ML17289A870

Amend 110 to License NPF-21,deleting Battery Load Profiles from TS

ML17289A870
Person / Time
Site:	Columbia
Issue date:	09/18/1992
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML17289A872	List: ML17289A870 ML17289A874
References
NUDOCS 9209290311
Download: ML17289A870 (10)

Text

gp,R Rf(Iy P

+4 0~i 0O (i

Cy

+~

gO W**y+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 110 License No.

NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Washington Public Power Supply, System (licensee) dated April 4,

1991, and supplemented by letters dated April 6,

1992, June 25,

1992, and July 16,

1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; 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; 2.

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.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-21 is hereby amended to read as follows:

92092903 ii 9209i 8 PDR ADOCK 05000397 P

PDR'

3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

110 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

This amendment is effective as of the date of issuance and must be fully implemented no later that 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Theodore R. quay, Director Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 18, 1992

f f

AMENDMENT NO.

ATTACHMENT TO LICENSE AMENDMENT TO FACILITY OPERATING ICENSE NO.

NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE 3/4 8-13 B 3/4 8-2 B 3/4 8-3 INSERT 3/4 8-13 B 3/4 8-2 B 3/4 8-3

I ELECTRICAL POWER SYSTEMS

~ SURVEILLANCE RE UIREMENTS (Continued d.

At least once per 18 months, during shutdown, by verifying that either:

1.

The battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for Divisions 1, 2 and 3 when the battery is subjected to a battery service test, or 2.

The battery capacity is adequate to supply a

dummy load (minimum amperage) based on anticipated loads required during loss of offsite power (LOOP) and loss-of-coolant accident (LOCA) conditions, while maintaining the battery terminal voltage greater than or equal to 21 volts for the +24-volt battery, 105 volts for the 125-volt battery, and 210 volts for the 250-volt

battery, and 105 volts for the 125-volt Div.

3 battery.

e.

At least once per 60 months during shutdown by verifying that the battery capacity is at least 80'83.4X for the 250 Volt battery) of the manufacturer's rating when subjected to a performance discharge test.

At this once per 60-month interval, this performance discharge test may be performed in lieu of the battery service test.

f.

At least once per 18 months during shutdown performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85K of the service life expected for the application.

Degradation is indicated when the battery capacity drops more than 10K of rated capacity from its average on previous performance tests, or is below 90K (93.4X for the 250 Volt battery) of the manufacturer's rating.

WASHINGTON NUCLEAR - UNIT 2 3/4 8-13 Amendment No.

N, 1i0

TABLE 4.8. 2. 1-1 BATTERY SURVEILLANCE RE UIREMENTS CATEGORY A(1)

CATEGORY B(2)

Parameter Electrolyte Level Float Voltage Specific Gravity(a)

Limits for each designated pilot cell

>Minimum level indication mark, and < 4" above maximum level indication mark

> 2.13 volts Limits for each connected cell

>Minimum level indication mark, and

< %" above maximum level indication. mark

> 2.13 volts(c)

> 1.195 Allowabl e(3) value for each connected cell Above top of

plates, and not overflowing

> 2.07 volts Not more than 0.020 below the average of all connected cells

> 1.200(b)

Average of all connected cells

> 1.205 Average of all connected cells

> 1.195(b)

(a)Corrected for electrolyte temperature.

Level correction will be used when-electrolyte level is outside the normal range.

(b)Or battery charging'urrent is less than (2) amperes when on float charge.

(c)May be corrected for average electrolyte temperature.

(1)For any Category A parameter(s) outside the limit(s) sho~n, the battery may be considered OPERABLE provided that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the Category B

measurements are taken and found to be within their allowable values, and provided all Category' and B parameter(s) are restored to within limits within the next 6 days.

(2)For any Category B parameter(s) outside the limit(s) shown, the battery may be considered OPERABLE provided that the Category B parameters are within their allowable values and provided the Category B parameter(s) are restored to within limits within 7 days.

(3)With any Category B parameter not within its allowable value declare the battery inoperable.

