ML20039B709

Proposed Tech Specs Re Electrical Power Sys to Accomplish NUREG-0313,Revision 1 Objectives

ML20039B709
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/08/1981
From:	DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20039B703	List: ML20039B702 ML20039B709
References
RTR-NUREG-0313, RTR-NUREG-313 NUDOCS 8112230452
Download: ML20039B709 (44)

Text

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3.0 APPLICABILITY SURVEILLANCE REQUIREMENTS - (Cont'd) 3.0.7 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25% of the surveillance interval.

b.

A total maximum combined interval time for any 3 con-secutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

3.0.8 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

Surveillance Requirements do not have to be performed on inoperable equipment or on equipment not required to be OPERABLE.

3.0.9 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

3.0.10 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2,

& 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and 7alves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

8112230452 811208 PDR ADOCK 05000409 P PDR a

3.0 ' APPLICABILITY SURVEILLANCE REQUIREMENTS - (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice Terminology for' inservice in-inspection and testing spection-and testing activities activities-Weekly At least once per 7 days Monthly At_least once per 31 days Quarterly or every 3 months At least once per 92 days-Semiannually or;every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366: days c.

The provisions of Specification 3.0.7 are applicable to the above required frequencies for performing inservice in-spection-and testing activities.

d.

Performance of the above inservice inspection and testing activities shall be in addition to-other specified

-Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

f.

Inservice inspection of all non-conforming service sensitive lines, identified per NUREG-0313, shall be performed ~at 36-month intervals' (plus or minus by as'much' as '12 months) co-inciding with a refueling or other outage.

In'the event these examinations reveal no unacceptable indications within three successive inspections, the schedule may revert to i

l examinations per Specifications 5.3.1, with the exception

^

j that the required examinations should be completed during l

each 80-month period.

I' 3.0.11 All replacement of and repairs to ASME Code Class 1, 2, and 3 lines shall conform to the guidelines stated in the NUREG-0313, Rev.

1,

" Technical Report on Material Selection and Processing Guide-lines for BWR Coolant Pressure Boundary Piping", July 1980.

1 i ir 1

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3.0 APPLICABILITY BASES - (Continued) 3.0.10 This specification ensures that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50, Section 50.55a.

Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of_the frequencies of performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applic-able addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for per-forming the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive require-ments of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

For example, the requirements of Specification 3.0.9 to perform surveil-lance activities prior.to entry into an OPERATIONAL CONDITION-or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Ccde provision which allows pumps to be tested up to one week after return to normal operation.

And, for example, th,e Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of per-forming its specified function is declared inoperable and tukes precedence over the ASME Boiler and Pressure Vessel Provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

3.0.11 This specification insures that replacement piping and re -

pairs to ASME Code Class 1, 2, and 3 lines conform to the guidelines stated in NUREG-0313, Rev.

1,

" Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping",

July 1980.

Application of these guidelines will help reduce inter-

' granular-stress corrosicn cracking (IGSCC) susceptibility.

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4.0 OPERATING LIMITATIONS 4.0.1 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved.

When these terms appear in capitalized type, the following definitions apply in these Technical Specifications.

AC" ION ACTION shall be ise additional requirements specified as corollary statements to each principle specification and shall be part of the specifications.

AVERAGE PLANAR EXPOSURE The AVERAGE PLANAR EXPOSURE shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

AVERAGE PLANAR LINEAR HEAT GENERATION RATE The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy'to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the quclitative assessment of channel be-havior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indicating and/or status derived from independent instrument channels measuring the same parameter.

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-l i

'l 14 ~.1 GENERAL 4.1.3 During periods.when the reactor is in Condition 3,'4, or 5,

.either Channel 1 or 2 of the Nuclear Instrumentation System shall be in operation and shall be monitored by the operator.

4.1.4 Whenevu..he reactor contains;one or more fuel elements, any operati'ons from points outside the control room of-equipment which

.may affect the reactor shall be conducted under the direction, or with the knowledge,'of the control room operator.

4.1.5 If the plant is operational during a tornado warning, the

. Shift Supervisor on duty.shall keep informed of the actual tornado activity which may approach the plant.

In the event that reports

' indicate an. imminent tornado strike at or near the LACBWR' plant,

-the' Shift Supervisor shall reduce reactor power to a level which permits.promptLreduction of power generation to station load.

However, the Shift-Supervisor shall be instructed to discontinue plant' operation if, in his judgment, this action is required to ensure plant safety.

4.2.1 Reactor-Building 4.2.1.1 CONTAINMENT INTEGRITY shall be maintained-in~ Conditions 1,

2, 3 and during:

(a)

CORE ALTERATIONS, (b) handling of irradiated fuel, or (c) there is fuel in the reactor and any control rod is withdrawn. i

9 9

4.2 OPERATIONS LIMIOS 4.2.2.18 The low pressure coolant injection system shall be available for automatic operation except at times when the reactor is shut down and the system depressurized to approximately atmospheric pressure.

Manual valves in this system shall be locked in that position which will not impair system capability when automatic operability is required.

4.2.2.19 The shutdown condenser system shall be available for auto-matic operation except at times when the reactor is shut down and the primary system depressurized to app _oximately atmospheric pressure.

Manual valves in the shutdown condenser system shall be locked in that position which will not impair system capability when automatic oper-ability is required.

