Text

Proposed Tech Spec Sections 3 & 4,incorporating Changes Recommended in Generic Ltr 87-09 & Other Administrative Changes
	ML17328A114
Person / Time
Site:	Cook
Issue date:	08/30/1989
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17328A113	List: ML17328A112; ML17328A114;
References
	GL-87-09, GL-87-9, NUDOCS 8909070032
	Download: ML17328A114 (211)
	v • d • e

Attachment 2 to AEP:NRC:1036 Proposed Revised Technical Specification Changes 89'09070032 890830 050003i5 PDR ADOCK PDC

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3 4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3 4.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provide in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place it, as applicable, in:

a. At least HOT STANDBY within the next 6 hours,

b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODES 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown they are not met within a specified time interval. Entry into an if OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

D. C. COOK - UNIT 1 3/4 0-1 Amendment No'.

3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This Specification is not applicable in MODES 5 or 6.

SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 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, but

b. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. (This does not apply to surveillances that have been delayed per exemption to Specification 4.0.4.) The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

D. C. COOK - UNIT 1 3/4 0-2 AMENDMENT NO.

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APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 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 valves 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:

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing ins ection and testin 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 4.0.2 are applicable to the above required frequencies for performing inservice inspection 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'hall be construed to supersede the requirements of any Technical Specification.

By specific reference to this'ection, those surveillances which must be performed on or before July 31, 1987, and are designated as 18-month surveillances (or required as outage-related surveillances) may be delayed until the end of the Cycle 9-10 .

refueling outage (currently scheduled to begin during the second quarter of 1987)'. For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1987 refueling outage.

D. C. COOK - UNIT 1 3/4 0-3 AMENDMENT NO.

APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.7 By specific reference to this section, those surveillances which must be performed on or before April 1, 1989, may be delayed until the end of the Cycle 10-11 refueling outage (currently scheduled to begin during the latter part of the first quarter of 1989). For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1989 refueling outage.

D. C. COOK - UNIT 1 3/4 0-4 Amendment No.

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3 4 LIMITING CONDITIONS FOR OPEPATION AND SURVEILLANCE PE UIREHENTS BASES S eciffcation 3.0.1 throu h 3.0,4 establish the general requirements applicable to m t ng on t ons or peration. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federa1 Regulations, 10 CFR 50.36(c)(2):

"Limiting conditions for operation are the lowest functional capability or performance levels of equipment reauired for safe operation of the faci1fty. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

S ecfffcation 3.0.1 establishes the Applicability statement within each n v ua spec cation as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION reouirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit fs the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the a11owable outage time limits, a shutdown is required to place the facility in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system(s) or component(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operationa1 problems. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service. In this case, the allowable outage time D. C. COOK - UNIT 1 B 3/4 0-1 Amendment No.

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3/4. 0 APPLICABILITY BASES (Continued) limits of the ACTION requirements are. applicable when this limit expires the surveillance has not been completed. Mhen a shutdown is required to ff comply with ACTION reouirements, the plant may have entered a MODE'n which a new specification becomes applicable. In this case, the time limits of the ACTION requirements would apply from the point in time that the new speci~ication becomes applicable for Operation are not met.

if the requirements of the Limiting Condition S ecification 3.0.2 establishes that noncompliance with a specification exists w en t e reau rements of the Limiting Condition. for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (I) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

S ecification 3.0.3 establishes the shutdown ACTION requirements that must be mp emente w en a Limiting Condition for Operation is not met and the cond)tion is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown NODE when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Oper ation and i.ts ACTION requirements. It is not contended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change fn plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower NODES of operation permit the shutdown to proceed fn a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

D. C. COOK - UNIT 1 B 3/4 0-2 Amendment No.

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3 4.0 APPLICABILITY BASES (Continued)

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MOOE of operation.

3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with source the ACTION state-ments for po~er sources, when a normal or emergency power is not OPERABLE. It specifically prohibits operationis when one division is inoperable because its normal or emergency power source inoperable and a system, subsystem, train, component or device in another division is inoperable f'r another reason.

The provisions of this specification permit the ACTION statement associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source. It allows oper ation. to be governed by thefortime limits of the ACTION Operation for the normal statement associated with the Limiting Condition or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoper able solely because of the inoperability of its normal or emergency power source.

For example, Specification 3.8. 1. 1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months out-of-service time when one emergency diesel generator is not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0 ', all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Oper ation. However, the provisions of Specification 3. 0. 5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency po~er source OPERABLE). If they are not satisfied, action is required in accordance with this specification.

L As a further example, Specification 3.8.1.1 requires'in part that two physi" cal'ly independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required nffsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consider ation of Specification 3.0.5, a11 systems, subsystems, trains, components and devices D. c. cooK - UNIT I B 3/4 0-4 Amendment No.

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3/4. 0 APPLICABILITY BASES (Continued) supplied by the inoperable normal power sources, both of the offsite circuits would also be inoperable. This would dictate invoking the applicable ACTION statements 'for each of the apol icabie LCOs. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied. In this case, thfs would mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power sour=e) and all redundant systems, subsystems, trains, components and devices iz the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i. e., be capable of performing their design functions and have an emergency power source OPERABLE). In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE. If these conditions are 'not satisfied, action is required in accordance with this specification.

In MODES 5 or 6, Specification 3. 0. 5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

S ecifications 4.0. 1 through 4.0.5 establish the general requirements app ica e to urve ance equ rements, These requirements are based on the Surveillance Requirements stated in the Code of Federal Reoulations, IO CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibra-tion, or inspection to assuage that the necessary quality of systems and components is maintained, that facility operation will be within the safety limits, and that the limiting conditions of operation will be met."

S ecificatfon 4.0. 1 establishes the requfrement that survefllances must be per orme ur ng t e OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated fn an individual Survefllance Requirement. The purpose of this speci-fication fs to ensure that surveillances are performed to verify the opera-tional status of systems and components and that parameters are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specffied condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is fn an OPERATIONAL MODE for which the reaufrements of the associated Limiting Condition for Operation do not apply unless otherwise specffied. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception fs used as an allowable exception to the requirements of a speciffcation.

D. C. COOK - UNIT 1 8 3/4 0-5 Amendment No.

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3 4.0 APPLICABILITY BASES Continued If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements. If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated. For surveillances that may be delayed per exemption to Specification 4.0.4, it is expected that the surveillances will be performed expeditiously after entering the applicable mode. However, it is recognized that plant conditions may, at times, cause greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to be required to complete the surveillance.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

S ecification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specifi.ed surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

D. C. COOK - UNIT 1 B 3/4 0-7 AMENDMENT NO.

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t 3/4.0 APPLICABILITY BASES (Continued) of S ecification 4.0.5 establishes the requirement that inservice inspection o e ass , 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall 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 50.55a. These requirements apply except when relief has been provided in writing by the Comaission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification fs provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of t

the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

D. C. COOK UNIT I B 3/4 0-8 Amendment No.

I TABLE 3.3-1 A REACTOR TRIP SYSTEM INSTRUMENTATION O

O Iq MINIMUM I TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. 'Manual Reactor Trip 1 2 1, 2 and* 12

2. Power Range, Neutron Flux 1, 2-and *

3. Power Range, Neutron Flux, 1, 2 High Positive Rate

4. Power Range, Neutron Flux, 1, 2 High Negative Rate

5. Intermediate Range, 1, 2 and*

Neutron Flux

6. Source Range, Neutron Flux A. Startup 2"" and

B. Shutdown 3, 4 and 5

7. Overtemperature hT Four Loop Operation 1, 2

8. Overpower bT Four Loop Operation 1, 2

TABLE 3.3.1 ONTINUED)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION oO 9. Pressurizer Pressure-Low 1, 2 Iq I 10. Pressurizer Pressure High 1, 2 6 g

11. Pressurizer Water Level High 1, 2 74

12. Loss of Flow Single Loop 3/loop 2/loop in 2/loop in 74 (Above P-8) any opera- each opera-ting loop ting loop

13. Loss of Flow Two Loops 3/loop 2/loop in 2/loop in (Above P-7 and below P-8) two opera- each opera-ting loops ting loop

