Text

Amend 101 to License NPF-42,revising TS 3/4.8.1, Electric Power Sys AC Sources & Associated Bases to Achieve Overall Improvement in EDG Reliability & Availability
	ML20116M005
Person / Time
Site:	Wolf Creek
Issue date:	08/09/1996
From:	Stone J; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20116M009	List: ML20116M005; ML20116M013;
References
	NUDOCS 9608190246
	Download: ML20116M005 (27)
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4 UNITED STATES g

j NUCLEAR REGULATORY COMMISSION

't WASHINGTON. G.c. fA61 l

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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. NPF-42 1.

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

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No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated July 29, 1994, which was superseded by letter dated September 15, 1995, and supplements dated March 8, 1996, April 18, 1996, June 14, 1996, and July 12, 1996, complies with the standards and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 of the Commission; C.

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the healtn and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license 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.

9608190246 960809 PDR ADOCK 05000482 P

PDR i

i O

2.

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

)

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101, 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 4

the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3.

The license amendment is effective as of its date of issuance and shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION

~

James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 9, 1996 i

1 ATTACHMENT TO LICENSE AMENDMENT N0.101 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with

-the attached pages. The revised pages are identified by Amendment number and 1

contain marginal lines indicating the areas of change. The corresponding

' overleaf pages are also provided to maintain document completeness.

REMOVE INSERT l

XI XI l

3/4 8-1 3/4 8-1 i

3/4 8-la 3/4 8-la l

3/4 8-2 3/4 8-2 l

3/4 8-3 3/4 8-3 l

3/4 8-4 3/4 8-4 3/4 8-4a l

3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6 3/4 8-6a 3/4 8-7 3/4 8-7 3/4 8-8 3/4 8-8 8 3/4 8-1 B 3/4 8-1 B 3/4 8-2 B 3/4 8-2 8 3/4 8-3 B 3/4 8-3 B 3/4 8-4 B 3/4 8-5 B 3/4 8-6 6-18 6-18 6-18a 6-18a 6-18b 6-18b 6-18c 1

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

SECTION EAGE l

PLANT SYSTEMS (Continued) 3/4.7.10 DELETED l

l TABLE 3.7-3 DELETED i

3/4.7.11 DELETED 3/4.7.12 AREA TEMPERATURE MONITORING..............................

DELETED TA8LE 3.7-4 AREA TEMPERATURE MONITORING...........................

DELETED l

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................

3/4 8-1 1

TABLE 4.8-1 DELETED I

l Shutdown.................................................

3/4 8-8 3/4.8.2 D.C. SOURCES 0perating................................................

3/4 8-9 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.....................

3/4 8-11 Shutdown.................................................

3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating................................................

3/4 8-13 Shutdown.................................................

?/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES l

i Containment Penetration Conductor Overcurrent Protective Devices.....................................

DELETED t

1

[

4 WOLF CREEK - UNIT 1 XI Amendment No.15,30,tt,89,101

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION f%E 3/4.9 REFUELING OPERATIONS l

3/4.9.1 BORON CONCENTRATION......................................

3/4 9-1 l

3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 1

3/4.9.3 DECAY TIME...............................................

3/4 9-3 l

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4 i

l 3/4.9.5 COMMUNICATIONS...........................................

DELETED l

3/4.9.6 REFUELING MACHINE........................................

DELETED l

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY...............

DELE.TED l

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level.........................................

3/4 9-9 l

Low Water Level..........................................

3/4 9-10 l

3/4.9.9 CONTAINMENT VENTILATION SYSTEM...........................

3/4 9-11 3/4.9.10 WATER LEVEL - REACTOR VESSEL F u e l A s s embl i e s..........................................

3/4 9-12 Control Rods............................................

DELETED l

3/4.9.11 WATER LEVEL - STORAGE POOL..............................

3/4 9 3/4.9.12 SPENT FUEL ASSEMBLY ST0 RAGE..............................

3/4 9-15 FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2........................................

3/4 9-16 3/4.9.13 EMERGENCY EXHAUST SYSTEM.................................