4.2.2.10 The condition of low accumulator pressure in the hydraulic valve accumulator system whall be corrected within a maximum time of one hour following annunciation in the control room or the reactor shall be shut down.

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 4.2.2.21 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

IDENTIFIED and UNIDENTIFIED LEAKAGE AS SHOWN below:

Max. Allowable Area Source Leakage - GPM Lower Reactor IDENTIFIED 0.04 Cavity UNIDENTIFIED 0.01 l

Forced Circulation IDENTIFIED 2.0 l

Pump Cubicles UNIDENTIFIED 0.5 i

Balance of IDENTIFIED 4.0 Containment Bldg.

UNIDENTIFIED 1.0 c.

2 gpm increase in UNIDENTIFIED LEAKAGE within any 24-hour period.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION - (Continued)

ACTION:

a.

With any PRESSURE BOUNDARY -LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

With any reacuor coolant system leakage greater than the limits in b. and/or c. above, reduce the leakIge rate to within the limits within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

With any reactor coolant system leakara greater than the limit in c. above, identify the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 5.2.2.21 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by monitoring a. below and at least one of b.,

c.,

or d.

a.

Monitoring the Containment Building retention tank level at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

Monitoring the containment Builoing forced circulation pump cubicle and the reactor vessel cavity atmospheric particulate radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

Monitoring the Containment Building atmospheric gaseous radioactivity at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION - (Continued)

ACTION - (Cont'd) b.

With one electrical feed from 2400-volt bus 1A or 1B to the associated essential switchgear bus inoperable and with diesel generator lA or 1B inoperable, demonstrate the OPERABILITY-of the remaining A.C.

sources by performing Sur-veillance Requirements 5.2.10.1.1.a and 5.2.10.1.2.a.4 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore both electrical feeds and both diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

With the above required c rcuit between the offsite trans-i mission network and the onsite power distribution system inoperable and/or with the electrical feeds from both 2400-volt buses 1A and IB to the associated essential switchgear buses inoperable, demonstrate the OPERABILITY of diesel generators 1A and 1B by performing Surveillance Requirement 5.2.10.1.2.a.4 within one hour and at leaat once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, unless the diesel generators are already oper-ating; restore the required circuit between the offsite trans-mission network and the onsite power distribution system and at least one electrical feed from either 2400-volt bus to the associated essential switchgear bus to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With only one electrical feed from a 2400-volt bus restored, restore the electrical feeds from both 2400-volt buses to the associated essential switchgear buses to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d.

With diesel generators 1A and 1B inoperable, demonstrate the l

OPERABILITY of the circuit between the offsite transmission network and the onsite power distribution system and the electrical feeds from 2400-volt buses 1A and 1B to the associated essential switchgear buses by performing Surveil-lance Requirement 5.2.10.1.1.a within one hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or l'e in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Re-sto s both diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> tr*m time of initial loss or be in HOT SHUTDOWN within the next 12 hairs and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l

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4.2.3 ELECTRICAL POWER SYSTEMS 4.2.3.1 A.C.

SOURCES A.C.

SOURCES-OPERATING LIMITING CONDITIONS FOR OPERATION 4.2.3.1.1 As a minimum, the following A.C.

electrical power sources shall be OPERABLE:

a.

The physically independent circuit between the offsite transmission network and the onsite: power distribution system, with a separate electrical feed from:

1.

2400-volt bus 1A to 480-volt essential switchgear bus 1A, and 2.

2400-volt bus 1B to the Diesel Building 480-volt essential switchgear bus 1B.

b.

Two separate and independent diese,1 generators, 1A and 1B, each with:

1.

A separate day tank containing a minimum of 80 gallons of fuel for diesel generator 1A and 170 gallons for diesel generator 1B.

2.

A separate fuel storage tank containing a minimum of 200 gallons of fuel for diesel generator lA and 2500 gallons for diesel generator 1B.

3.

A separate fuel transfer pump.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 AND 2 ACTION:

a.

With either one electrical feed from 2400-volt bus 1A or 1B to the associated essential switchgear bus inoperable or with diesel generator 1A or 1B inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirements 5.2.10.1.1.a and 5.2.10.1.2.a.4 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter; restore both electrical feeds and both diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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O

4 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 5.2.10.1.1 The physically independent circuit between the offsite transmission network and the onsite power distribution system and the electrical feeds from 400-volt bus lA and 1B to the associated essential switchgear bus shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and b.

Demonstrated OPERABLE at least once per 18 months by transferring, manually, and automatically, unit power supply from the main feed to the reserve feed.

5.2.10.1.2 Each diesel generator shall be demonstrated OPERABLE:

a.

In accordance with the frequency specified in Table 5.2.10.1.2-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank.

2.

Verifying the fuel level in the fuel storage tank.

3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel generator starts from ambient condition, and is up to rated bus voltage in less than or equal to 10 seconds.

5.

Verifying the diesel generator is loaded with the design test load and operates for greater than or equal to 60 minutes.

6.

Verifying the diesel generator is aligned to provide erergency power to the associated essential buses.

b.

At least once per 92 days by verifying that a sample of diesel fuel from within 3 inches from the bottom of each fuel storage tank, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water, and sediment.

c.

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 manu-facturer's recommendations for this class of standby service.

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J

ELECTRICAL POWER SYSTEMS

' SURVEILLANCE REQUIREMENTS - (Continued) 2.

