ML17059A224
| ML17059A224 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/02/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17059A223 | List: |
| References | |
| NUDOCS 9403100088 | |
| Download: ML17059A224 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 SAFETY EVA UATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT ON RE AT TO AMENDMEN
- 0. 55 TO FACILITY OPERATING ICENSE NO. NPF-69 AGARA MOHAWK POW CORPO ATION NIN MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 T.N
~IN NDDNDTIIIN By letter dated December 14,
- 1993, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear
- Station, Unit 2 (NHP-2), Technical Specifications (TSs).
The requested changes would revise TS 3/4.8.2, "DC Sources,"
to delete two notes that indicate that two 125-volt full capacity battery chargers are required when the Uninterruptible Power Supply (UPS) is powered by its backup DC power supply.
These notes apply to the Divisions I and II DC sources during operating and shutdown conditions.
The changes would also revise TS 3/4.8.2 to increase the minimum allowable electrolyte temperature for the 125-volt batteries from 60 'F to 65 'F.
The licensee also requested that administrative changes be made to TS 3/4.8.4, "Electrical Equipment Protective Devices,"
and the TS Bases.
- 2. 0 EVALUATION
- 2. 1 Deletion of Notes from TS 3 4.8.
The NHP-2 emergency 125-volt DC system consists of three physically separate, electrically independent DC power divisions corresponding to the three divisions of the onsite AC power system.
Each division feeds a separate load group through a separate distribution system.
Each division of the emergency DC system has its own battery, primary and backup battery chargers, switchgear, and distribution panels.
The Divisions I and II emergency batteries are designated 2BYS*BAT2A and 2BYS*BAT2B, respectively.
The Division I battery chargers are designated 2BYS*CHGR2A1 and 2BYS*CHGR2A2 and the Division II battery chargers are designated 2BYS*CHGR2B1 and 2BYS*CHGR2B2.
As stated in Section 8.3.2. 1.2 of the NHP-2 Updated Safety Analysis Report (USAR), each primary or backup battery charger is capable of supplying the largest combined steady-state loads on the battery while recharging the battery from the design minimum charge state to the fully charged state within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The Divisions I and II DC power sources supply backup power to plant emergency UPSs 2VBA*UPS2A and 2VBA~UPS2B, respectively.
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TS 3/4.8.2 currently requires that the Divisions I, II, and III DC power sources each have one 125-volt full capacity battery charger during operating and shutdown conditions.
Two notes in TS 3/4.8.2 further require that the Divisions I and II DC power sources each have two 125-volt full capacity battery chargers when the associated UPS is powered by its backup DC power supply.
The licensee has stated that these notes were placed in the TSs based on overly conservative load calculations that determined that two battery chargers were required to provide adequate power to a UPS and connected loads.
- However, more recent calculations have shown that the Divisions I and II battery chargers are each capable of recharging the.battery from the designed minimum charge to full charge in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined steady state DC loads, including a UPS.
The battery charger capability established by the more recent calculations is consistent with the regulatory position delineated in Regulatory Guide (RG) 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants."
The licensee requested that the two notes in TS 3/4.8.2 be deleted based on their deter-mination that only one battery charger is required to meet current design requirements and the criteria delineated in RG 1.32.
Based on the results of the licensee's more recent assessment of battery charger.capability and the consistency of this capability with RG 1.32, the staff has concluded that deletion of the subject notes from TS 3/4.8.2 is acceptable.
2.2 Chan e to Batter Electrol te Tem erature Re uirement in TS 3 4.8.
TS 3/4.8.2 currently requires that the 125-volt batteries be demonstrated to be operable by verifying that the average electrolyte temperature of one of five connected cells is above 60 'F.
The licensee has stated that current battery capacity calculations and the NHP-2 USAR assume an electrolyte temperature of 65 F.
Although the batteries can provide adequate voltage with an average electrolyte temperature of 60 F, battery capacity would be increased by raising the minimum temperature requirement to 65 'F.
The battery rooms are maintained at a temperature above 65 'F.
The licensee has requested that the requirement for minimum allowable electrolyte temperature be changed from 60 'F to 65 'F to improve the capacity of the batteries and establish consistency between the TSs,
- USAR, and applicable battery capacity calculations.
The staff has concluded that this proposed change will increase battery capacity and is, therefore, acceptable.
2.3 Administ tive Chan es to TS 3 4.8.4 TS 4.8.4.2.a.l currently requires that overcurrent protective devices be demonstrated operable by verifying that medium voltage 13.8-kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10X of the circuit breakers of each voltage level and performing specified channel calibrations and functional tests.
Since TS 4.8.4.2.a. I only delineates surveillance requirements for 13.8-kV circuit breakers, the words "of each
/
voltage level" are inappropriate.
The licensee has, therefore, proposed that these words be deleted from TS 4.8.4.2.a.l.
The staff has concluded that this proposed administrative change will clarify the surveillance requirement and is, therefore, acceptable.
2.4 Administrative Chan es to Bases for TSs 3 4.6.3 and 3 4.8.4 The Bases for TSs 3/4.6.3 and 3/4.8.4 currently make reference to Administrative Procedure AP-8.8, "List of Controlled Lists."
However, AP-8.8 has been superseded by Nuclear Interfacing Procedure NIP-DES-04.
The licensee has, therefore, proposed that the references to AP-8.8 be replaced with NIP-DES-04.
The Bases for TS 3/4.6.3 currently make reference to the "...maximum isolation times for the primary containment automatic isolation valves listed in the specification..."
The lists of primary containment isolation valves were removed from TS 3/4.6.3 via NHP-2 License Amendment No. 37.
The licensee
- has, therefore, proposed that the words "listed in this specification" be deleted from the Bases for TS 3/4.6.3.
The staff has concluded that the proposed changes to the Bases for TS 3/4.6.3 and 3/4.8.4 are administrative in nature and has no objections to these changes.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Yor k State official was notified of the proposed issuance of the amendment.
The State official 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 (59 FR 2868).
Accordingly, the amendment meets the eligibilitycriteria 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.
5.0 CONCLUSIO 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 Commission 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:
John E. Nenning Date:
March 2, 1994
Docket No. 50-410 March 2, 1994 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
H
SUBJECT:
ISSUANCE OF AMENDMENT FOR NINE MILE POINT NUCLEAR STATION, UNIT 2 (TAC NO. H88415)
The Commission has issued the enclosed Amendment No.
55 to Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Unit 2.
The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated December 14, 1993.
The amendment revises TS 3/4.8.2, "DC Sources,"
to delete two notes which indicated that two 125-volt battery chargers were required when the Uninterruptible Power Supply was powered from its backup DC power source.
These notes applied to the Divisions I and II DC sources during operating and shutdown conditions.
The amendment also revises TS 3/4.8.2 to increase the minimum allowable electrolyte temperature for the 125-volt batteries from 60 F to 65 F.
In addition, the amendment makes administrative changes to TS 3/4.8.4, "Electrical Equipment Protective Devices,"
and the TS Bases.
A copy of the related Safety Evaluation is enclosed.
A Notice of Issuance will be included in the Commission's next regular biweekly Federai
~Re ister notice.
Sincerely, Original signed by:
John E. Henning, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 55 to NPF-69 2.
Safety Evaluation cc w/enclosures:
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CBerlin er OGC PDI-1:D RACa ra OFFICIAL RECORD COPY FILENAME: G: iNMP2iNH288415.AMD
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