3/4 9-17 l

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WOLF CREEK - UNIT 1 XII Amendment No. 89

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. S0yBC15 OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be i

OPERABLE:

Two physically independent circuits between the offsite transmission a.

network and the Onsite Class IE Distribution System, and b.

Two separate and independent diesel generators, each with:

i l

1)

A separate day tank with a minimum fuel oil free surface elevation of 86 inches from the bottom (outside diameter) of l

the tank, 2)

A separate Fuel Oil Storage System containing a minimum volume of 85,300 gallons of fuel, and 3)

A separate fuel transfer pump.

APPLICABILITY: MODES 1, 2, 3, and 4.

)

ACTION:

a.

With an offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining l

offsite A.C. source by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

Restore at least two l

offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN l

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the offsite A.C. sources by performing Specification 4.8.1.1.1 within I har and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Specification 4.8.1.1.2a.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , unless the absence of any potential common mode failure for the remaining diesel generator l

1s demonstrated, or if the diesel generator became inoperable due to j

l any cause other than an inoperable support system, an independently testable componant, preplanned preventive maintenance.or testing, or maintenance to correct a condition which, if left uncorrected, would i

not affect the OPERABILITY of the diesel generator; restore the i

inoperable diesel generator to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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WOLF CREEK - UNIT 1 3/4 8-1 Amendment No. *,*2,^',101 i

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Specification 4.8.1.1.1 within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and Specification 4.8.1.1.2a.4* within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months on the redundant diesel generator, unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated, or if the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, preplanned preventive maintenance or testing, or maintenance to correct a condition which, if left uncorrected, would not affect the OPERABILITY of the diesel generator; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore the remaining A.C.

electrical power source (offsite circuit or diesel generator) to OPERABLE in accordance with Specification 3.8.1.1. ACTION a. or ACTION b. as applicable with the time requirement for the ACTION based on the time of the initial loss of the remaining inoperable A.C. electrical power source. A successful test of diesel generator OPERABILITY performed in accordance with Specification 4.8.1.1.2a.4*

under this ACTION for an OPERABLE diesel generator or a diesel generator that was restored to OPERABLE, satisfies the subsequent testing requirement of Specification 3.8.1.1 ACTION b. for an OPERABLE diesel generator.

d.

With one diesel generator inoperable in addition to ACTION b. or c.

above, verify that:

1.

All required systems, subsystems, trains, components, and de, ices that depend on the remaining OPERABLE diesel ger.erator as a source of emergency power are also OPERABLE, and

The automatic start and sequence loading of a diesel generator satisfies the testing requirements of Specification 4.8.1.1.2a.4 for this Action Statement.

WOLF CREEK - UNIT 1 3/4 8-la Amendment No. 8,101

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued)

~

2.

When in MODE 1, 2, or 3, the steam-driven auxiliary feedwater pump is OPERABLE.

If these conditions are not satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

e.

With two of the above required offsite A.C. circuits inoperable, restore at least one of the inoperable offsite sources to OPERABLE I

status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Following restoration of one offsite A.C. electrical power source, follow ACTION a. above with the time requirement of ACTION

a. based on the time of the initial loss of the remaining inoperable offsite A.C. electrical power source.

l f.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Specification 4.8.1.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Following restoration of one diesel generator follow ACTION b. with the time requirement of the ACTION based on the time of initial loss of the remaining inoperable diesel generator. A successful test of diesel generator operability performed in accordance with Specification 4.8.1.1.2a.4 under this ACTION for the OPERABLE diesel generators, satisfies the subsequent testing requirement of Specification 3.8.1.1 ACTION b.

g.

With one or more diesel generators with new fuel oil properties outside the required Diesel Fuel Oil Testing Program limits, following the addition of new fuel 011* to the Diesel Fuel Oil Storage Tanks, restore the stored fuel oil properties to within the required limits within 30 days.

h.

With one or more diesel generators with stored fuel oil total particulates outside the required Diesel Fuel Oil Testing Program limits, restore the fuel oil total particulates within the required limits within 7 days.