Verifying _the diesel generator capability to reject a load greater than or equal to 41 }ae load on diesel generator 1A and greater than or' equal to 50 kw on diesel generator 1B without tripping.

3.

Verifying that on an ECCS actuation test signal,-without-loss of offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes.

4.

Simulating a loss of offsite power in' conjunction with an emergency core cooling system actuation test signal, and:

a)

Verifying de-energization of the essential switch--

gear buses associated with diesel generators 1A and IB, and load shed 'ing from the _ essential-switchgear bus associated with diesel generator 1B.

b)

Verifying the diesel generator starts from ambient

~

condition on the auto-start signal, energizes the essential switchgear bus with permanently connected loads, and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads, c)

Verifying that all diesel generator 1B trips, except engine overspeed, overcrank, and generator differ-ential, are automatically bypassed upon loss of voltage on_the essential bus.

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS-- (Continued) 5.

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The diesel generator shall be loaded 1 41 kw for diesel generator 1A and 1 50 kw for diesel generator 1B.

Within 5 minutes after completing this 24-hour test, repeat Specification. 5.2.10.1.2.c.3.

6.

Verifying that all available loads to each diesel generator do not exceed the continuous load rating of 250 kw for diesel generator 1A and 400 kw for diesel generator IB.

d.

At least once per 10 years or after any modifications which could affect diesel generator interdependence, by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators are up to rated voltage in less than or equal to 10 seconds.

5.2.10.1.3 The starting and control power battery and battery charger of each diesel generator shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each battery is above the

plates, 2.

The pilot cell specific gravity, corrected to 77 F and normal electrolyte level, is greater than or equal to 1.180, and has not decreased more than 0.04 from the value observed during the previous test, and 3.

The overall battery voltage is greater than or equal to 24 volts for diesel generator IA and greater than or equal to 32 volts for diesel generator IB.

b.

At least once per 18 months by verifying that:

1.

The batteries, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.

The battery-to-battery terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

32k (1)

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS - (Continued) 5.2.10.1.4 Reports - All diesel generator failures, valid or non-valid, shall be reported to the Commission pursuant to Specification 6.9.1.

If the number of failures in the last 100 valid tests, on a per nuclear unit basis, is greater than or equal to 7, the report shall be supplemented to include the additional information recom-mended in Regulatory Position c.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

32k(2)

TABLE 5.2.10.1.2-1 DIESEL GENERATOR TEST SCHEDULE Number of Failures in Last 100 Valid Tests

• Test Frequency

< 1 At least once per 31 days 2

At least once per 14 days 3

At least once per 7 days-

> 4 At least once per 3 days

• Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the last 100 tests are determined on a per nuclear unit basis.

For the purposes of this test schedule, only valid tests conducted after the issuance date of Amendment No. (

) shall be included in the computation of the "last 100 valid tests".

Entry into this test schedule shall be made at the 31 day test frequency.

1

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.)

ELECTRICAL POWER SYSTEMS A.C.

SOURCES-SHUTDOWN LIMITING CONDITION FOR OPERATION 4.2.3.1.2 As a minimum, the following A.C.

electrical power sources shall be OPERABLE:

a.

The physically independent circuit between the offsite transmission network and the onsite power distribution system and at least one electrical feeder from 2400-volt bus 1A or 1B energizing either, but not-both, essential switchgear buses.

b.

Diesel generator 1A or 1B, aligned to, but not energizing, the same essential switchgear bus, with:

1.

A day tank containing a minimum of 80 gallons of fuel for diesel generator 1A or 170 gallons of fuel for diesel generator 1B.

2.

A fuel storage system containing a minimum of 200 gallons of fuel for diesel generator 1A or 2500 gal?.ons of fuel for diesel generator IB.

3.

A fuel transfer pump.

APPLICABILITY:

OPERATIONAL CONDITIONS 3, 4, AND 5.

ACTION:

With less than the above required A.C.

electrical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS, irrad-iated fuel handling, positive reactivity changes or operations that have the potential of draining the reactor vessel until at least the minimum required power sources are OPERABLE.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.10.2 At least the above required A.C.

electrical power sources shell be determined OPERABLE per Surveillance Requirements 5.2.10.1.1.a, 5.2.10.1.2, 5.2.10.1.3, and 5.2.10.1.4, except for the l

requirement of 5.2.10.1.2.a.5.

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ELECTRICAL POWER SYSTEMS 4.2.3.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 4.2.3.2.1 The following A.C.

electrical buses shall be OPERABLE and energized from sources of power other than the diesel gener-ators with tie breakers open between redundant buses:

a.

480-Volt A.C.

Essential Switchgear Bus lA.

b.

480-Volt A.C. Diesel Building Essential Switchgear Bus 1B.

c.

120-Volt A.C. Non-Interruptible Bus lA.

d.

120-Volt A.C. Non-Interruptible Bus 1B.

e.

120-Volt A.C. Turbine Building Regulated Bus, f.

120-Volt A.C.

1 KVA Static Inverter from Generator Plant 125-Volt D.C.

Bus.

APPLICABILITY:

OPERATIONAL CONDIT79NS 1 AND 2.

ACTION:

a.

With one of the above required A.C.

distribution system buses incperable, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With two or more of the above required A.C. distribution system buses inoperable, restore at least all except one of the inoperable buses to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore all of the above required A.C.

distribution system-buses to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 5.2.11.1.