14. Steam Generator Water 3/loop 2/loop in 2/loop in 1, 2 Level Low-Low any opera- each opera-ting loop ting loop

15. Steam/Feedwater Flow 2/loop-level 1/loop-level 1/loop-level 1, 2 Mismatch and Low Steam and coincident and Generator Water Level 2/loop-flow with 2/loop-flow

'ismatch in 1/loop-flow mismatch or same loop mismatch in 2/loop-level same loop and 1/loop-flow mismatch w4 0

n TABLE 3.3-1 Continued nO O REACTOR TRIP SYSTEM INSTRUMENTATION I

MINIMUM g TOTAL NO ~ CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

16. Undervoltage-Reactor Coolant 4-1/bus Pumps

17. Underfrequency-Reactor 4-1/bus Coolant Pumps

18. Turbine Trip A. Low Fluid Oil Pressure B. Turbine Stop Valve Closure 74 Vl I 19. Safety Injection Input 1, 2 from ESF

20. Reactor Coolant Pump Breaker Position Trip Above P-8 1/breaker 1/breaker 10 A.

B. Above P-7 and below P-8 1/breaker 1/breaker per oper-ll ating loop

21. Reactor Trip Breakers 1, 2 ls 13 3* 4* 5* 14 R

aX 22. Automatic Trip Logic 1, 2 1 3* 4* 5* 14 O

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MUDES ACTION

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUHPS

a. Steam Generator Water 2/Stm. Gen.

Level Low-Low 3/Stm. Gen. any Stm. Gen. 2/Stm. Gen. 1I 2I 3

b. 4 kv Bus 2/Bus 2/Bus 2/Bus 1, 2, 3 Loss of Voltage

c. Safety Injection I, 2, 3

d. Loss of Main Feedwater Pumps 2 1, 2 18

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 2/Stm. Gen. 2/Stm. Gen. 1, 2, 3 14 Level Low-Low 3/Stm. Gen. any 2 Stm. Gen.

b. Reactor Coolant Pump Bus Undervoltage 4-1/Bus 1, 2, 3 19

8. LOSS OF POWFR

a. 4 kv Bus 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 Loss of Voltage

b. 4 kv Bus 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 Degraded Voltage

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3 4 3 I OR G I STRUMENT ON DIATION ONITOR NG INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 .The radiation monitoring instrumentation channels shown in Table 3 '-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

INACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c. The provisions of Specification 3.0.3 are not applicable,,

SURVEILIANCE RE UIREME TS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at

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D. C. COOK - UNIT 1 3/4 3-35 AMENDMENT NO.

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1)

MINIMUM CHANNELS ALARM TRIP OPERATION MODE/INSTRUMENT OPERABLE SETPOINT SETPOINT ACTION

1. Modes 1, 2, 3, & 4 A) Area Monitors i) Upper Containment (VRS 1101/1201) N/A ~ 54 mR/hr 21 B) Process Monitors i) Particulate Channel (ERS 1301/1401) N/A < 2.52 uCi 20 ii) Noble Gas Channel -3 (ERS 1305/1405) < 4.4 x 10 uCi CC C) Noble Gas Effluent Monitors i) Unit Vent Effluent Monitor a) Low Range (VRS 1505) (See T/S Section 3.3.3.10)

TABLE 3.3-6 (Cont'd)

O RADIATION MONITORING INSTRUMENTATION O (OPERABILITY BASES DISCUSSED IN BASES SECTION 3/4.3.3.1) 8 I

MINIMUM CHANNELS ALARM TRIP OPERATION MODE INSTRUMENT OPERABLE SETPOINT SETPOINT ACTION iii) Noble Gas Channel N/A + 4.4 x 10 uCi 22 (ERS 1405) CC

3. Mode ***

A) Spent Fuel Storage (RRC-330) ~

15 mR/hr 4 15 mR/hr 21

The provisions of Specification 3.0.4 are not applicable.

- - Mith fuel in storage pool or building.

I + This specification applies only during purge.

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INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles,

b. A minimum of 2 detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the axial flux difference detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or Measurement of FLH> and F (Z,<)

ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output to be used during its use when required for:

a. Recalibration of the excore axial flux difference detection system, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of F H

and F (Z, k).

D. C. COOK - UNIT l 3/4 3-39 Amendment No.

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INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.'CTION'.

With the number of OPERABLE seismic monitoring instruments less than required by Table 3.3-7, restore the inoperable instrument(s) to OPERABLE status within 30 days.

b. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument(s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.3.1 Each of the above seismic monitoring'instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

D. C. COOK - UNIT 1 3/4 3-40 Amendment No.

'I fJ INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring fnstrumentatfon channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At al 1 times.

ACTION:

a. Wfth the number of OPERABLE meteorologfcal monitoring channels less than required by Table 3.3-8, suspend all release of gaseous radioactive materfal from the radwaste gas decay tanks.

until the inoperable channel(s) is restor ed to OPERABLE status.

b. Wfth one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Coamfssfon pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

C. The prOViSiOnS Of SpeCfffCatfOn 3.0.3 ax'e not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

D. C. COOK-UNIT 1 3/4 3-43 Amendment No.

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INSTRUMENTATION TE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

Mith the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either:

a. Restore the inoperable channel to OPERABLE status within 30 days, or

b. Be in HOT SHUTDOMN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.5 Each remote shutdow'n monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNFL CHECK, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

0. C. COOK-UNIT 1 3/4 3-46 Amendment No.

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INSTRUNENTATION PIRE DETECTION INSTRUMENTATION LIMITING CONDITION POR OPERATION 3.3.3.7 As a miaimum, che fire detection instrumentation for each fire dececcioa cone shovn tn Table 3.3-10 shall be OPERABLE, APPLICAB?LITY: Mhenever equipmenc procecced by the fire detection iascrumenc(s) is required co be OPERABLE.

ACT IOH:

Mich the number of OPERABLE fire detection instrument(s) less chan the minimum number OPERABLE requirement of Table 3.3>>1.0:

a. Mithia l hour escablish a fire vatch pacrol to inspect the cone(s) vich che inoperable inscrumenc(s) ac least once per hour, unless the instrument(s) is located inside the concainmenc, chen iaspecc the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the concainment air temperature at least once per hour at. the locations listed in Specificacion 4.6.l.5.

b. Restore the inoperable instrument(s) to OPERABLE status vithin l4 days, or in lieu of any other report required by Specification 6.9.l, prepare and subnit a Special Report co che Commission pursuant to Specificacioa 6.9.2 vichin che next 30 days outlining the action taken, che cause of the inoperability and the plans and schedule for restoring che inscrument(s) to OPERABLE status.

c ~ The provisions of Specif icacion 3.0.3 axe not applicable-SURVEILLANCE RE Ui,RZ.'ANTS 4 ~ 3.3.7.1 Each of the above required fire decection instruments vhich are accessible during plant operation shall be demonstraced OPERABLE at Least once per 6 months by performance of a CHANNEL fUNCTIONAL TEST. Pire detectors vhich are not accessible during plane operation shall be demonstrated OPERABLE by che performance of a CHANNEL fUNCTIONAL TEST during each COLO SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 mone hs.

4 ~ 3.3.7.2 The NFPA Standard 72D Class B supervised circuits supervision associated vith the dececcor alarms of each of the a bove required fire detection iascrumencs shall be demonscraced OPERABLE at lease once per 6 mont hs.

D C COOK - UNIT 1 3/4 3-51 Amendment No.

INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12

'CTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative,than a value which will ensure that the limits of 3.11.1.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, reset, or declare the channel inoperable.

b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the applicable ACTION shown in Table 3.3-12.

c. The provisions of Specifications 3.0.4 and 6.9.1.13 are not applicable.

SURVEILLANCE'RE UIREMENTS 4.3.3.9,1 The setpoints shall be determined in accordance with methodology as described in the ODCM and shall be recorded.

'4.3.3.9.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

D. C. COOK - UNIT 1 3/4 3-57 AMENDMENT NO.

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INSTRUMENTATION RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3 '-13.

ACTION

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.2.1 are met, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, reset, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.10.1 The setpoints shall be determined in accordance with methodology as described in the ODCM and shall be recorded.*

4.3.3.10.2 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

This surveillance requirement does not apply to the Waste Gas Holdup System Hydrogen and Oxygen Monitors, as their setpoints are not addressed in the ODCM.

DE C. COOK - UNIT 1 3/4 3-62 Amendment No.