SURVEILLANCE RE0VIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class IE Distribution System shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

i

The properties of API Gravity, specific gravity or an absolute specific gravity; kinematic viscosity; water and sediment content; and flash point shall be confirmed to be within the Diesel Fuel Oil Testing Program limits, prior to the addition of new fuel oil to the Diesel Fuel Oil Storage Tanks.

WOLF CREEK - UNIT 1 3/4 8-2 Amendment No. 8,101

1 l

ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) l 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by:

l a.

1)

Verifying the fuel oil transfer pump starts on low level in the day tank standpipe, 2)

Verifying the fuel level in the fuel storage tank, 3)

Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank, 4)

Verifying the diesel starts ** and obtains a voltage of 4160 + 160 - 420 volts, and a frequency of 60 i 1.2 Hz. The diesel generator can be slow started and allowed to reach rated speed at a rate that is selected to minimize stress and wear.

5)

Verifying the generator is synchronized, gradually loaded to an indicated 5580 to 6201 kW*** for at least 60 minutes, and until temperature equilibrium is attained.

The rate of loading and unloading of the generator during this test should be gradual, based upon minimizing stress and wear on the diesel generator, and 6)

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses, b.

At least once per 31 days by checking for and removing accumulated water from the day tanks; At least once per 31 days by checking for and removing accumulated c.

water from the fuel oil storage tanks;

- 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.

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

Loads outside of this band for special testing under direct monitoring or j

momentary variations due to changing bus loads shall not invalidate this test.

WOLF CREEK - UNIT 1 3/4 8-3 Amendment No. 8,94,101

.-.y ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

By verifying fuel oil properties of new fuel oil are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.

By verifying fuel oil properties of stored fuel oil are tested in e.

accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.

f.

At least once per 184 days verify each diesel generator starts from standby conditions

and achieves in less than or equal to 12 seconds, a voltage of 4160 + 160 -_420 volts, and a frequency of 60 i 1.2 Hz using one of the following signals:

1)

Manual, or 2)

Simulated loss-of-offsite power by itself, or 3)

Safety injection test signal.

g.

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

1)

Verifying each diesel generator operating at a power factor between 0.8 and 0.9 does not trip on overspeed and voltage does not exceed 4784 volts and frequency does not exceed 65.4 Hz following a load rejection of 5580 to 6201 kW,**

2)

Verifying on an actual or simulated loss-of-offsite power signal (LOOP)**:

a)

De-energization of emergency buses; b)

Load shedding of emergency buses; c)

The diesel generator auto-starts from standby conditions *** and:

1) energizes permanently connected loads within 12

seconds, 2) energizes the auto-connected shutdown loads through the shutdown sequencer, 3) maintains steady state voltage at 4160 + 160 - 420

volts, This test shall be preceded by an engine prelube period so that the mechanical stress and wear on the diesel engine is minimized.

- This surveillance shall not be performed in Modes I or 2 and credit may be taken for unplanned events that satisfy this requirement.

- - 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 8-4 Amendment No. 8769,101

I ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4)

maintains steady state frequency at 60 i 1.2 Hz, and 5) operates for greater than or equal to 5 minutes while the generator is. loaded with the shutdown loads.

3)

Verifying on an actual or simulated Safety Injection Actuation Signal (SIAS)** that each diesel generator auto-starts from the standby condition

and:

a) achieves a voltage of 4160 + 160 - 420 volts in less than or equal to 12 seconds after the auto-start signal; b) achieves a frequency of 60 1 1.2 Hz in less than or eoual to 12 seconds after the auto-start signal; c) operates on standby for greater than or equal to 5 minutes; d) the offsite power source energizes the auto-connected (accident) loads through the LOCA sequencer.

i 4)

Verifying on a simulated loss-of-offsite power in conjunction with a simulated Safety Injection Actuation Signal (SIAS)**

that each diesel generator auto-starts from the standby condition

and:

a) achieves a voltage of 4160 + 160 - 420 volts in less than or equal to 12 seconds after the auto-start signal; b) achieves a frequency of 60 i 1.2 Hz in less than or equal to 12 seconds after the auto-start signal; c) de-energization of the emergency busses and load shedding from the emergency busses; d) energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected emergency (accident) loads through the LOCA sequencer; e) operates for greater than or equal to 5 minutes while its 9enerator is loaded with emergency loads.