The above required A.C. distribution system buses shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

I

- 32m -

l

ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 4.2.3.2.2 As a minimum, the following A.C.

electrical buses shall be OPERABLE and energized from sources of power other than a diesel generator but aligned to an OPERABLE diesel generator, a.

480-Volt Essential Switchgear Bus lA or 480-Volt Diesel Building Essential Switchgear Bus 1B.

b.

120-Volt A.C. Non-Interruptible Bus lA.

c.

120-Volt A.C.

Non-Interruptible Bus 1B.

d.

120-Volt Turbine Building Regulated Bus.

APPLICABILITY:

OPERATIONAL CONDITIONS 3, 4,

5 and*

ACTION:

With less than the above required A.C.

distribution system buses OPERABLE,' establish CONTAINMENT INTEGRITY and suspend all operations i

involving CORE ALTERATIONS, irradiated fuel handling or operations I

that have the potential of draining the reactor vessel within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 5.2.11.2 At least the above required A.C.

distribution system buses-shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignment and indicated power availability.

• When handling irradiated fuel or a spent fuel shipping cask in the Containment Building.

- 32n -

ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - OPERATING LIMITING CONDITIONS FOR OPERATION 4.2.3.2.3 The following D.C.

buses shall be energized and OPERABLE with the tie breakers between buses open:

a.

Reactor Plant 125-volt D.C. bus, a full capacity charger, and a 125-volt battery bank, b.

Generator Plant 125-volt D.C. bus, a full capacity charger, and a 125-volt battery bank, and c.

Diesel Building 125-volt D.C. bus, a full capacity charger, and a 125-volt battery bank.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 AND 2 ACTION:

With one of the above required 125-volt D.C.

buses inoperable, restore the inoperable bus to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 5.2.11.3.1 Each of the above required D.C.

distribution system buses shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignment and indicated power availability.

5.2.11.3.2 Each 125-volt battery bank and charger shall be demon-strated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.

2.

The pilot cell specific gravity, corrected to 77 F and normal electrolyte level, is greater than or equal to 1.200, 3.

The pilot cell voltage is greater than or equal to 2.0 volts, and 4.

The overall battery voltage is greater than or equal to 120 volts.

- 32o -

)

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS - (Continued) b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is greater than or equal to 2.0 volts under float charge and has not de-creased more than 0.3 volts from the value observed during the original acceptance test, 2.

The specific gravity, corrected to 77 F, of each con-nected cell is greater than or equal to 1.200 and has l

not decreased more than 0.04 from tha value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

c.

At least once per 18 months by verifying that:

1.

The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration.

2.

The cell-to-cell and terminal connections.are clean, tight, free of corrosion and coated with anti-corrosion material.

3.

The Reactor Plant battery charger will supply at least 15 amps, the Diesel Building battery charger will supply at least 50 amps, and the Generator Plant battery charger will supply at least 7 amps at greater than or equal to 120' volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

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

1.

The battery capacity is adequate to supply and maintain in OPERABLE status a dummy load equal to or greater than all of the emergency loads or all of the actual emergency loads for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> when the battery is subjected to a battery service test.

2.

At the completion cf the above test, the battery charger shall be demonstrated capable of recharging its battery while supplying normal D.C.

loads.

The battery shall be charged to at least 90% capacity in less than or equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, e.

At least once per 60 months during shutdown by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to performance discharge test.

This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery capacity test of d.1 and d.2 aoove.

- 32p -

J

1 m

4 J

.I ELECTRICAL' POWER SYSTEMS

- D.C.' DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION H

4.2.3.2.4 As a minimum, the Diesel Building 125-volt D.C. bus with the Diesel Building.125-volt battery bank and' charger shall be 4

OPERABLE:

APPLICABILITY:

OPERATIONAL CONDITIONS 3, 4, 5, and *.

i

' ACTION:

I a.

With less than the above required Diesel Building 125-volt D.C. bus-OPERABLE, establish CONTAINMENT INTEGRITY and-I suspend all operations that could decrease the shutdown j

margin, or operations that have the potential for draining the reactor vessel within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.. CORE ALTERATIONS may j.

-continue.

b.

Restore the Diesel Building 125-volt D.C. bus to OPERABLE i

status within 7 days or cease CORE ALTERATIONS.

c.

The provisions'of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.11.4.1 The Diesel Building 125-volt D.C. bus shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignment and indicated power availability.

5.2.11.4.2 The Diesel Building 125-volt bus battery bank and charger shall be determined OPERABLE per Surveillance Requirement l-5.2.11.3.2.

a 3

• When handling irradiated fuel or a spent fuel shipping cask in the

~

Containment Building.

- 32q -

i I

L' l

~

ELECTRICAL POWER SYSTEMS A.C.

DISTRIBUTION - INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4.2.3.3.1 The Essential Bus instrumentation channels of Table 4.2.3.3-1 shall be OPERABLE with their trip set points set consistent with the values shown in the Trip Set Point Column of Table 4.2.3.3-2.

APPLICABILITY:

As shown in Table 4.2.3.3-1.

ACTION:

As shown in Table 4.2.3.3-1.

SURVEILLANCE REQUIREMENTS 5.2.11.5 Each Essential Bus instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST at the frequency shown in Table 5.2.11.3-1.