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONOITION FOR OPERATION 3.4.9.3 At least one of the fo) lowing overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves {PORVs) with a lift setting of less than or equal to 400 psig, or

b. One power operated relief valve (PORV) with a lift setting of less than or equal to 400 psig and the RHR safety valve with a lift setting of less than or equal to 450 psig, or

c. A reactor coolant system vent of greater than or equal to 2 square inches.

APPLICABILITY: When the temperature of one or more of the RCS cold legs is less than or equal to 170'F, except when the reactor vessel head is removed.

ACTION:

With two PORV's inoperable or with one PORV inoperable and the RHR safety valve inoperable, either restore the inoperable PORV{s) or RHR.safety valve to OPERABLE status within 7 days ot depressurize and vent the RCS through an at least 2 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until the inoperable PORV or RHR safety valve has been restored to OPERABLE status.

With both PORVs inoperable, depressurize and vent the RCS through an at least 2 square inch vent(s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both PORVs or one PORV and the RHR safety valve have been restored to OPERABLE status.

C. In the event either the PORVs, the RHR safety valve or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Rector. shall be prepared and submitted to the Commission pursuant to Specification 6. 9. 2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

O.C. COOK - UNIT 1 3/4 4-31 Amendment No.

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REACYOR COOLANT SYS~o.

3/4, 4, 10. STRUCTURAL INTEGRITY ASME COOK CLASS 1 2 and 3 CCMPOHEHTS LIr."lITIHG CQHOITIOH FOR OPcRATION 3.4.10.1 The struc.ural intzgrity of ASME Code Class 1, 2 and 3 camponents shall be maintained in ac=arcance with Specification 4.4.10.1 ~

APPt ICABILITY ALL DOGES ACTIdN:

Vith the structural integrity of any ASME Code Class 1 camponent(s) not conforming ta the above requirements, restore the structural integrity of the affected camponent(s) ta within its limit or isolate the af fee-ed component(s) prior a increasing the Reac.or Coolant System temperature more than 50 F above the minimum emper ature required by NOT cansicerations. requirements Mith the structural integri y of any ASHE Code Class 2 camponent(s) not conforming ta :.",e above . restore the structural integrity of the ar, ced amcanent(s) -- within its limit or isolate the affec ed camconent(s) prior ta increasing he Reac:ar Coolant

~ ~ System temperature,.a"ove ZGC'F.

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c With he structural inta~ri".y o, any ASME CaCe Class 3 cawonent(s) not conforming ta:he above r equiremenrs, restar e the struc.ural

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integrity Of the af eC:ed Campanent(S):a within itS 1imi. Or iSOlate the affected component( s ) frem service.

SURVEILLANCE REOUIRKHEHTS 4.4.10. 1 In addition ta the requirements of Soeci fication 4.0. 5, each reac-or cao ant pump f1 ywne 1 1 shal I be inspected per the recommendations of Requl atory Position C. 4.b of Regulatary Guide l. 14, Revision 1, Augus- 1975.

D. C. COOK - UNIT 1 3/4 4-33 Amendment No.

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V V M G CO D 0 OR 0 ION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

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a ~ With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, 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 .

With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODE 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the reactor trip breakers are opened; otherwise, be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE, with lift settings and orifice sizes as shown in Table 4.7-1, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition.

D. C. COOK - UNIT 1 3/4 7-1 AMENDMENT NO,"

~ h PLANT SYS EMS STE GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator stop valve shall be OPERABLE ~

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1 - With one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

MODES 2 - With one steam generator stop valve inoperable, subsequent and 3 operation in MODES 2 or 3 may proceed provided the stop valve is maintained closed. Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by:

a. Pare-stroke exercising the valve at least once per 92 days, and

b. Verifying full closure within 5 seconds on any closure actuation signal while in HOT STANDBY with T greater than or equal to 541 0 F during each reactor shutdown except that verification of full closure within 5 seconds need not be determined more often than once per 92 days.

4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.

D. C. COOK - UNIT 1 3/4 7-10 AMENDMENT NO.

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PLANT SYSTEMS 3 4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material,, shall be free of

> 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION

a. Each sealed source with removable contamination in excess of the above limits shall be immediately withdrawn from use and:

l. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.7.1.1 Test Re uirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.7.1.2 Test Fre uencies - Each category of sealed sources shall be tested at the frequency described below.

a. Sources in use excludin startu sources reviousl sub ected to core flux) - At least once per six months for all sealed sources containing radioactive materials.

D. C. COOK - UNIT 1 3/4 7-26 Amendment No.

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PLANT SYSTEMS 3/4,7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION MATER SYSTEM LIMITIHQ COHDITIOH FOR OPERATIOH 3.7.9.1 The fire suppression vacer system shall be OPERABLE vith:

a. Tvo<<high demand pumps, one of vhich shall be a diesel driven pump, vith cheir discharge aligned to che fire suppression header.

b. An OPERABLE flov path capable of taking suction from Lake Michigan and transferring che vacer through discribucion piping vich OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the hose scandpipe or spray system riser or vacer flov alarm device on each sprinkler, required to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.5.

APPLICABILITY: Ac all times.

ACTION:

a. Pith one pump inoperable, restore the inoperable equipmenc to OPERABLE status vichin 7 days or, in Lieu of any other reporc required by Specification 6.9.1, prepare and submit a Special.

Report to the Commission pursuant to Specification 6.9.2 vithin the next 30 days ouclining the plans and procedures co be used to provide for the loss of redundancy in this system. The provisions of Specif ication 3.0.3 'ax'e not applicabla;

b. 'Mi.ch che fire suppression vater system othervise inoperable:

1. Establish a backup fire suppression vacer system vichin hours, and

2. Suhnic a Special Report ln accordance vith Specification o.9.';

a) By telephone vichin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b) Confirmed by telegram, maiigram or facsimile transmission no lacer than che first vorking day folloving the event, ~nd

<<Shared system vich D.C. COOK - UNIT 2.

D C COOK - UNIT l 3/4 7-41 Amendment Ho.

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PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITIHG CONDITION FOR OPERATION p y /or sprinkler systems located in che areas shov Table 3.7"5 shall be OPERABLE:

APPLICABILITY: Mhenever equipmenc in the spray/sprinkler protected areas is re qui red co be OPERABLE ~

hCTZON:

a. Pith one or more of the above required spray and/or sprinkler systems inoperable, vithin l hour establish a continuous fire vatch vith backup fire suppression equipment for chose areas~ iq.vhich redundant safe shucdovn systems or components could be damaged.

Restore the system to OPERABLE status vithin 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 co Specification 6.9.2 vithin the next 30 days outlining the action taken, the cause Qf che i,@operability and the plans and schedule for restoring che

.system to OPERABLE stacss.

The provisions of Specificacion 3.0,3 pre not applicable.

SURVEILLANCE RE UIREMENTS 4 ~ 7.9.2 Each of che above required spray and/or sprinkle t'ystems shall be demonstrated co be OPERABLE:

a. Ac Least once per 12 monchs by cycling each cescable valve in the flov path through at least one complete cycle of full travel.

~- For che reaccor coolant pumps preaction sprinklers inside che containment, a closed circuic television located in che lover containmenc, vich periodic monitoring (and hourly logging) of che CCTV screen, shall'e an acceptable subscicuce co an hourly fire,vatch pacrol. For high radiation areas vhere closed circuic television coverage does noc exisc, an hourly fire vatch pacrol vill be instituted.

D C COOK UNIT l 3/4 7 44'mendment No.

PLANT SYSTEMS LOW PRESSURE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.3 The low pressure CO systems located in the areas shown in Table 3.7-6 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the low pressure CO2 protected areas is required to be OPERABLE.

ACTION:

a.. With one or more of "he above required low pressure CO2 systems isolated for personnel protection, to permit entry for routine tours, maintenance, construction or surveillance testing, verify the operability of the fire detection system as per Specification 4.3.3.7 in the affected area(s) and establish a Roving Fire Watch Patrol (as defined in the Bases Section) in those areas affected by the isolated C02 system(s). In the event that the Roving Fire Watch Patrol cannot be maintained in the affected areas, then personnel must be evacuated and the CO2 system returned to its normal condition.

b. With one or more of the above required low pressure CO2 systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment Eor those areas in which redundant safe shutdown systems or components could be damaged; for other areas ensure that back-up fire suppression equipment is available and establish an hourly Eire watch patrol. 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.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREHENTS 4.7.9.3 Each of the above required low pressure C02 systems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the C02 storage tank level to be > 50% and pressure to be > 285 psig, and

b. At least once per 18 months by verifying:

1. The system valves, associated ventilation dampers and self closing fire doors actuate manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a "Puff Test".