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.

- This surveillance shall not be performed in Modes 1 or 2 and credit may be taken for unplanned events that satisfy this requirement.

WOLF CREEK - UNIT 1 3/4 8-5 Amendment No. 8,101

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 5)

Verifying each diesel generator's automatic trips are bypassed upon the simulated SIAS and LOOP combined test ** except:

a)

High jacket coolant temperature; b)

Engine overspeed; c)

Low lube oil pressure; d)

High crankcase pressure; e)

Start failure relay; f)

Generator differential current.

6)

Verifying full-load carrying capability of the diesel generator at a power factor between 0.8 and 0.9 for an interval of not less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 5580 to 6201 kW (indicated)**. Verify the diesel generator operates for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded to an indicated 6600 to 6821 kW if auto connected loads increase above 6201 kW.

The generator voltage and frequency shall be maintained within 4160 + 160 - 420 volts and 60 i 1.2 Hz during this test;****

7)

Verifying the diesel generator's hot restart capability by operating the diesel generator for greater than or equal to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at an indicated load of 5580 to 6201 kW, shutting down the diesel generator and restarting it within 5 minutes. On restart, the diesel generator voltage and frequency shall be 4160 + 160 - 420 volts and 60 i 1.2 Hz within 12 seconds after the start signal; 8)

Verifying the diesel generator's capability *** to:

l a)

Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b)

Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

This surveillance shall not be performed in Modes 1 or 2 and credit may be taken for unplanned events thtt satisfy this requirement.

- - This surveillance shall not be performed in Modes 1, 2, 3, or 4 and credit may be taken for unplanned events that satisfy this requirement.

- - - 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.

WOLF CREEK - UNIT 1 3/4 8-6 Amendment No. 8,101

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ELECTRICAL POWER SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 9)

Verifying that with the diesel generator operating in a test l

mode, connected to its bus, a simulated Safety Injection signal overrides the test mode by:

(1) returning the diesel generator to standby operation and (2) automatically energizing the emergency loads with offsite power;

10) Verifying that the fuel transfer pump transfers fuel from each l

fuel storage tank to the day tank of each diesel via the installed cross-connection lines; and

11) Verifying that the automatic LOCA and Shutdown sequence timer l

1s OPERABLE with the interval between each load block within i 10% of its design interval.

h.

At least once per 10 years or after any modification which could affect diesel generator interdependence, verify that when started simultaneously from standby conditions,** each diesel generator achieves in less than or equal to 12 seconds, a voltage of 4160 +

160 - 420 volts and a frequency of 60 i 1.2 Hz.

i.

At least once per 10 years by:

1)

Draining each fuel oil storage tank, 2)

Removing the accumulated sediment, 3)

Cleaning the tank to remove microbiological growth.

- 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.

WOLD CREEK - UNIT 1 3/4 8-7 Amendment No. 8 60,101 7

O ELECTRICAL POWER SYSTEMS 1

A.C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the Onsite Class IE Distribution System, and j

b.

One diesel generator with:

1)

A day tank with a minimum fuel oil free surface elevation of 86 inches from the bottom (outside diameter) of the tank, 2)

A fuel storage system containing a minimum volume of 85,300 gallons of fuel, and 3)

A fuel transfer pump.

APPLICABILITY: MODES 5 and 6.

ACTION:

1 With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the spent fuel pool.

In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1 and 4.8.1.1.2 (except for Specification 1

4.8.1.1.2a.5)).

l WOLF CREEK - UNIT 1 3/4 8-8 Amendment No. 0,02,M,101

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3/4.8 ELECTRICAL POWER SYSTEMS

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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 j

and are based upon maintaining at least one redundant set of onsite A.C. ano 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 I

depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump i

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 administrative 1y check by examining logs or other information to determine if certain i

components are out-of-service for maintenance or other reasons.

It does not i

mean to perform the Surveillance Requirements needed to demonstrate the j

OPERABILITY of the component.

l 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 l

for extended time periods, and (2) sufficient instrumentation and control capability are available for monitoring and maintaining the unit status.

