ML20127P531

Amend 145 to License DPR-35,revising TS SRs for Station Batteries by Replacing Rated Load Discharge Test W/Svc Discharge Test once-per-cycle & Performance Discharge Test Every Five Yrs

ML20127P531
Person / Time
Site:	Pilgrim
Issue date:	01/25/1993
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127P497	List: ML20127P496 ML20127P531 ML20127P543
References
NUDOCS 9302010310
Download: ML20127P531 (7)

Text

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"[  % UNITED STATES

. _gh-k NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20S65 '

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BOSTON EDISON COMPANY DOCKET NO. 50-293 PILGRIM NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 License No. DPR-35

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for amendment filed by the Boston Edison Company (the licensee) dated August 10, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

W the Commission's rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity wi.h 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 inis amendment can be conducted without endangering the health and that such activities will be conducted safety of the with in compliance public, and (ii) ion's regulations set forth in 10 CFR the Commiss Chapter I; D. The issuance of this amendment will not be inimical to the cummon 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.

2. Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-35 is hereby amended to read as follows: ,

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9302010310 930325 PDR ADOCV 05000293 p FDR

Technical Specifications The Technical 5,acifications contained in Appendix A, as revised through Amendment No.145 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION-Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 25, 1993 m

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ATTACHMENT TO LICENSE AMENDMENT NO.145 FACILITY OPERATING LICENSE _NO.-DDR-31 DOCKET NO. 50-293 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical. lines indicating the area of change.

Remove IDHE1 195 195 196 196- -

201 201 s

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, LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A AUXILIARY ELECTRICAL EOUIPMENT 4.9.A AUXILIARY _ ELECTRICAL EQUIPMENT (Cont'd) SURVEILLANCE (Cont'd)

4. 4160 voit buses A5 and A6 are d. Once a month the quantity of energized and the associated 480 diesel fuel available shall volt buses are energized. be logged.

5. The station and switchyard 125 and e. Once a month a sample of 250 volt batteries are operable. diesel fuel shall be checked Each battery shall have an for quality in accordance operable battery charger. with ASTM D40d7-81 or D4177-82. The quality shall

6. Emergency Bus Degraded Voltage be within th6 acceptable Annunciation System as specified limits specified in Table 1 in Table 3.2.a.1 is operable, of ASTM D975-81 and logged.

7. Soecification 2. Station and Switchyard Batteries Two redundant RPS Electrical a. Every week the specific Protection Assemblies (EPAs) shall gravity, the voltage and be operable at all times on both temperature of the pilot cell inservice power supplies, and overall battery voltage shall be measured and logged.

Action

b. Every three months the

a. With one EPA on an inservice measurements shall be made of power supply inoperable, voltage of ecch cell to continued operation is nearest 0.1 volt, specific permissible provided that the gravity of each cell, and EPA is returned to operable temperature of every fifth status or power is transferred cell. These measurements to a source with two operable shall be logged.

EPAs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this requirement cannot be met, trip c.. Once each operating cycle, the power source. the stated batteries shall be subjected to a Service

b. With both RPS EPAs found to be Discharge Test (load inoperable on an inservice profile). The specific power supply, continued gravity and voltage of each -

operation is permissible, cell shall be determined provided at least one EPA is after the discharge and restored to operable status or logged.

power is transferred to a source with at least one d. Once every five years,-the operable EPA within 30 stated batteries shall be minutes. If this requiremer.t subjected to a Performance cannot be met, trip the power Discharge Test (capacity).

source. This test will be performed in lieu of the Service NOTE: Only applicable if tripping the Discharge Test requirement of power source would not result in a 4.9.A.2.c above.

scram.