D. C. COOK - UNIT 1 3/4 7-47 Amendment No.

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PLANT SYSTQS Hru.ON SYSTEM LINITINO CONDITION FOR OPERAT ON 3.7.9.4 The Halon system located tn che Unit I Control Room Cable Spreading

rea shall be OPERABLE.

APPLICABILITY: Mhenever equipment in che Halon procected areas is required co be OPERABLE+

ACTION:

a. Mich the above required Halon system inoperable, vithin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that the fire detection system and the backup COg fire suppression system are OPERABLE; othervise,'scablish a continuous fire vetch vich backup fire suppression equipmenr. for the Control Room Cable Spreading Area. Restore the system to OPERABLE status vithin 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report ro the Commission pursuant to Specification 6.9.2 vithin the next 30 days outlining che accion taken, the cause of r,he inoperability and the plans and schedule for restoring the syscem co OPERABLE statue.

b. The provisions of Specification. 3.0.3 are not applica&le.

SURVEILLANCE RE UIRZitENTS 4.7.9.4 The above required Halon syscem shall be demonscraced OPERABLE:

a. Ac lease once per 6 months by verifying each Halon scorage tank co be > 951 pressure.

of full charge veighc and co be > 90'f full charge

b. At least once per 18 months by:

l. Verifying che syscem, including associaced ventilation dampers, actuaces manually and aucomacically co a simulated case signal.

2.'erformance of an air flov cesc or CO~ puff test chrough

'headers and nozzles co assure no blockage.

D C COOK ~ UNIT 1 3/4 2 49 Amendment No

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PLANT STSTEMS FIRE HOSE STATIONS L~ZTINO COHDITIOH POR OPERATION 3.7.9.5 The fire hose scaadpipe conneccions in che follouing locations shall be OPERABLE-'.

Auxiliary Buildiag (minimum 12).

2e Access to Diesel Cene ra to rs (minimum 1) o

3. hccess to Suitcbgear Rooms (minimum 1).

4. Access to Coacrol Room (minimum 1).

APPLICABILITY: whenever equipmeac in cbe areas protected by the fire hose stacioas is required co te OPERABLE.

ACfION:

a. Pith one or more of che above required hose standpipe conaectioas inoperable, route aa addicioaal equivalent capacity fire bose co cba,uaprotected area(s) from an OPERABLE bose standpipe conneccion uithia 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if cbe inoperahle fire hos>> is cbe primary means of fire suppression; ochervise, route che additional bose vithia 24 bours. Restore the fire bose scation co OPERABLE status vithin 14 days or, ia lieu of any other report required by lpecification 6.9.1, prepare and subai,t a Special Report ro che Commission pursuant co Specification &.9.2 uichin che next 30 days oucliniag the action taken, the cause of the inoperability, and plans aad schedule for restoriag che station to OPERABLE status.

b. Tbe provisions of Specificacion 3.0.3 are not applicable.

SURVEILLANCE RE UIREMNTS 4.7.9.5 Each of the above required fire hose standpipe connections shall be

,demonstrated OPERABLE:

a. hc least once per 31 days by a usual inspection oi che iire bose standpipe connections co assure all required equipuenc Ls ac che connection ~

b. At least oace per 18 months by:

Removing the bose for inspection and re-racking, and

2. Replacemenc of all degraded gaskets ln couplings.

c At least once per 3 years by:

Parcially opening each hose standpipe connection valve co verify valve OPERABILITY and no ilou blockage.

2. Conduccing a hose hydrostatic cesc, ac a pressure ac least 50 psig greater chan che maximum pressure available ac chac hose s candp tpe connec cion.

D C COOK UNIT 1 3/4 7-50 Amendment No ~

,rr Ii I

~

3/4.7,L0 STSTZHS CHIRK RATKb ASSR(K ZES OR r 3.7.10 ALL'ire rated assemblies <~allsi floor/ceilingsr cable tray enclosures) separating safety related fire areas or separating portions of redundant systems important to safe shutdown vithin a fire area and all seaLing devices in fire rated assembly penetrations (fire dampersi cable and piping penetration seals'nd ventilation seals) doors'ire shall be OPERh8LE APPLZCABZLZTT: Ae alL tiaaa.

ACT 10 N:

a. Mich oae or mora of ehe above required fire rated assemblies aad/or seaLing devices iaoperable, vithia oae hour either establish a coatiauous fire vatch oa at lease one side of ehe af fectad assembly, or verify the OPKLABZLZTY of fire detectors pet Specificaeioa 4.3.3.7 on at least one side of the inoperable aaaanbly aad eaeabLish aa hourly fire vetch paero1. or secure in the c1osed position the iaoperable seaLing device* and establish aa hourly fire vetch patroL. Restore ehe inoperable fire rated assembly aad seaLing device eo QPvRhBLE status viehia 7 days or, in ELec of aay ocher report required by Specificaeioa 6.9.1, prepare aad submit a SpeciaL Report eo ehe Cotnsissioa pursuaat eo Specificat'oa 6.9.2 viehia the aexe 30 days outlining ehe action cakaa, ehe cause of the iaoperabla fire raced assembly and/or sealing device aad the plaas and scheduLe for raseoriag ehe fire rated assembly and/or sealing device eo OPERABLE status.

b..he provisions of Specificaeion 3.0.3 t

are not applicable.

4 7.10.1

~ Ae Lease once per E8 aonths eha above required fire rated asse biles and peneeraeiOa SeaLiag deViCaS Shall. be verified OPERABLE by:

a. Perfoaaing a visuaL inspection of ehe exposed sucfaces of eac.".: Lre tated assenblies;

b. Performing a visual inspection of each fire damper and associated ha rdva re.

Except, fire doots on Turbine Orivea Auxiliary ."-eedvaear ?uap and HaLLvay enclosures vhich caanoe be Locked cLosed foc'ELB considerations.

0 C COOK UNIT l 3/4 7-3Z Aeendaene Ho.

,k J

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REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the stroage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within+ the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status,

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.12

~ ~ The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a.~ At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.

2 ~ Verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm + 10%.

+ The crane bay roll-up door and the drumming room roll-up door may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

~Shared system with Cook Nuclear Plant - Unit 2.

+ This does not include the main load block, For purposes of this specification, a deenergized main load block need not be considered a load.

COOK NUCLEAR PLANT - UNIT 1 3/4 9-13 AMENDMENT NO.

~ I 4

a

~71

>gt+

Q

COSK LIMITING CONOITIQN FOR OPERATION 3.11.1.2 The dose or dose ceanfweat to an fndfvfdual fran radfoac.fve material in Ifqufd ei'fluents released to unrestricted areas (se Ffgure 5.1-3) shall be Ifmfted:

a. Ourfng any calendar quarter to cI.S mren to the total body and to gmrem to any organ, and

b. Ourfng any calendar year to c 3 mren to the total body and to ~ 10 mren to any organ.

APPLICABILITY: At all tfmes.

ACTION:

a. fifth the calculated dose fram the release of radioactive materials in 1fqufd effluent exceeding any oi'he above Ifmfts, pr pare and suhnit.to the Ccmmfssfon within 30 days, pursuant to Specfffcatfon 5.9.2, a Specfal Report which'dentfifes the cause (s) f'r exceed-ing the limit(s) and defines the canectfve actions taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases wfll be wi:hin the above limfts.

This Specfal Report shall also include (1) the results of'adfologfcal analyses oi'he drfnkfng water source, and (2) the radfologfcal fmpaca on ffnfshed drinking water suop1fes with regard to the requfmnenw of'0 CFR 141, Sai'a Orfnkfng Mawr Act. (Ap'ol fcable only ff drinkfng water supply fs uken Prem the recefvfng water body.)

b. The prOVf sfOnS Of SpeCf fCatfOns 3.0.3 and 6.9.1.13 are not applicable.