When determining compliance with action statement requirements, addition i

to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive reactivity change.

The surveillance requirements of Technical Specification 3/4.8.1 are l

based upon, in part, the guidance of Generic Letter 94-01, " Removal of l

Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators from Plant Technical Specifications," Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," Regulatory Guide 1.9, " Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class IE Onsite Electrical Power Systems at Nuclear Power Plants," Revision 3, and WOLF CREEK - UNIT 1 B 3/4 8-1 Amendment No. 0,59,55,101 November 22, 1993

i ELECTRICAL POWER SYSTEMS l

4 j

BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTIOG (Continued) 4 j

NUREG-1431, " Standard Technical Specifications - Westinghouse Plants." Also, 1

the guidance of NUMARC 87-00, " Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," Revision 1, and Regulatory Guide 1.160 has been adopted to formulate a comprehensive j

Emergency Diesel Generator Reliability Program.

1 i

Technical Specification 3.8.1.1, Action b and c, require, in part, the demonstration of the operability of the remaining operable emergency diesel generator by performing Technical Specification 4.8.1.1.2a.4.

This test is required to be completed regardless of when the inoperable emergency diesel 1

generator is restored to operable status unless the emergency diesel generator j

was declared inoperable to do preplanned preventative maintenance, testing, or maintenance to correct a condition which, if left uncorrected, would not l

affect the operability of the emergency diesel generator. The requirement to

{

test the remaining operable emergency diesel generator when one emergency l

diesel generator is inoperable is limited to those situations where the cause j

for inoperability cannot be conclusively demonstrated in order to preclude the i

potential for common mode failures. The test is not required to be accomplished if the emergency diesel generator was declared inoperable due to an inoperable support system or an independently testable component. When such a test is required, it is required to be performed within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of

{

having determined that the emergency diesel generator is inoperable.

Technical Specification 4.8.1.1.2a.4 is considered to be a " Start Test" l

as described in Regulatory Guide 1.9, Revision 3.

A " Start Test" is performed to demonstrate proper startup from standby conditions and to verify that the required design voltage and frequency is attained.

For these tests, d

Regulatory Guide 1.9, Revision 3, recommends that the emergency diesel generators be slow started and allowed to reach rated speed on a prescribed j

schedule that is selected to minimize stress and wear.

l Regulatory Guide 1.9, Revision 3, considers Technical Specification i

4.8.1.1.2a.5 to be a " Load-Run Test". A " Load-Run Test" demonstrates 90 to 1

100 percent (5580 to 6201 kilowatts) of the continuous rating (6201 kilowatts) of the emergency diesel generator for an interval of not less than I hour and until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of a diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.

Regulatory Guide 1.9, Revision 3, corsiders Technical Specification 4.8.1.1.2b to be a " Fast-Start Test". A ' ast-Start Test" demonstrates that each emergency diesel generator starts from standby conditions.

If a plant normally has in operation keep wars systems designed to maintain lube oil and jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant.

Verification that the emergency diesel generator reaches required voltage and frequency within acceptable limits and time is also required.

WOLF CREEK - UNIT 1 B 3/4 8-2 Amendment No.101

C ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)

The requirements of the " Single-Load Rejection Test" and the " Full-Load Rejection Test" as described in Regulatory Guide 1.9, Revision 3 have been costbined. The " Full-Load Rejection Test" is a demonstration of the emergency diesel generator's capability to reject a load equal to 90 to 100 percent of its continuous rating (5580 to 6201 kilowatts) while operating at a power factor between 0.8 and 0.9 and that the voltage does not exceed 4784 volts and that the frequency does not exceed 65.4 Hertz following a load rejection of 5580 to 6201 kilowatts. The frequency criteria is from the " Single-Load Rejection Test" and is based on nominal engine speed plus 75 percent of the difference between nominal speed and the over-speed trip setpoint.