195 -

Amendment No. 42, 67, 96, 127, 145 l

a LIMITING CONDITION FOR' OPERATION SURVEILLANCE REOUIREMENI$'

3.9.B Ooeration with Inocerable 4.9.A Auxiliary Electrical Enuinment Eauineent Surveillana (Cont'd)

Whenever the raactor is in Run 3. Emergency 4160V Buses AS-A6 Mode or-Startup Mode with the Degraded Voltage Annunciation reactor not in a Cold Condition, System.

the availability of electric power shall be as specified in 3.9.B.1, a. Once each operating cycle, 3.9.B.2, 3.9.B.3, 3.9.B.4, and calibrate the alarm sensor.

3.9.B.5.

b. Once each 31 days perform a

1. From and after the date that channel functional test on incoming power is not available the alarm system.

from the startup or shutdown transformer, continued reactor , c. In the event the alara system o operation is permissible under is determined inoperable this condition for seven days. under 3.b above, commence During this period, both diesel logging safety related bus generators and associated voltage every 30 minutes emergency buses must be untti such time as the alarm demonstrated to be operable. is rer,tored to operable status.

2. From and after the date that incoming power is not available 4. RPS Electrical Protection from both startup and shutdown Assemblies transformers, continued operation is permissible, provided both a. Each pair of redundant RPS -

diesel generators and associated EPAs shall be determined to emergency buses are demonstrated be operable at least once per ,

to be operable, all core and 6 months by performance of an containment cooling systems are instrument fenctional test.

operable, reactor power level is reduced to 25% of design and the b. Once per operating cycle, NRC is notified within one (1) each pair of redundant RPS hour as required by 10CFR50.72. EPAs shall be determined to be operable by performance of

3. From and after the date that one an instrument calibration and.

of the diesel generators or by verifying tripping of the associated emergency bus is made circuit breakers upon the or found to be inoperable for any simulated conditions for reason, continued reactor automatic actuation of the operation is permissible in protective relays within the accordance with Specification following limits:

3.5.F if Specification 3.9.A.1 and-3.9.A.2.a are satisfied. Overvoltage i 132 volts Undervoltage 1 108 volts'

4. From and after the date that one Underfrequency 1-57Hz of the diesel generators or associated emergency buses and either the shutdown or startup transformer power source are made 1

196 Amendment No. 88, 127, 145

l PJJLS: (Cont'd) 4.9 deliver fulI flow. Periodic testing of the various components, plus a functional test once per cycle, is sufficient to maintain adequate reliability.

Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type of surveillance described in this specification has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

The Service Discharge Test provides indication of the batteries' ability to satisfy the design requirements (battery duty cycle) of the associated de system. This test will be performed using simulated or actual loads at the rates and for the duration specified in the design load profile. A once per cycle testing interval was chosen to coincide with planned outages.

The Performance Disch3rge Test provides adequate indication and assurance that the batteries have the specified ampere hour capacity. The results of these tests will be logged and compared with the manufacturer's recommendations of acceptability. This test is performed once every five years in lieu of the Service Discharge test that would normally occur within that time frame.

The diesel fuel oil quality must be checkod to ensure proper operation of the '

diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine.

The electrical protection assemblies (EPAs) on the RPS inservice power supplies, either two motor generator sets or one motor generator and the alternative supply, consist of protective relays that trip their incorporated circuit breakers on overvoltage, undervoltage, or underfrequency conditions.

There are two EPAs in series per power source. It is necessary to periodically test the relays to ensure the sensor is operating correctly and to ensure the trip unit is operable. Based on experience at conventional and nuclear power plants, a six-month frequency for the channel functional test is established. This frequency is consistent with the Standard Technical Specifications.

The EPAs of the power sources to the RPS shall be determined to be operable by performance of a channel calibration of the relays once per operating cycle. During calibration, a transfer to the alternative power source is required; however, prior to switching to alternative feed, de-energization of the applicable MG set power source must be accomplished. This results in a half scram on the channel being calibrated until the alternative power source is connected and the half ecram is clearei. Based on operating experience, drift of the EPA protective relays is not significant. Therefore, to avoid possible spurious scrams, a calibration fraquency of once per cycle is established.

Amendment No. 127, 135, 141, 145 201 3 1