WASHINGTON NUCLEAR - UNIT 2 3/4 8-14 Amendment No.

6

3/4. 8 ELECTRICAL POWER SYSTEMS BASES 3/4.8. 1 3/4. 8. 2 and 3/4.8. 3 A. C.

SOURCES D. C.

SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribu-tion systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for (1) the safe shutdown of the facility and (2) the mitigation and control of accident conditions within the facility.

The minimum specified independent and redundant A. C.

and D. C.

power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.

The OPERABILITY of the power sources are con-sistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least Division 1 or 2 of the onsite A.C. and D.C.

power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. or D.C. source.

Division 3 supplies the high pressure core spray (HPCS) system only.

The A.C.

and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, "Availability of Electrical Power Sources,"

December 1974.

When diesel generator (1) or (2) is inoperable, there is an additional ACTION requirement to verify that all required systems, subsystems,

trains, components and devices, that depend on the remaining OPERABLE diesel generator (1) or (2) as a source of emergency power, are also OPERABLE.

This require-ment is intended to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function of critical systems during the period diesel generator (1) or (2) is inoperable.

The term verify as used in this context means to administratively check by examining logs or other information to determ'ine if certain components are out-of-service for maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the OPERABILITY of the component.

The OPERABILITY of the minimum specified A.C.

and D.C.

power sources and associated distribution systems during shutdown and refueling ensures that (1) the facility can be maintained in the shutdown or refueling condition for extended time periods and (2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.

The surveillance requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guide 1.9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"

March 10,

1971, Regulatory Guide 1.108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants,"

Revision 1, August 1977, and Regulatory Guide 1.137, "Fuel-Oil Systems for Standby Diesel Generators,"

Revision 1, October 1979.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 8"1

ELECTRICAL POWER SYSTEMS BASES A.C.

SOURCES D.C.

SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)

The diesel generator fast start surveillance requirements, based on a PRA

study, are sufficient to demonstrate the onsite A.C. power system capability to mitigate the consequences of the design basis event for the plant, i.e.,

large LOCA coincident with a loss-of-offsite power, while minimizing the mechanical stress and wear on the diesel engine.

The surveillance requirements for demonstrating the OPERABILITY of the unit batteries are in accordance with the recommendations of Regulatory Guide

1. 129, "Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants,"

February 1978, and IEEE Std 450-1980, "IEEE Recom-mended Practice for Maintenance,

Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.

The simulated emergency load profile used for the battery service test of Surveillance Requirement 4.8.2. l.d is verified to be at least equivalent to the actual emergency load profile and is based on anticipated operations required during loss-of-offsite power (LOOP) and loss-of-coolant accident (LOCA) conditions as described in the WNP-2 Final Safety Analysis Report (FSAR).

The simulated emergency load profiles for the batteries are defined and located in the FSAR Section 8.3.

Table 4.8.2. 1-1 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity.

The limits for the designated pilot cells float voltage and specific gravity, greater than 2. 13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity.

The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer s full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer s full charge specific gravity, ensures the OPERABILITY and capability of the battery.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 8-2 Amendment No. 110

ELECTRICAL POWER SYSTEMS BASER A.C.

SOURCES D.C.

SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (Continued)

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8.2.1-1 is permitted for up to 7 days.

During this 7-day period:

(1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its des>gn function.

3/4.8.4 ELECTRICAL E UIPMENT PROTECTIVE DEVICES Primary containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.

The surveillance requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturers brand of circuit breaker.

Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.

If a wide variety exists within any manufacturer's brand of cir-cuit breakers, it is necessary to divide.that manufacturer s breakers into groups and treat each group as a separate type of breaker for surveillance purposes.

The bypassing of the motor-operated valve thermal overload protection continuously or during accident conditions ensures that the thermal overload protection will not prevent safety-related valves from performing their function.

The surveillance requirements for demonstrating the bypassing of the thermal overload protection continuously and during accident conditions are in accordance with Regulatory Guide 1. 106 "Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.

WASHINGTON NUCLEAR " UNIT 2 B 3/4 8-3 Amendment No.

82, ii0