In addition, through a plant procedure, the ESW pump starting transient during the LOCA sequencing test, Technical Specification 4.8.1.1.2.g.4.d, will be demonstrated to be within a minimum voltage of 3120 Vac and recover to 3680 Vac within 3 seconds and to be within a maximum voltage of 4784 Vac and recover to 4320 Vac within 2 seconds. This acceptance criteria is based on Regulatory Guide 1.9, Revision 3, section 1.4 and past trending of ESW pump starting transient performance.

j i

The note that will not allow a surveillance requirement to be performed in Modes 1 or 2 is based on the improved Standard Technical Specifications (NUREG-1431) which recognizes that the performance of certain surveillance requirements during operation with the reactor critical could cause i

perturbations to the electrical distribution systems that could challenge continued steady state operation and, as a result, unit safety systems.

However, this note does not preclude operating the emergency diesel generator with the reactor critical, as necessary, to support operational conditions.

The design of the diesel generator fuel oil system is unique in that the day tanks include a standpipe mounted on the top of each tank. The day tanks are sized to supply a minimum of one hour's worth of fuel for the diesel generators while running at their continuous rating plus a 10 percent margin (per ANSI N195-1976, " Fuel Oil Systems for Standby Diesel-Generators").

However, early in the design phase it.was discovered that the diesel 9enerators injection headers were located at an elevation above that of the i

day tanks.

This would have caused the headers to drain back to the day tank, instead of remaining full, while in the standby mode.

The diesel generators are required to start and load within 12 seconds of receiving the start signal. The diesel generators can be depended upon to meet this operability requirement as long as the supply piping to the injector pumps remains full at all times. Maintaining the day tank fuel oil level above the highest component in the engine fuel oil system will result in a positive pressure being applied throughout the system. This will assure the entire fuel oil system will be maintained full at all times. Thus, the standpipes were added to the day tanks, allowing the day tank level to be raised above the elevation of the injection headers. Since this required level of fuel oil is elevation-dependent, instead of volume-dependent, LCOs 3.8.1.lb.1) and 3.8.1.2b.1) reflect the required elevation of fuel oil (i.e., oil level) from the bottom of the tank, instead of specifying a volume amount (i.e., gallons) of fuel oil.

Performing Surveillance Requirement 4.8.1.1.2a.1) causes the transfer WOLF CREEK - UNIT 1 B 3/4 8-3 Amendment No. 69 94,101 7

ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued) l pump to start on low tank level and refill the day tank to the pump shutoff setpoint.

Pump start and stop setpoints are set to ensure the oil level remains in the standpipe, thus verifying that the oil level has been maintained above the minimum required oil level since the last surveillance or diesel generator run.

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 Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended 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.

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 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 design function.

WOLF CREEK - UNIT I B 3/4 8-4 Amendment No. 20,00,04,101 j

^

- - - - ~

~

ELECTRICAL POWER SYSTEMS i

BASES t

A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued) t DIESEL FUEL OIL TESTING PROGRAM In accordance with Technical Specification 6.8.4, a Diesel Fuel Oil Testing Program to implement required testing of both new fuel oil and stored fuel oil shall be established.

For the intent of this specification, new fuel oil shall represent diesel fuel oil that has not been added to the Diesel Fuel 011 Storage Tanks. Once the fuel oil is added to the Diesel Fuel Oil Storage Tanks, the diesel fuel oil is considered stored fuel oil, and shall meet the Technical Specification requirements for stored fuel oil.

Tests listed below are a means of determining whether new fuel oil is of the appropriate grade and has not been contaminated with substances that would have an immediate detrimental impact on diesel engine combustion.

If results from these tests are within acceptable limits, the new fuel oil may be added to the storage tanks without concern for contaminating the entire volume of fuel oil in the storage tanks. These tests are to be conducted prior to adding the new fuel to the storage tanks, but in no case is the time between receipt of the new fuel oil and conducting the tests to exceed 30 days. The tests, limits, and applicable ASTM standards being used to evaluate the condition of new fuel oil are:

1.

By sampling new fuel oil in accordance with ASTM D4057 prior to addition to storage tanks and; 2.

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 supplier's certification; c)

A flash point equal to or greater than 125*F; and d)

A water and sediment content of less than or equal to 0.05% when tested in accordance with ASTM D1796-83.

Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the Limiting Condition for Operation of Technical Specification 3.8.1.1, since the new fuel oil has not been added to the diesel fuel oil storage tanks.