SUR'lEiLLANC"= RKQUiR 4BITS 4.11.1.2. Oose Col culatf ons. hmulat'.ve dose con-ributions fram I fqufd Iat',on hfanuaI (OOQl) at leas: once per 31

'lII . N I II days.

II O. C. CCOK - UNiT L 3/4 Ll& Amendment No.

gl

'I i

Radf oactf ve Kt f1uents gfou{d Mast@ Treatment i.fmf tf n Condf tfon For Ooeratf on 3.11;163 The lfqufd radwaste treatment system shall be used to reduce the radfoactfve materfals fn liqufd wastes prfor to their discharge when the pro-jected doses due to the liquid effluent from the sfte (se Figure S.I-3) when averaged over 31 days, would exc d OaC6 mrs to the Atal body or 0.2 mrea to any organ.

~aee bllfc': a \'I n, Actlan:

a. Nth radfoactfve Ifqufd waste being discharged without treatment and fn excess of the above Iimf w, fn lieu of any other report requfr ed by Specification 6.9.1, prepare and submf t to the Cuaafssfon wfthfa 30 days pursuant to SpeciAcatfon 6;9.2 a Specfal Repo'it wpfch includes the foIIowfng fnformatfon:

1. Ldentfffcatfon of Pe inoperable equfpment or subsystens and the reason for inoperabi1fty, Z. Action(s) taken to restore the faoperable equipment to operable

,status and

3. Su+nary descrfptfon. of actfon(s) %ken to prevent recurrence.

~6 P~rf3$ 003 0f $ 960$ ff 06$300s 3.0.3 and 6.9.1.13 are nat aPP>>nab1a Sur Ief1 I ance Reouf rments 4.11.1.3 Oases due to Ifqufd releases to UNRESTRI~i AREAS shal.l be pro-Sectad at Ieas. once per 31 days, in accordance with tNe COQUE, wnenever liquid releases are being made without being processed by the Iiqufd rad-waste treatment systsa.

0. C. CCOK - UNO' 3/4 Ig 6 Amendment No.

Radfoactf ve ft'fluents Lfoufd Holdup Tanks*

Lfmftfno Condftfon For Ooeratfon 3.]1,1.4 The quantity of radioactive material contained fn each of the followfng tanks shall be limfted to less than or equal .to 10 curfes, excludfng tritium and dfssolved or entrained noble gases.

a. Outsfde temporary tanks.

~41 tftf: tt ll tf Acefan:

a. Qfth the quantity of radioactive materfal in any of the above listed tanks exceeding the above limf t, without delay suspend all addftfons of radfoactfve materfa1 to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the lfmft.

b. The Provisions of Specification s 3.0.3 and 6.9.1.13 are not applicable.

Surveillance Reaui rements 4.11,1.4 The quantf.ty of radfoactfve materfal contained fn each of the above listed tanks shall be determfned to be within the above limit by analyzfng a representative sample of the tank's contents at least once per 7 days when radfoactfve materials are being added to the tank.

system.

Tanks included fn this Specfffcatfon ar those outdoor tanks that are not surrounded by liners, dfkes, or walls capable of holding the tank contents and that do not have tank overflows and sur-rounding area drains connected to the liquid radwaste treatment

0. I . CQQK - UNIT 1 3l4 lL-a Amendment Ho.

v1 g

<<g II 0

RAOIOACTIVE EFFLUEBTS NSE NNLE GASES LIMITING CONOITTOM FOR 0PERATTON 3.1E.2.2 The afr dose fn- UNRESTRICTED AREAS due to noble gases released fn gaseous effluents shall be lfmfted to the fotlowfng:

a. Ourfng any calendar quarter, to ~ S mrad for'alena radfatfon and c IO mrad for beth radfatfon;

b. Ourfng any calendar year, to < 10 mrad for gamma radfatfon and c 20 mrad for beta radfatfon.

APPLICABILITY: At all tfmes.

ACTICN:

a. 'fifth the calculated afr dose from radfoactfve noble gases fn gaseous effluents exce~dfng any of the above lfmfts, prepare.

and submft to the Ccmrfssfon wfthfn 30 days, pursuant to Specfffcatfon 6.9.2, a Specfal Report whfch fdentfffes the cause(s) for exceHing the lfmft(s) and deffnes the corr tfve actfons to be taken to reduce the releases and the propo ad correctfve actfons to be taken to assure that subsequent re-leases wfll be wfthfn the above lfmfts.

b'he prOVf SfOnS Of SpeCfffcatfOns 3.0.3 and 6.9.1.13 are not aPPlicable.

4.11.2.'2 tt I

'I~'b SURVE:LANCE REQUIRHDTS Oose Ca1cu1atfon ~znua1 Calculatf ons (00K) at least A

I once

'thdays.tl Cumulatf ve.dose contrfbut",ons every 31 af for i

the 0

total

0. C. COOK - UNIT 1 3/4 ll-10 Amendment Ho

3 0

k SW gt g4

RADIOACTIVE EFFLUENTS DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADZONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to A MEMBER OF THE PUBLIC from radioiodine, radioactive materials in particulate form, and radionuclides ocher than noble gases with half-lives greater than 8 days in gaseous effluencs released co unrestricted areas shall be limiced to the following:

a. During any calendar quarter to less than or equal to 7.5 mrem co any organ;

b. During any calendar year to less than or equal to 15 mrem to any organ;

c. Less chan O.lt of che 3.11.2.3 {a) and {b) limits as a result of burning contaminated oil.

APPLICABILITY: Ac all times.

ACTION'

~ Mi.th the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluencs exceeding any of the above limits, prepare and submit to che Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which idencifies the cause{s) for exceeding the limit and defines che corrective actions taken co reduce the releases and the proposed corrective action to be taken to assure that subsequent, release vill be within the above limits.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILIANCE RE UIREMENTS time period shall be determined in accordance with the ODCM at least once every 31 days.

D. C. COOK - UNIT 1 3/4 11-11 Amendment No. 115

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RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system and the ventilation exhaust treatment system shall be used to reduce the radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas (See Figure 5.1.3) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous

~aste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas (See Figure 5.1-3) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a ~ With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

l. Identification of the inoperable equipment or subsystems and the reason for inoperability.

2. Action(s) taken to restore the inoperable equipment to operable status'.

The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.4 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the ODCM, whenever the gaseous waste treatment system or ventilation exhaust treatment system is not operational.

D. C. COOK - UNIT 1 3/4 11-12 Amendment No.

0 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to < 3S by volume if the hydrogen in the system is

> 4% by volume APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system > 3% by volume but < 4S by volume and containing > 4%

hydrogen, restore the concentration of oxygen to < 3% or reduce the hydrogen concentration to < 4a within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

With the concentration of oxygen in the waste gas holdup system or tank > 4% by volume and > 4% hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to < 3%

or the concentration of hydrogen to < 4S within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months in the system or tank.

c>> The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

D. C. COOK - UNIT 1 3/4 11-13 Amendment No.

F4 ll

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 4 days by analysis of the Reactor Coolant System noble gases.

D. C. COOK - UNIT 1 3/4 11-14 Amendment No.-

t~g h

Jy p'l e

RADIOACTIVE EFFLUENTS 3 4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used as applicable in accordance with a PROCESS CONTROL PROGRAM for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a ~ With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.

With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to operable status,

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and

4. Summary description of action(s) taken to prevent a recurrence.

c. The provisions of Specifications 3.0.3 and 6.9.1 ~ 13 are not applicable.

D. C. COOK - UNIT 1 3/4 11-15 Amendment No.

igAgf

~t k J 1l Rt 41 Qt<

P

RA0raaCTIm m.uem 3 4 11.4 TOTAL OOSK LINETBG CON0ITIN FOR OPERATION 3.11.4 The dosi or dose caamftment to a real fndfvfdual fram all uranfum fuel cycle sources fs lfmf&d to < 25 mrem to the total body or any organ (excipt the thyrofd, whfch fs lfmited to ~ 76 area) over a period af 12 consecutf ve months.

APPLICA8ILI7Y: At all tfmes.

