity of 1.200 for l
months, (6) y surveillance, (5) a battery service test at least once every 18 the quarterl
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a performance discharge test in 11eu of a service-test at least once every 60 months, and (7) an annual performance discharge test for a battery exhibiting signs of degradation.
These IEEE Working Group's recommendations, while not yet endorsed in the Standard Review Plan, have been adopted by the staff and included in the Technica1' Specifications for recently-licensed facilities.
In addition, the L
battery vendor, C&D Power Systems, Inc., has recomended the draft IEEE recossendations for the Cooper application. -Changes A,B &C have been reviewed 5
against.the IEEE draft criteria and have been determined to be conservative with respect to the criteria. The Staff also believes them to be conservative for the proposed use of the batteries at the Cooper Nuclear Station. Based on conformance to the IEEE Working Group's recommendations and to'the original L
licensing criteria, the licensee's proposed amendment is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
I The amendment involves a change in the installation or use of a facility component' located within the restricted area as defined in 10 CFR Part 20.
l The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may -
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be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forthin10CFRSection51.22(c)(9).Pursuantto*10CFR51.22(b),noenvironmental i
impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
1 (1) there is reasonable assurance that the health and safety of the l
will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations, l
and the issuance of the amendment will not be inimical to the common defense and security or to the health and ' safety of the public.
Date: May 24, 1989 Principal Contributor: Paul W. O'Connor L-____-____-__