WOLF CREEK - UNIT 1 B 3/4 8-5 Amendment No.101 l

i ELECTRICAL POWER SYSTEMS BASES i

A.C. SO'JRCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued) i l

Within 30 days following the initial new fuel oil sample, the fuel oil is i

analyzed to establish that the other properties specified in Table 1 of ASTM i

D975-81 are met, when tested based on ASTM D975-81, except that the analysis i

j for sulfur may be performed in accordance with ASTM D1552-79, ASTM D2622-82, or ASTM D4294-90.

If the sulfur analysis is performed using ASTM D129 (as

]

specified by ASTM D975-81), ion chromatography may be used as an alternative l

to the gravinetric analysis.

In the event the correct fuel oil properties are l

not met, Action g provides an additional 30 days from the time that it is j

determined that the correct fuel oil properties are not met to meet the Diesel Fuel Oil Testing Program limits. The additional 30 day period is acceptable l

t l

because the fuel oil properties of interest, even if they are not within i

limits, would not have an immediate effect on emergency diesel generator l

operation. The diesel fuel oil surveillance in accordance with the Diesel Fuel Oil Testing Program will ensure the availability of high quality diesel 1

j fuel oil for the emergency diesel generators.

i j

At least once every 31 days, a sample of fuel oil is obtained from the j

storage tanks in accordance with ASTM D2276-83. The particulate contamination i

is verified to be less than 10 mg/ liter when checked based on ASTM D2276-83, 1

Method A.

The filter size for the determination of particulate contamination will be 3.0 micron instead of 0.8 micron as specified by ASTM D2276-83. The i

{

filtered amount of diesel fuel oil will be approximately one liter when possible. Also, it is acceptable to obtain a field sample for subsequent j

laboratory testing in lieu of field testing.

s l

Fuel oil degradation during long term storage shows up as an increase in particulate, due mostly to oxidation. The presence of particulate does not mean the fuel oil will not burn properly in a diesel engine.

The particulate can cause fouling of filters and fuel oil injection equipment which can cause engine failure.

The frequency for performing surveillance on stored fuel oil is based on stored fuel oil degradation trends which indicate that particulate concentration is unlikely to change significantly between surveillances.

3/4.8.4 DELETED i

WOLF CREEK - UNIT 1 B 3/4 8-6 Amendment No.101 l

ADMINISTRATIVE CONTROLS e

L PROCEDURES AND' PROGRAMS (Continued) l e.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably

achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Lirnitations on the operability of radioactive liquid and gaseous l

monitoring instrumentation including surveillance tests and j

setraint determination in accordance with methodology in the

ODCM, l

2)

Lititations on the concentrations of radioactive material released in licuid effluents to UNRESTRICTED AREAS conforming to 10 CFR Eart 20, Appendix E, Table II, Column 2,

.)

l'onitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, l

4)

Limitations on the annual and quarterly doses or dose commitment to a MEMEER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions frort radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)'

Limitations of the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Tab)e II, Column 1, l

l i

i j

(

WOLF CREEK - UNIT 1 6-17 Amendment No. 42 l

l

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS.(Continued) 1 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER 0F THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

f.

Radioloaical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the j

highest potential exposure pathways, and (2) verification of the i

accuracy of the-effluent monitoring program and modeling of environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2)' conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1)

Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM.

2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and the modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

g.

Diesel Fuel Oil Testina Proaram A diesel fuel oil testing program to implement required testing of j

both new fuel oil and stored fuel oil.

The program shall include sampling and testing requirements, and acceptance criteria, in i

accordance with the applicable ASTM Standard. The purpose of the program is to establish the following:

a.

Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1.

an API gravity or an absolute specific gravity within

limits, i

2.

a flash point within limits for ASTM 2D fuel oil, WOLF CREEK - UNIT 1 6-18 Amendment No. '2,"O,07,101

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 3.

a kinematic viscosity within limits for ASTM 2D fuel oil; 4.

a water and sediment content within the limits for ASTM 2D j

fuel oil; b.