- 32r -

TABLE 4.2.3.3-1 A.C.

DISTRIBUTION--UNDERVOLTAGE INSTRUMENTATION l

l MINIMUM APPLICABLE TRIP FUNCTION AND TOTAL NO.

CIIANNELS CIIANNELS OPERATIONAL FUNCTIONAL UNITS OF CHANNELS TO TRIP OPERABLE CONDITIONS

• ACTION Loss of Power a.

440V Essential 2/ Bus 1/ Bus 2/ Bus 1,

2, 3

1 Bus Undervoltage (Undervoltage relays phases A and C) l b.

440V Essential 3/ Bus **

2/ Bus 2/ Bus 1,

2, 3

2 l

w l

y Bus Undervoltage (Undervoltage D!

relays phases A, B and C)

Required when engineered safety equipment is required to be >.merable.

To be effective only after unit is modified 3o have 3 channels per bus.

TABLE 4.2.3.3 (Continued)

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE require-ment, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; except that one channel may be bypassed up to two hours for surveillance testing or maintenance provided that:

a.

The other channel is OPERABLE, and b.

The time during which redundant protection is not provided shall not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 30-day interval.

ACTION 2 With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within one hour.

- 32r(3)

TABLE 5.2.11.3-1 A.C.

DISTRIBUTION--UNDERVOLTAGE INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CGi4DITIONS TRIP FUNCTION AND CHANNEL FUNCTIONAL CHANNEL FOR WHICH FUNCTIONAL UNITS CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Loss of Power a.

440V Essential Bus NA R

NA 1,

2, 3

Undervoltage (Under-voltage relays phases A and C)

Iw b.

440V Essential Bus **

NA M

R 1,

2, 3

Undervoltage (Under-g; voltage relays 7

phases A, C and C)

• • To be effective only after unit is modified to have 3 channels per bus.

TABLE 4.2.3.3-2 A.C.

DISTRIBUTION--UNDERVOLTAGE INSTRUMENTATION TRIP VALUES TRIP FUNCTION AND FUNCTIONAL UNITS TRIP SETPOINT Loss of Power a.

440V Essential Bus 88.3 < 93 < 97.6 ) Volts Undervoltage (Under-voltage relays phases

- 2 < 2.1 ) Seconds, Time Delay 1.9 <

A and C)

I L>

b.

440V Essential Bus **

95 < 100 < 105

) Volts Undervoltage (Under-2 voltage relays phases

- 9.9

) Seconds, Time Delay 8.1 < 9 A, B and C)

• • To be effective only after unit is modified to have 3 channels per bus.

PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 4.2.18.2 The following spray and/or sprinkler systems shall be OPERABLE:

a.

The turbine lube oil reservoir.

b.

The turbine lube oil storage room.

c.

The ACS valve area.

d.

The main and auxiliary transformers, e.

1A diesel generator room.

f.

Electrical Penetration area.

APPLICABILITY:

Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE.

ACTION:

a.

With the above required spray and/or sprinkler system inoperable, establish a continuous fire watch with back-up fire suppression equipment for the unprotected area (s) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.18.2 The above required spray and/or sprinkler system shall be demonstrated OPERABLE:

a.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

b.

At least once per 18 months:

1.

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct positions, and

- 37g -

PLANT SYSTEMS I

SURVEILLANCE REQUIREMENTS - (Continued) b)

Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2.

By inspection of the spray headers to verify their integrity, and 3.

By inspection of each nozzle to verify no blockage, j

1 l

l l

l 1

l l -

I

- 37h -

PLANT SYSTEMS CHEMICAL EXTINGUISHING LIMITING CONDITIONS FOR OPERATION 4.2.18.3 The chemical extinguishing systems located in the follow-

'ing areas shall be OPERABLE:

a.

12 Emergency Diesel Generator, with a minimum of 4 high pressure CO2 bottles weighing at least 190 pounds-each, b.

Electrical equipment room, with a minimum of 1 Halon 1301 bottle weighing at least 270 pounds.

APPLICABILITY:

Whenever equipment in the chemical extinguishing protected areas is required to be OPERABLE.

ACTION:

a.

With either of the above required chemical extinguishing systems inoperable, establish a continuous. fire watch with backup fire suppression equipment for the unprotected areas within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the system to OPERABLE status within 14 days or, in lieu of any-other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2'within the next 30 days outlining the action taken,~the cause of-the inoperability.and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not-applicable.

SURVEILLANCE REQUIREMENTS 5.2.18.3 Each of the above required chemical extinguishing systems shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying tank weight.

of each of the required bottles, and pressure of Halon bottle.

b.

At least once per 18-months by verifying each. system,'

including associated ventilation dampers, actuates man-ually and automatically with the solenoid valve removed from the respective bottles, upon receipt.of a simulated test signal.

- 3 7 i --

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 4.2.18.4 Ths. fire hose stations in the following locations shall be OPERABLE:

1.

Turbine Building Mezzanine Floor in turbine main steam-stop valve area.

2.

IB Emergency Diesel Generator Building.

3.

Turbine Building Grade Floor by turbine-lube oil reservoir.

4.

Main Floor Turbine Building outside Control Room.

5.

Containment Building Basement.

APPLICABILITY:

Whenever equipment in the areas protected by the

~

fire hose station is required to be OPERABLE.

