ML20034H228

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Amend 59 to License NPF-42,revising TS 4.8.1.1.2 by Removing Numerical Value of 1,352 Kw Associated W/Verification of EDG Capability to Reject Largest Single Load While Maintaining Required Voltage & Frequency
ML20034H228
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/08/1993
From: Black S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034H229 List:
References
NUDOCS 9303160205
Download: ML20034H228 (7)


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h o-UNITED STATES -

P NUCLEAR REGULATORY COMMISSION f

o WASHINGTON, D. C. 20535 l

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING' STATION

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DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE q

Amendment No.'59-1 License No. NPF-42 1.

The Nuclear Regulatory Comission (the Commission) has found that:

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A.

The application for amendment to the Wolf Creek Generating Station.

(the facility) Facility Operating License No. NPF-42 filed by the Wolf.

Creek Nuclear Operating Corporation (the Corporation), dated June 11, 1992, complies with the standards and requirements of-the Atomic Energy Act of 1954, as amended (the Act),-and the Commission's rules.

and regulations set forth in 10 CFR Chapter. I B.

The facility will operate in conformity with the' application, as amended, the provisions of the Act, and the rules and regulations ofl the Commission; C.

There-is reasonable assurance:

(1) 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; 7

D.

The issuance of this license amendment will not be inimical to the

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common defense and security or to the health and safety of the public; a

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 j

satisfied.

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O 9303160205 930308-PDR ADOCK 05000482 P

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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph.2.C.(2) of Facility Operating License No. NPF-42 is hereby i

amended to read as follows:

2.

Technical Specifications t

The Technical Specifications contained in Appendix' A, as revised i

through Amendment No.

59, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby-incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

1 3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

>za 0l W Suzanne. Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 8, 1993 t

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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 1

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

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

t REMOVE INSERT 3/4 8-4a 3/4 8-4a B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 B 3/4 8-2 i

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RECTRICALPOWERSYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

By sampling new fuel oil in accordance with ASTM D4057 prior to addition to storage tanks and:

(1) By verifying in accordance with the tests specified in ASTM D975-81 prior to addition to the storage tanks that the sample has:

(a) An API Gravity of within 0.3 degrees at 60 F or a specific gravity of within 0.0016 at 60/60 F, when compared to the supplier's certificate or an absolute specific gravity at 60/60 F of greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; (b) A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with the sup-plier's certification; (c) A flash point equal to or greater than 125 F; and (d) A clear and bright appearance with proper color when tested in accordance with ASTM D4176-82.

(2) By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM D975-81 are met when tested in accordance with ASTM D975-81 except that the analysis for sulfur may be performed in accordance with ASTM D1552-79 or ASTM D2622-82.

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At least once every 31 days by obtaining a sample of fuel oil in accordance with ASTM D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance I

with ASTM D2276-78, Method A.

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f.

At least once per 184 days the diesel generators shall be started

  • from ambient conditions (using the keep warm system) using one of the signals specified in 4.8.1.1.2a.4 and accelerated to at least 514 rpm in less than or equal to 12 seconds.

The generator voltage and frequency shall be 4160 + 160-420 volts and 60 i 1.2 Mz within 12 seconds after the start signal.

Subsequently verify thelgenerator-is loaded to an indicated 6000 to 6201 kW** in less than or equal to 60 seconds and operates at a load of 6000 to 6201 kW** for at least 60 minutes.

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  • This test shall be preceded by an engine prelube period so that the mechanical j

stress and wear on the diesel engine is minimized.

    • This band is meant as guidance to avoid routine overloading of the engine.

Loads in excess of this band for special testing under direct monitoring or momentary variations due to changing bus loads shall not invalidate this test.

Amendment 'No.

8 WOLF CREEK - UNIT 1 3/4 8-4

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) g.

At least once per 18 months, during shutdown, by:

1)

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2)

Verifying the diesel generator capability to reject the ESW pump motor load (the largest single emergency load) while maintaining voltage at 4160 + 160 - 420 volts and frequency at 60 1 5.4 Hz, 3)

Verifying the diesel generator capability to reject a load of 6201 kW without tripping. The generator voltage shall not exceed 4784 volts during and following the load rejection, 4)

Simulating a loss-of-offsite power by itself, and:

i a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses, and t

b)

Verifying the diesel starts *** on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected shutdown loads through the shutdown sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.

After energization, the steady-state voltage and frequency of the emergency i

busses shall be maintained at 4160 + 160 - 420 volts and 60 i 1.2 Hz during this test.

      • This test shall be preceded by an engine prelube period and/or other warmup procedures recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

WOLF CREEK - UNIT 1 3/4 8-4a Amendment No. 8, 59

o 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 The OPERABILITY of the A.C. and D.C power sources and associated distri-bution systems during operation ensures that sufficient power will be avail-able to supply the safety-related equipment required for:

(1) the safe shut-down of the facility, and (2) the mitigation and control of accident condi-tions 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 commen-surate with the level of degradation. The OPERABILITY of the power. sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during acci-dent conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source.

The A.C. source and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93,

" Availability of Electrical Power Sources", December 1974. When one diesel generator 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 as'a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. This requirement 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 one of the diesel generators is inoperable. The term verify as used in this context means to administratively check by examining logs or other information to determine 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 are 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 Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Sup-plies," Revision 1, November 1978,1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977 as modified by Amendment No. 8 issued on' May 29, 1987, and 1.137, " Fuel-0il Systems for Standby Diesel Generators,"

Revision 1, October 1979.

WOLF CREEK - UNIT 1 B 3/4 8-1 Amendment No; 59

ELECTRIC POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued) i Each diesel generator (DG) is provided with an engine overspeed trip to prevent damage to the engine. Recovery from the transient caused by the loss of a large load could cause diesel engine overspeed, which, if excessive, might result in a trip of the engine. The DG load response characteristics j

and capability to reject the largest single load without exceeding predetermined voltage and frequency are demonstrated while maintaining a specified margin to the overspeed trip as required by Regulatory Guide 1.9, Position C.4.

For meeting Surveillance Requirements, the largest single load l-is defined as a load equivalent to the ESW pump motor while under the full post-LOCA mode of operation.

The Surveillance Requirement for demonstrating the OPERABILITY of the Station batteries are based on the recommendations of Regulatory Guide 1,129,

" Maintenance Testing and Replacement of Large Lead Storage Batteries for i

Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended-Practice for Maintenance, Testing, and Replacement of Large Lead Storage Bat-teries for Generating Stations and Substations."

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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 j

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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 j

capacity.

Table 4.8-2 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.

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-2 is permitted for up to j

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 allewable 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 2

individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.

WOLF CREEK - UNIT 1 B 3/4 8-2 Amendment No. 59 l

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