Other properties for ASTM 2D fuel oil are within limits within 30 days following sampling and addition of new fuel oil to storage tanks when tested based on ASTM 0975; and Total particulate concentration of the stored fuel oil is < 10 c.

mg/ liter when tested every 31 days based on ASTM D2276, Method A.

h.

Emeroency Diesel Generator Reliability Proaram An emergency diesel generator reliability program that establishes the requirements and guidelines for emergency diesel generator reliability, availability, and monitoring. The program shall include the -lollowing:

Eme"gency diesel generator reliability performance goals a.

(target reliability) based upon the station blackout coping assessment. Target reliability goal monitoring is accomplished through monitoring methods that are based upon those described in Appendix D of NUMARC 87-00.

b.

Measures to ensure detailed root cause analysis of emergency diesel generator failures is performed and effective corrective actions are taken in response to failures.

Implementation of an emergency diesel generator preventive c.

maintenance program that is consistent with the Maintenance Rule, and d.

Mor.itoring of emergency die::e1 generator availability and performance parameters to ensure the target reliability is met or exceeded.

i.

Containment Leakaae Rate Testina Proaram A program shall be established to implement the ieakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design i

basis loss of coolant accident, P., is 48 psig.

(

t WOLF CREEK - UNIT 1 6-18a Amendment No. 89W,101

I ADMINISTRATIVE CONTROLS

.(

l PROCEDURES AND PROGRAMS (Continued)

The maximum allowable containment leakage rate, L, at P, shall be 0.20% of containment air weight per day.

Leakage rate acceptance criteria are:

l a.

Containment leakage rate acceptance criterion is s 1.0 L l

Duringthefirstunitstartupfollowingtestinginaccor$.

1 ance with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and C tests and s 0.75 L, for Type A tests; b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0.05 L, when tested at 2 P,;

2)

For each door, leakage rate is s 0.005 L, when pressurized to 2 10 psig.

The provisions of Technical Specification 4.0.2 do not apply to the l

test frequencies specified in the Containment Leakage Rate Testing i

Program.

The provisions of Technical Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

6.8.5 a.

Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the WASTE GAS HOLDUP SYSTEM, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

1.

The limits for concentrations of hydrogen and oxygen in the WAS'E GAS HOLDUP SYSTEM and a surveillance program to ensure the limits are maintained.

2.

A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than the amount that would result in a whole body exposure of 20.5 rem to any individual in an UNRESTRICTED AREA in the event of an uncontrolled release of the tanks' l

contents, consistent with Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases due to Waste Gas System Leak or Failure."

i WOLF CREEK - UNIT 1 6-18b Amendment No. 89p,101 I

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGBN11 (Continued) 3.

A surveillance program to ensure that the quantity of I

radioactivity contained in following outdoor liquid I

radwaste tanks that are not surrounded by liners, dikes, l

or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains l

connected to the liquid radwaste system, is'less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface l

water supply in an UNRESTRICTED AREA, in the event of an uncontrolled release of the tank's contents.

l a.

Reactor Makeup Water Storage Tank, b.

Refueling Water Storage Tank, l

c.

Condensate Storage Tank, and l

d.

Outside Temporary tanks, excluding demineralizer vessels and the liner being used to solidify radioactive waste.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable to the Explosive Gas and Storage Tank R&dioactivity Monitoring i

Program surveillance frequencies.

b.

Reactor Coolant Pump Flywheel Inspection Program l

Each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, dated August 1975.

c.

Containment Tendon Surveillance Program l

This program provides controls for monitoring tendon performance, including the effectiveness of the tendon corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial plant operation as well as periodic testing thereafter.

The Containment Tendon Surveillance Program, and its inspection frequencies and acceptance criteria, shall be in accordance with Wolf Creek Generating Station position on draft Revision 3 of Regulatory Guide 1.35 dated April 1989.

The provisions of Specifications 4.0.2 and 4.0.3 are applicable t

to the Containment Tendon Surveillance Program inspection frequencies.

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS l

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the 4

Regional Administrator of the NRC Regional Office unless otherwise noted.

I 89 97,101 l

WOLF CREEK - UNIT 1 6-18c Amendment No.

7

ML20116M005

Text

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