ACTION:

a.

With a hose station inoperable, route an additional hose of equivalent capacity to the unprotected area from an OPERABLE hose station within one hour, b.

The provisions of Specifications 3.0.3 and '3.0.4.are not' applicable.

SURVEILLANCE REQUIREMENTS 5.2.18.4 Each of the fire hose stations shall be demonstrated OPERABLE:

a..

At least.once per 31 days by visual inspection of'the' station to assure all required equipment.is at the; station.

b.

At least once per 18 months by:

1.

Removing the hose for inspection and re-racking,.and

' 2:.

Replacement of all degraded gaskets in couplings, c.

At least once per 3 years by:

1.

Partially opening each' hose station valve to verify l valve OPERABILITY and no flow blockage.

2.

Conducting a hose hydrostatic test at a pressure at-least 50 psig' greater than the maximum pressure' avail-able at that hose station.

- 37j (1)' -

~

PLANT SYSTEMS YARD FIRE HYDRANTS AND OUTSIDE HOSE HOUSES LIMITING CONDITION FOR OPERATION 4.2.18.5 The five yard fire hydrants and four outside hose houses shall be OPERABLE.

APPLICABILITY:

Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

ACTION:

a.

With one or more of the yard fire hydrants or outside hose houses inoperable, route sufficient additional lengths of 2

inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area (s) within one hour if the inoperable fire hydrant or associated hydrant hose house is-the primary means of fire suppression; otherwise, route an additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Pestore the inoperable hydrant (s) and/or hose house (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.18.5 Each of the yard fire hydrants and outside hose houses shall be demonstrated OPERABLE:

a.

At least once per 31 days by visual inspection of the out-side hose house to assure all required equipment is at the hose house.

b.

At least once per 6 months, during March, April or May and during September, October or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

c.

At least once per 12 months by:

1.

Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure avail-able at any yard fire hydrant.

2.

Replacement of all degraded gaskets in couplings.

- 37j (2) -

9 PLANT SYSTEMS FIRE FIGHTING EQUIPMENT LIMITING CONDITION F' JERATION 4.2.18.6 A supply of fire fighting equipment located in a readily accessible location to the fire brigade shall be OPERABLE.

APPLICABILITY:

Whenever equipment required to be protected from fire is required to be OPERABLE.

ACTION:

a.

With the required fire fighting equipment not available, obtair equivalent equipment within 14 days.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.18.6 The supply of fire equipment shall be demonstrated OPERABLE:

a.

At least once per 31 days by visual inspection to assure all required equipment is at the location.

b.

At least once per 18 months by:

1.

Replacement of all degraded gaskets.

2.

Removing the equipment and visually inspecting for defects.

3.

Conducting a functional test on appropriate equipment.

- 37j (3) -

l PLANT SYSTEMS 4/5.2.19 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION 4.2.19 All penetrat,an fire barriers protecting safety related areas shall be functional.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the above required penetration fire barriers non-fanctional, the area shall be protected by operable fire detection instrumentation and within one hour a fire watch patrol shall be established to inspect the area at least once per hour.

If the fire detection instrumentation in the area is inoperable, a continuous fire watch shall be established on at least one side of the affected penetration within one hour.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 5.2.19 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection:

a.

At least once per 18 months, and b.

Prior to declaring a penetration fire barrier functional following repairs or maintenance.

l

- 37k -

' BASES 4

L4/5.2.17 FIRE DETECTION INSTRUMENTATION

-OPERABILITY of the fire detection instrumentation ensures that I

adequate warning capability is available-for the prompt detection of. fires.

This capability is required in. order to detect and locate fires in1their early stages.

Prompt detection of fires will reduce

.the potential for' damage to safety related equipment and is an integral element in the overall facility fire protection program.

4 In the event that a portion of the fire detection instrumentation is inoperable, the establishment of fire patrols in the affected areas 1

is required-to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

i e

i i

4 P

l l-

- 371 -

l m.

1

BASES - (Continued) 4/5.2.18 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.

The fire suppression system consists of the water system, spray and/or sprinklers, CO2, Halon, and fire hose stations.

The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire pro-tection program.

In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to

'be made available in the affected areas until the inoperable equip-ment is restored to service.

In the event the fire suppression water system becomes inoper-able, immediate corrective measures muct be taken since this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Commission provides for prompt evaluation fo the acceptability of the corrective measures to provide adequate fire suppression capability for the continued pro-tection of the nuclear plant.

4/5.2.19 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that the fires will be confined or adequately retarded from spreading to adjacent portions of the facility.

This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detectionand extinguishment.

The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, and fire detection instrumentation in safety related areas on either side is not functional, a continuous fire watch is required'to be maintained in the vicinity of tF-affected barrier until the barrier is restored to functional status.

- 37m -

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 5.2.21.1.1 The Emergency Service Water Supply System shall be demon-strated OPERABLE:

a.

At least once per 31 days by verifying that each manual or automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct.

position.

b.

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel, c.

At least once per 18 months, during reactor shutdown, by performing an integrated system test which directs coolant flow through the Alternate Core Spray System test loop and back to the river.

(1)

Verifying that the combined pump output develops 900 gpm at a minimum system test pressure of 90 psig.

d.

At least once per 18 months, by performing a. drill which assembles the system under simulated emergency conditions.