A~iON:

a. Mfth the calculated doses frcm the release of radioactive materials fn lfqufd or gaseous effluents exceeding %fee the lfmfts oi'pecfff-catfan 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, fn lfeu of any other report required by Specfffcatfan 6.9.1, prepare and submit a Specfal Report to the Ofrector, Nuclear Reactor Regulatfan, U.S. Nuclear Regulatory Camnissfan, Washington,

0. C. 206~8, within 30 days, which defines the corrective action to be taken to reduc subsequent releases to prevent recurrence of exceedfng the lfmfts of Specfffcatfan 3.11.4. Thfs Specfal Report shall fnclude an analysis which es.fmates the radfatfan exposure (dose) to a member of'he publfc fran uranium fuel cycle sources (includfng all ef 1uent pathways and direct radfation) for a 12 consecutfve month period that fncludes the release(s) covered by thfs report. If the estimated dose(s}

exceeds the lfmfts o, Specification 3.11.4, and ff the release candffan resultfng fn violation af 40 CFR 190 has no. already been carr+:t-d, the Specfal Report shall fnclude a request far a variance fn accordance with the pravisfans af 40 CFR 19Q and fncludfng the specif'fed fnf'ar-matian af t 190.11(b). Submittal oi'he report fs considered a timely request, and a varfance fs granted untf1 staff'ction an "Ne reques fs ccmplete. The variance only r laths to the lfmfts af 40 C.=R 190, and does not apply fn any way ta the ~ufrenents for dose limitatfan af 10 Cr% Part 20, as addressed fn other sections af thfs Te wnfca1 Specf ffcatf an.

The prOVf SfanS 41 Spe fffCatians 3.0.3 and 6.9.l.l3 are not applicable.

SURVEiLt INC:- RHUIRBG i S 4*.~4,f dl&*

4.11.4 4

Oase Calculat'.ans l1-!-2, 4.11.2-2, and 4.11.2.3 and with the OGQI.

INSET lf Cunalatfve dose cantrfbutfans fran lfqufd and tf

0. C. COOK UNIT L 3/4 11-17 Amenctment No.

f1 l

4~

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION CONTINUED co With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3 '2-1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from Table 3.12-1 provided the locations from which the replacement samples were obtained are added to the environmental, monitoring program as replacement locations, available.

if

d. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4 '2.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12-1 and 4.12-1.

D. C. COOK - UNIT 1 3/4 12-2 Amendment No.

/I I 4

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)k v P 4$

. RADIOLOGICAL BlVIRCNEHTAL MONITORING 3 4.12. 480 USE CENSUS LIMITING CONamOH FOR OPERATION 3.12.2 A land use census sha11 he conducted and shall fdentffy the loca-tfon of the nearest mf1k anfaal, the'nearest resfdence and the nearest garden>> of greater than SN square feet producfng fresh leafy vegetables fn each of the ~ land caverfng meterolaqfcal sectors wfthfn a dfstance of ffve argyles.

APPLICABILITY: At all times.

aCTION:

a. Mfth a land use census fdentffyfng a locatfon(s} whfch yfelds a calculated dose or dase comf&ent greater than the values currently befng calculated fn Spccfffcatfon 4.11.2.3, pre-pare and suhmft to the Ccamfssfon wfthfn 30 days, pursuant ta Specfffcatfon 6.9.2. a Specfal Report.whfch fdentfffes the new lacatfan(s}.

b. Mfth a 1and use census fdentffyfng a locatfon(s) whfch yfelds a calcu1ated dose or dose ceanf~nt (vfa the same exaasure patnwav) 20 percent areater than at a lacatfan free whfch sam@les are currentTy befnq obtafned fn accordance wfth Specfffcatfan 3.i2.1, prepare and sulmtt to the Ceaaissfon wfthfn 30 days, pursuant to Specfffcatfon S.9.2, a Specfal Report whfch fdentfffes the new lacatfan. The neo 1acatfan shall be added.to the radfologfcal envfronmental monftarfng program. wfthfn 30 days, ff lossfble.

The. samplfng locatfon havfng the lowest calculated'ose or aose ccamftment (vfa the same exposure pathway) may be deleted fram thfs monftarfng program after (Octaber 3'l) of tha year fn whfch thfs land use census was conducted.

c. The orovfsfans of Specfffcatfons 3.0.3 and 6.9.1.13 are not applicable.

SUPlKILLANCF REOUIR&ENTS 4-12-2. The land use census shall be conducted at. least once per 12

.. months bet~ the dates of June 1 and October 1, by door-to<oar survey, aerfal survey, ar by consultfng local agrfculture authorf tfes.

roan ear vegetatfan sanplfng may be performed at the sfte boundary fn the dfrectfon sector wfth the hfghest 0/g fn 1 feu of the garden census.

0- C. COOK - UNIT 1 3/4 12-9 Amendment No.

(4 t

RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4 12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA crosscheck program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

D. C. COOK - UNIT 1 3/4 12-10 Amendment No.

T

'I I

l pl ll

3 4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3 4.0 APPLICABILITY LIMITING CONDITIONS FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provide in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place it, as applicable, in:

a. At least HOT STANDBY within the next 6 hours,

b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODES 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

D. C. COOK - UNIT 2 3/4 0-1 Amendment No.

k 4

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3 4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s),

subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification, Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

l. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

This Specification is not applicable in MODES 5 or 6.

SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 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, but

b. The combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed "surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. (This does not apply to surveillances that have been delayed per exemption to Specification 4.0.4.) The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

D. C. COOK - UNIT 2 3/4 0-2 AMENDMENT NO.

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APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.5 Surve1llance Requ1rements for fnservfce inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class I, 2, and 3 compone'nts and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed fn accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Sectfon 50.55a(g), except where specif1c written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

b. Surveillance intervals specified fn Section XI of the ASHE Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASHE Boiler and Pressure Vessel Code arid applicable Addenda shall be applicable as follows in these Technfcal Speciffcatfors:

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for fnservice inspection and testing fns ection and testfn actfvftfes activfties ee y t east once per ays Honthly At least once per 31 days quarter ly 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 provis1ons of Specification 4.0.2 are applicable to the above required frequencies for performfng inservfce inspection and test1ng activities.

d, Performance of the above fnservfce inspection and testing activities shall be fn addition to other specified Surveillance Requirements.

e. Mothfng fn the ASME Bof'ler and Pressure Vessel Code shall be

'onstrued to supersede the requirements of any Technical Specification.

4.0.6 By specific reference to this section, those surveillances which must be performed on or before March 31, 1986, and are designated as 18-month surveillances (or required as outage-related surveillances under the provisions of Specification 4.0.5) may be delayed until the end of the refueling outage scheduled to begin on or before February 28, 1986. For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1986 refueling outage.

Amendment Ho.

D. C. COOK - UNIT 2 3/4 0-3

4~

1

APPLICABILITY SURVEILLANCE RE UIREMENTS 4.0.7 By specific reference to this section, those surveillances which must be performed on or before July 1, 1988 and are designated as 18-month surveillances (or required as outage-related surveillances

-under the provisions of Specification 4.0.5) may be delayed until the end of the cycle 6-7 refueling outage (currently scheduled to begin during the latter part of the second quarter of 1988). For these specific surveillances under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 2 1988 refueling outage.

D. C. COOK - UNIT 2 3/4 0-4 Amendment No.

3 4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE PE UIREMEHTS BASES S ecification 3.0. 1 throu h 3.0.4 establish the general requirements applicable to m>t nq on t ons or peration. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36{c){2):

"Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. i/hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

S ecffication 3.0. 1 establishes the Applicability statement within each n v ua spec cation as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system(s) or component(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when

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equipment is removed from service. In this case, the allowable outage time D. C. COOK - UNIT 2 B 3/4 0-1 Amendment No.

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3/4.0 APPLICABILITY BASES (Continued) limits of the ACTION requ1rements are. applicable when this 11mft expires ff the surveillance has not been completed. 'Hhen a shutdown fs required to comply with ACTION reouirements, the plant may have enter ed a MODE in which a new specification becomes applicable. In this case, the tfme limits of the ACTION requirements would apply from the point in time that the new speci<icatfon becomes applicable 1f'he requirements of the Lfmfting Condition for Operation are not met.

S ecfficatfon 3.0.2 establishes that noncompliance with a specification exists w en t e reau rements of the Limiting Condition for Operatfon are not met and the associated ACTION requirements have not been implemented within the specified time fnter val. The purpose of thfs speciffcat1on is to clarify that (I) fmplementation of the ACTION requirements. within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a L1m1ting Condition of Operation 1s restored within the time interval specfffed in the assocfated ACTION requirements.

