ML20137D611
| ML20137D611 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/24/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137D589 | List: |
| References | |
| NUDOCS 9703260236 | |
| Download: ML20137D611 (3) | |
Text
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t UNITED STATES I
NUCLEAR RF.GULATORY COMMISSION f
WASHINGTON, D.C. 20665-4001 nl SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.189 4
q TO FACILITY OPERATING LICENSE NO. DPR-16 l
l GPU NUCLEAR CORPORATION AND
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JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
By letter dated November 27, 1996, the GPU Nuclear Corporation (the licensee) submitted a request for changes to the Oyster Creek Nuclear Generating Station Technical Specifications (TSs). The requested amendment would change the acceptance criteria for the individual cell voltage from 2.0v to 2.09v, change the surveillance frequency for battery specific gravities to implement the recomendations of IEEE 450-1995, delete surveillance requirement 4.7.B.4.d, j
and add a clarifying phrase "while on a float charge..." where appropriate.
During the refueling outage 14R of Oyster Creek in 1992, GPU replaced the B station battery with a round-cells low-specific gravity AT&T (now Lucent Technologies) battery. The acceptance criteria for the existing battery individual cell voltage of 2.0 volts do not reflect the recommendation of the j
manufacturer Lucent Technologies; therefore, GPU is requesting the TS changes.
i Additionally, the frequency of the specific gravities surveillance of the battery would be revised to reflect the recommendations of IEEE 450-1995,
" Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications."
J TS 4.7.B.4.d. related to battery low voltage annunciators verification every 24 months would be deleted as present TS battery inspection and testing I
requirements are adequate to verify battery o'perability and condition.
2.0 EVALUATION 4
In its submittals, GPU confirmed that the new round-cell low-specific gravity battery installed during Refueling Outage 14R at Oyster Creek has adequate capacity for future load. The usual individual cell voltage (ICV) on a ficat charge for this battery is 2.2 volts. However, the manufacturer recommends the low limit of the ICV to be 2.09 volts while on float charge.
This value i
is higher than the existing 2.0 ICV in the TS. The 2.09 volts limit would l
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. require actions at a voltage higher than the present TS and it is therefore more conservative. The staff finds this change acceptable.
The present TS requires r,uarterly verification of the specific gravity of each cell and recording the temperature of each fifth cell. The requested change is to test and record quarterly the specific gravity and temperature of every tenth cell. The TS change reflects the sampling of the cells as recommended by IEEE 450-1995, and therefore, the staff finds this change acceptable.
The existing TS 4.7.B.4. requires that at least one.e per 24 months during shutdown certain tests be performed to verify the battery ca)acity.
Subsection (d) of TS 4.7.B.4 also requires verification of t te battery annunciators low voltage pickup and reset values. The licensee is requesting removal of this annunciator surveillance. The present voltage indication in the control room and the existing and revised TS are adequate to verify the operability of the battery. Specifically, low voltage indication and alarm functions in the control room are still maintained to alert the operators of malfunction, and battery capacity is verified by periodic tests.
Therefore, the staff finds the deletion of TS 4.7.B.4.d acceptable.
The Basis section did not require an update to effect this TS change.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official l
was notified of the proposed issuance of the amendment. The State official i
had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC 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 be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. 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 (62 FR 6576). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Saba N. Saba Date: March 24, 1997 i
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