5.2.21.1.2 Each Emergency Service Water Supply System gasoline engine driven pump shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying an acceptable built-in battery hydrometer indication, and voltage > 12 volts, b.

At least once per 31 days by verifying that the fuel tank contains at least 4.0 U.S. gallons of gasoline, and that the crankcase oil is at a safe level.

c.

At least once per 6 months on a STAGGERED TEST BASIS by starting an engine / pump unit from ambient conditions and operating at least 20 minutes with pump load.

d.

At least once per 6 months by verifying that the fuel tank has been drained and replenished with freah fuel, e.

At least once per 6 months, by performing inspection and maintenance in accordance with written procedures.

f.

At least once per 18 months, by performing inspection and maintenance in accordance with written procedures.

- 37o -

REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 4.3.1 The_ structural integrity of the ASME Code Class 1, 2 and 3 com-ponents shall be maintained in accordance with Specification 5.3.1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2,

3, 4 and 5 ACTION:

With the structural integrity of any ASME Code Class 1 a.

component (s) not conforming to the above requirements, restore the structural integrity of the affected compo-nent(s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum tem-perature required by NDT considerations.

b.

With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected_compo-nent(s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 212'F.

With the structural integrity of any ASME Code Class 3 c.

component (s) not conforming to the above requirements, restore the structural integrity of the affected compo-nent(s) to within its limit or isolate the affected component (s) from service'.

d.

The provisions of Specification 3.0.4 are not applicable.

The provisions of Specification 3.0.3 are not applicable e.

in OPERATIONAL CONDITION 5.

SURVEILLANCE REQUIREMENTS 5.3.1 The structural integrity of ASME Code Class 1, 2 and 3 com-ponents shall be demonstrated per the requirements of Specification 3.0.10.

The applicable surveillance requirements are set forth in Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, Summer 1975 Addenda, except where specific written relief has been requested from the Nuclear Regulatory Commission pursuant to 10 CFR 50, Section 50.55a (g) (6) (i). '

1

REACTOR COOLANT SYSTEM PUMP AND VALVE TESTING LIMITING CONDITION FOR OPERATION 4.3.2 The operationa' eadiness of safety-related pumps and valves shall be maintained la accordance with Specification 5.3.2.

APPLICABILIT'l:

OPERATIONAL CONDITIONS 1, 2,

and 3.

ACTION:

a.

With any of the above required pump (s) and valve (s) not conforming to the above requirements, declare the pump (s) or valve (s) inoperable and refer to System LCO.

SURVEILLANCE REQUIREMENTS 5.3.2 The operational readiness of the above required pumps and valves shall be demonstrated OPERABLE by verifying their acceptability when tested per the applicable requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, Summer 1975 Addenda, except where specific written relief has been requested from the Nuclear Regulatory Commission pursuant to 10 CFR 50, Section 50.55a (g) (6) (i).

BASES 4/5.3 STRUCTURAL INTEGRITY The inspection and testing program conforms to the. requirements of 10 CFR 50, Section 50.55a(g).

To the extent practical, the inspec-tion and testing of components classified into Class 1, 2, and 3 will conform to the requirements for ASME Code Class 1, 2, and 3 compo-nents contained in Section XI of the ASME Boiler and Pressure Vessel Code, " Inservice Inspection of Nuclear Reactor Coolant Systcms,"

1974 Edition, Summer 1975 Addenda.

Using Regulatory Guide 1.26, Revision 3,

" Quality Group Classifica-tions and Standards for Water, Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants" as a guide, LACBWR components have been classified in " Classes."

This classification serves as the basis for determining which ASME Code Class inspection and testing requirements are applicable to a given component.

10 CFR 50, Section

50. 55a (g) requires components which are part of the reactor coolant pressure boundary and their supports to meet the inservice inspection and testing requirements applicable to components classified as ASME Code Class 1.

Other safety-related components must meet the inservice inspection and testing requirements applicable to components classs-fied as ASME Code Class 2 or 3.

The inservice inspection and testing program must be updated at 120-month intervals in accordance with 10 CFR 50, Section 50.55a (b) (2).

A description of the updated programs should be submitted to the NRC for review at least 3 months before the start of each interval.

The inservice inspection and testing program must, to the extent practical, comply with the requirements in editions and addenda to the ASME Code that are "in effect" more than twelve months before the start of the period covered by the updated program.

The term "in effect" means both having been published by the ASME, and having been referenced in paragraph (b) of 10 CFR 50, Section 50.55a.

If a code required inspection or test is impractical, requests for de-viations are submitted to the Commission in accordance with 10 CFR 50, Section 50.55a (g) (6) (i).

Deviation requests should, if possible, be submitted to the NRC for review at least 90 days before the start of each period, however, deviations identified during an inspection period may be requested.

A requested deviation which has been sub-mitted to the Commission may be considered acceptable until a formal disapproval has been received.

BASES PUMP AND VALVE TESTING The inspection programs for testing of safety-related pumps and valves ensure the operational-readiness of these components will be main-tained at an ceceptable level throughout the life of the plant.

The inservice inspection program will be performed in accordance with the applicable requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Summer 1975 Addenda, except where specific written relief has been requested from the Nuclear Regulatory Commission pursuant to 10 CFR 50, Section 50.55a (g) (6) (i).

1 e

f.