S ecfffcatfon 3.0.3 establishes the shutdown ACTION requfrements that must be mp emente w en a Lfmftfng Condition for Operat1on is not met and the condition fs not specffically add~essed by the associated ACTION requirements.

The purpose of th1s speciffcat1on fs to delineate the time lfm1ts for placing the unit in a safe shutdown MODE when plant operation cannot be mafntafned w1thfn the limits for safe operat1on def1ned by the Lfmit1ng Condftfons for Operation and fts ACTION requirements. It fs not contended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from servfce in lieu of other alternatives that would not result 1n redundant systems or components being inoperable. One hour fs allowed to prepare for an orderly shutdown before 1n1tfating a change fn plant operation. This time permits the operator to coordinate the reduct1on fn electrical generation with the load dispatcher to ensure the stability and avaflab11fty of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed fn a controlled and orderly manner that fs well wfth1n the specfffed maximum cooldown rate and within the cooldown capab11itfes of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under condftfons for which this specif1cation applies.

If remedial measures permitting lfmfted continued operatfon of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The tfme limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Conditfon .for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been met or, the time ',imfts of. the ACTION requirements have not expired, thus providing an allowance for the completfon of the required actions.

D. C. COOK - UNIT 2 B 3/4 0-2 Amendment No.

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3/4. 0 APPI I CAB IL I TY BASES (Continued)

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION state-ments for power sources, when a normal or emergency power source is not OPERABLE. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, t~ain, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source. It allows operation. to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoper able solely because of the inoperability of its normal or emergency power source.

For example, Specification 3.S. l. 1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months out-of-service time when one emergency diesel generator is not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This should dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation. However, the provisions of Specificat on 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, action is requi'red in accordance with this specification.

As a further example, Specification 3.8. 1. 1 requires"in part that two physi-.

cal*ly independent circuits between the offsite transmission network and the onsite Class IE distribution system- be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required nffsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consideration. of Specification 3.0.5, all systems, subsystems, trains, components'nd devices

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D. C. COOK - UNIT 2 8 3/4 0-4 Amendment No.

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3/4. 0 APPLlCABILZTY BASES (Continued) supplied by the inoperable normal power sour ces, both of the offsite circuits, would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of Speci fication 3. 0. 5 permit the time limits for continued operation to be consistent with the ACTION statement for the fnoper able normal power sources fnstead, provided the other specified conditions are satisffed. In this case, this would mean that for one division the emergency power source must be OP'ERABLE (as must be the components supp1ied by the emergency power sour"e) and al1 redundant systems, subsystems, trains, components and devices in the other division must be OPERABt E, or likewise satisfy Specification 3.0.5 (i.e., be capable of performing their design functions and have an emerge.~cy power source OPERABLE). In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices fn both divisions must also be OPERABLE. If these conditions are not satisfied, action is required in accordance with this specification.

In MODES 5 or 6, Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

S ecffications 4.0. 1 throuqh 4.0.5 establish the general requirements app ca e to urve ance eou rements, These requirements are based on the Survefllance Requirements stated in the Code of Federal Reoulations, 10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibra-tion, or inspection to assuage that the necessary quality of systems and components fs mafntafned, that facility operatfon will be within the safety limits, and that the limiting conditions of operation will be met."

S ecffication 4.0. 1 establishes the requirement that survefllances must be per orme ur ng t e OPERATIONAL MODES or other conditions for which the requfrements of the Limiting Conditions for Operation apply unless otherwise stated fn an individual Surveillance Requirement. The purpose of thfs speci-fication fs to ensure that survefllances are performed to verify the opera-tional status of systems and components and that parameters are within speci-ffed limits to ensure safe operation of the facility when the plant is fn a NODE or other specified condition for which the assocfated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facflfty is fn an OPERATIONAL MODE for which the requfrements of the associated Lfmitfng Condition for Operation do not apply unless otherwise specfffed. The Survef11ance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception fs used as an allowable exception to the requirements of a specification.

D. C. COOK - UNIT 2 Amendment No.

B 3/4 0-5

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3/4. 0 APPLICABILITY BASES (Continued)

S ecffication 4.0.2 establishes the conditions under which the specified time

~nterva or urve llance Requirements may be extended. Item a. permits an allowable extension of the normal surveillance fnterval to facilitate survefllance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.', transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of ftem a. to ensure that ft is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering iudgment and the recognitfon that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through, surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

S ecification 4.0.3 establishes the failure to perform a Surveillance equsrement wit sn the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the

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OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this

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specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorfly performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance fnterval and that the time limits of the ACTION requirements apply from the point fn time ft fs fdentified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement withfn the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specfffcatfon 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance wfthfn the provisions of Specification 4.0.2 fs a violation of a Technfcal Specification requirement and is, therefore, a reportable event under the requfremen.s of 10 CFR 50.73(a)(2)(f)(B) because It fs a condition prohibited by the plant's Technf'cal Specifications.

D. C. COOK - UNIT 2 B 3/4 0-6 Amendment No.

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3 4.0 APPLICABILITY BASES Continued If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of thi,s allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements. If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated. For surveillances that may be delayed per exemption to Specification 4.0.4, it is expected that the surveillances will be performed expeditiously after entering the applicable mode. However, it is recognized that plant conditions may, at times, cause greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to be required to complete the surveillance.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

S ecification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

D. C. COOK - UNIT 2 B 3/4 0-7 AMENDMENT NO.,

h 3/4.0 APPLICABILITY BASES (Continued)

S ecification 4.0.5 establishes the requirement that inservice inspection of

, 2, and 3 components and inservice testing of ass ASME Code o e Class 1, 2, and 3 pumps and valves shall be performed fn accordance with a periodically updated version of Section XI of the ASME Boilerrequirements and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These apply except when relief has been provided in writing by the Conmissfon.

This specification includes a clarfffcation of the frequencies for performfng the fnservfce inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. Thfs clarification fs provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specfffcation, the more restrictive requirements of the Technfcal Speciffcations take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that fs not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing fts specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

0 D. C. COOK UNIT 2 B 3/4 0-8 Amendment No.

3 3-svtJM ro MINIMUM TOTAL NO. ClfAHNEID CllANHELS APPLICABLE 0 C A E .XRMrKP ~OP '~Q~IE on .s

1. Manual Reactor Trip 1, 2 and *

2. Power Range, Neutron Flux 4 1, 2 and>>

3. Power Range, Neutron Flux 4 1, 2 lligh Positive Rate

i. Power Range, Neutron Flux, 4 1, 2 lligh Negative Rata

5. Intaraediate Range, 1,' and*

Neutron Flux

6. Source Range, Neutron Flux A. Startup 2I and

8.~ Shutdown 3, 4 and 5 7.

~ Overtemparatura .-

hT Four Loop Operation 1, -2

8. Overpower hT Four Loop Operation 1, 2

0

~ TABLE 3.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE n FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ~A~ION nO O 9. Pressurizer Pressure-Low 1, 2 I

10. Pressurizer Pressure High 1, 2 6

11. Pressurizer Water Level High 1I 2 7¹

12. Loss of Flow Single Loop 3/loop 2/loop in 2/loop in (Above P-8) any opera- each opera-ting loop ting loop

13. Loss of Flow Two Loops 3/loop 2/loop in 2/loop in (Above P-7 and below P-8) two opera- each opera-ting loops ting loop

14. Steam Generator Water 3/loop 2/loop in 2/loop in -

1, 2 Level Low-Low any opera- each opera-ting loop ting loop

15. Steam/Feedwater Flow 2/loop-level 1/loop-j.evel 1/loop-level 1, 2 Mismatch and Low Steam coincident and Generator Water Level and'/loop-flow with 2/loop-flow mismatch in 1/loop-flow mismatch or same loop mismatch in 2/loop-level same loop and 1/loop-flow mismatch

~ .