A Fire Brigade of at least 5 members shall be maintained on site at all times.*

The Fire Brigade shall not include the two LACBWR Plant Operators necessary for safe shutdown of the unit or any other personnel required for other essential functi0ns during a fire emergency.

g.

At all times when the reactor is critical, or when its controls are being manipulated with fuel in the reactor, the control room shall be attended by a minimum of two persons, one of whem shall have a valid Operators License and shall have full responsibility for operation of the facility.

6.2.3 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.

4

• Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum require-ments.

This provision does not permit any Fire Brigade position to be unmanned upon shift change due to an oncoming Brigade member being late or absent.

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(

Dairyland Power Cooperative Top Management Organization BOARD OF DIRECTORS GENERAL MANAGER m

0 SECRETARY &

GENERAL ADMINISTRATIVE C0l!NSEL ASSISTANT 1

l ASSISTANT ASSISTANT ASSISTANT ASSISTANT GENERAL GENERAL MGR.

GENERAL MGR.

GENERAL MGR, &

M AN AGER.

SYSTEM ENGIN-ADMINISTRATIVE CONTROLLER'S POWER GROUP EERING GROUP SERVICES GROUP GROUP Figure 6.2.1-1 0FFSITE ORGANIZATION

I GENERAL MANAGER l

SAFETY REVIEW COMMITTEE ASST. GENERAL MANAGER I

POWER I

TECH. SUPPORT LACBWR OPERATIONS I

CONTRACTORS PLANT SUPERINTENDENT REVIFW COMMITTEE I

I I

I I

OUALITY ASSURANCE ASST. PLANT SUPT.

RAD. PROTECTION ON-SITE TECHillCAL SUPERV150R STEN 0GRAPHERS SUPPORT SECl RITY MAB AGER (LS0)

MANACFR I

I ENGINELRS j

AND QA/QC l SECURITY DIRECTOR l HEALTH & SAFETY TECHNICAL,

TECHNICIANS SUPPORT qHPFR"ISOR HEALTH PHYSICS TFCHNICIANS L

l l

MECHANICAL OPERATIONS SUPERVISOR INSTRUMENT &

MAINTENANCE (LS0 )

ELECTRICAL SUPERVISOR SifPFRVISOR INSTRUMENT AND MECHANICAL SHIFT ASSISTANT TO lECHNICIAIS MAINTENANCE 0PERATIONS SUPERVISOR SUPERVISORS (LS0) g

& TRAINING (LSO )

IPLANT OPERATORS (LO)l FIk RTC1 i LS0)

NOTE:

• Designated Engineer Responsible for Fire DAIRYLAND POWER COOPERATIVE Protection Program.

LACBWR FACILITY ORGANIZATION FIGURE 6.2.2-1

ADMINISTRATIVE CONTROLS

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_6. 3 UNIT STAFF OUALIFICATIONS Each member of the unit staff shall meet or exceed the minimum

~

6.3.1 for comparable positions and the qualifications of ANSI N18.1-1971 supplemental requirements specified in Sections'A and C of Enclosure 1 1980 NRC letter to all licensees, except.for the of the-March 28, Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory. Guide 1.8, September 1975.

6.4 TRAINING

'c 6.4.1 A retraining and replacement training program for the unit staff shall.be maintained under the direction of the Training Super-visor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigades shall be maintained under the direction of the Mechanical Engineer and shall meet the requirements of Section 27 of the NFPA Code-1975,.except for.the frequency of Fire Brigade training sessions, which shall be held at least once per 92 days.

6.5 Review and Audit 6.5.1 OPERATIONS REVIEW COMMITTEE (ORC)

FUNCTION r

The Operations Review Committee shall-function to advise the 6.5.1 Plant Superintendent on all matters related to nuclear safety.

?'

COMPOSITION 6.5.1.2 The Operations Review Committee shall be composed of the:

Chairman:

Plant Superintendent Members:

. Operations Supervisor Mechanical Maintenance Supervisor Instrument and Electrical Supervisor Health and Safety Supervisor / Radiation Protection' Manager Assistant' Superintendent Assistant to Operations Supervisor and Training Operations Engineer Reactor Engineer ALTERNATES:

All alternate members shall be appointed in writing by the 6.5.1.3 ORC Chairman to serve on a temporary basis; however, no more than two

. alternates shall participate as voting members in ORC activities at L

any one time.

6-5 t

r

,r--

a ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The ORC shall meet at least once per calendar month and as convened by the ORC Chairman or his designated alternate.

OUORUM 6.5.1.5 The minimum quorum of the ORC necessary for the performance of the ORC responsibility and authority provisions of the Technical Specifications shall consist of the Chairman, or his designated alternate, and five members, including alternates.

RESPONSIBILITIES 6.5.1.6 The Operations Review Committee shall be responsibi_e for:

a.

Review of (1) all procedures required by specification 6.8 and changes thereto, (2) any other proposed procedures or changes thereto as determined by the Plant Superin-tendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

c.

Review of all proposed changes to the Appendix "A"

Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.

e.

Investigation of all violations of the Technical Specifi-cations including the preparation and forwarding of reports covering evaluation and recommendations to prevent recur-rence to the Assistant General Manager-Power Group and to the Safety Review Committee (SRC).

f.

Review of events requiring 24-hour written notification to the Commission, g.

Review of unit operations to detect potential nuclear safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Superintendent or SRC.

i. _ Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the SRC.

j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the SRC.

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