TABLE 3.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION n MINIMUM A TOTAL NO. CHANNELS CHANNELS APPLICABLE O FUNCTIONAL UNIT O OF CHANNELS TO TRIP OPERABLE MODES ~C~ON I

16. Undervoltage-Reactor Coolant 4-1/bus 1 6 Pumps

17. Underfreguency-Reactor 4-1/bus Coolant Pumps 18: Turbine Trip A. Low Fluid Oil Pressure 7¹ B. Turbine Stop Valve Closure 6

19. Safety Injection Input 1, 2 from ESF

20. Reactor Coolant Pump Breaker Position Trip A. Above P-8 1/breaker 1/breaker 10 B. Above P-7 and below P-8 1/breaker 1/breaker 11 per oper-ating loop

21. Reactor Trip Breakers 1, 2 1, 13 3* 4* 5* 14

22. Automatic Trip Logic 1, 2 1 3* 4* 5* 14

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUHENTATION HINIHUH TOTAl. NO. CHANNELS CI IANNELS APPlICABLE FUNCTIONAL UNIT OP CIIANNELS TO TRIP OPL'RABLE HODES 6 HOTOR DRIVEN AUXILIARYPEEDMATER PUHPS

a. Steam Generator Mater -2/Stm. Gen.

Level Low-Low 3/Stm. Gen. any Stm. Gen. 2/Stm. Gen. 1, 2, 3

b. 4 kv Bus 2/Bus 2/Bus 2/Bus 1, 2, 3 Loss of Voltage

c. Safety Injection 2, 3

d. l.oss of Hain Feedwater Pumps

7. TURBINE DRIVEN AUXILIARYPEEDMATER PUHPS

a. Steam Generator 'Mater Level Low-Low 3/Stm. Gen. 'ny 2/Stm. Gen.

2 Stm. Gen.

2/Stm. Gen. 1, 2, 3

b. Reactor Coolant Pump Bus Undervoltage 4-1/Bus 1, 2, 3 S. LOSS OP POHER

a. 4 kv Bus 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 Loss of Voltage

b. 4 kv Bus 3/Bus 2/Bus 2/Bus 1, 2, 3, 4 Degraded Voltage

4 l

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION*

LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a ~ With the number of OPERABLE meteorological monitoring channels less than required by Table 3.3-8, suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel(s) is restored to OPERABLE status.

b. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5,

Shared system with D. C. COOK - UNIT 1 D. C. COOK - UNIT 2 3/4 3-39 Amendment No.

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument(s) is required to be OPERABLE.

ACTION'ith the number of OPERABLE fire detection instrument(s) less than the minimum number OPERABLE requirement of Table 3.3-11:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone(s) with the inoperable instrument(s) at least once per hour, unless the instrument(s) is lo'cated inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

b. Restore the inoperable instrument(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 acti, on t'aken, the cause of the inoperability and the plans and schedule for restoring the instrument(s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.8.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.2 The NFPA Standard 72D Class B supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

DE C. COOK - UNIT 2 3/4 3-50 Amendment No.

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INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a ~ With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, reset, or declare the channel inoperable.

b. With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the applicable ACTION shown in Table 3.3-12.

c. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.9.1 The setpoints shall be determined in accordance with methodology as described in the ODCM and shall be recorded.

4.3.3.9.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

D. C. COOK - UNIT 2 3/4 3-53 Amendment No.

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INSTRUMENTATION RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a ~ With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.2.1 are met, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, reset, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.10.1 The setpoints shall be determined in accordance with methodology as described in the ODCM and shall be recorded.+

4.3.3.10.2 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

This surveillance requirement does not apply to the Waste Gas Holdup System Hydrogen and Oxygen Monitors, as their setpoints are not addressed in the ODCM.

D. C. COOK - UNIT 2 3/4 3-58 Amendment No.

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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a lift setting of less than or equal to 435 psig, or

b. One power operated relief valve (PORV) with a lift setting of less than or equal to 435 psig and the RHR safety valve with a lift setting of less than or equal to 450 psi, or

c. A reactor coolant system vent of greater than or equal to 2 square inches.

APPLICABILITY: When the temperature of one or more of the RCS cold legs is less than or equal to 152 0 F, except when the reactor vessel head is removed.

ACTION:

a. With two PORV's inoperable or with one PORV inoperable and the RHR safety valve inoperable, either restore the inoperable PORV or RHR safety valve to OPERABLE status within 7 days or depressurize and vent the RCS through an at least 2 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until the inoperable PORV or RHR safety valve has been restored to OPERABLE status.

b. With both PORV's inoperable, depressurize and vent the RCS through an at least 2 square inch vent(s) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both PORVs or one PORV and the RHR safety valve have been restored to OPERABLE status.

c. In the event either the PORVs, the RHR safety valve or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days.

The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent(s) on the transient and any corrective action necessary to prevent recurrence'.

C. COOK - UNIT 2 3/4 4-29 Amendment No.

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REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1 APPLICABILITY: ALL MODES ACTION:

With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50 0 F above the minimum temperature 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 component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200 0 F.

With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.

SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

D. C. COOK - UNIT 2 3/4 4-31 Amendment No.

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3 4.7 PLANT SYSTEMS 3 4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE with lift s'ettings as specified in Table 3.7-4.

APPLICABILITY: MODES 1, 2 and 3.

ACTION'.

With 4 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, 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 .

b. With 3 reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODE 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to status or the reactor trip breakers are opened; 'PERABLE otherwise, be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE UIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

D. C. COOK - UNIT 2 3/4 7-1 Amendment No.

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PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator stop valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1 - With one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

MODES 2 - With one steam generator stop valve inoperable, and 3 subsequent operation in MODES 2 or 3 may proceed provided the stop valve is maintained closed.

Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE UIREMENTS 4.7.1.5.1 Each steam generator stop valve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.

4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.

D. C. COOK - UNIT 2 3/4 7-10 Amendment No.

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PLANT SYSTEMS 3 4.7.8 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.8.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of

> 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. Each sealed source with removable contamination in excess of the above limits shall be immediately withdrawn from use and:

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.8.1.1 Test Re uirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.8.1.2 Test Fre uencies - Each category of sealed sources shall be tested at the frequency described below.

a. Sources in use excludin startu sources and fission detectors reviousl sub ected to core flux) - At least once per six months for all sealed sources containing radioactive materials.

D. C. COOK - UNIT 2 3/4 7-34 Amendment No.

PLANT SYSTEMS 3 4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire suppression water system shall be OPERABLE with:

a. Two* high demand pumps, one of which shall be a diesel driven pump, with their discharge aligned to the fire suppression header.

An OPERABLE flow path capable of taking suction from Lake Michigan and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves and the first valve ahead of the hose standpipe or spray system riser or water flow alarm device on each sprinkler, required to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.5.

APPLICABILITY: At all times.

ACTION:

a. With one pump inoperable, restore the inoperable equipment to OPERABLE status within 7 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 plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specification 3.0.3 are not applicable.

With the fire suppression water system otherwise inoperable:

l. Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and

2. Submit a Special Report in accordance with Specification 6.9.2.

a) By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months b) Confirmed by telegram, mailgram or facsimile transmission no later than the first working day following the event, and

Shared system with D. C. Cook - Unit 1 D. C. COOK - UNIT 2 3/4 7-36 Amendment No.

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PLANT SYSTEMS SPRAY AND OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The spray and/or sprinkler systems located in the areas, shown in Table 3.7-5 shall be OPERABLE:

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

ACTION

a. With one or more of the above required spray and/or sprinkler systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas*

in which redundant safe shutdown systems or components could be damaged. 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 inoperabili.ty and the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.2 Each of the above required spray and/or sprinkler systems shall be demonstrated to be 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.

For the reactor coolant pumps preaction sprinklers inside the containment, a closed circuit television located in the lower containment, with periodic monitoring (and hourly logging) of the CCTV screen, shall be an acceptable substitute to an hourly fire watch patrol. For high radiation areas, where closed circuit television coverage does not exist, an hourly fire watch patrol will be instituted.

D. C. COOK - UNIT 2 3/4 7-39 Amendment No.

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PLANT SYSTEMS LOW PRESSURE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.3 The low pressure CO systems located in the areas shown in Table 3.7-6 shall be OPERABLk."

APPLICABILITY: Whenever equipment in the low pressure C02 protected areas is required to be OPERABLE.

ACTION

a. With one or more of the above required low pressure C02 systems isolated for personnel protection, to permit entry for routine tours, maintenance, construction or surveillance testing, verify the operability of the fire detection system as per Specification 4.3.3.8 in the affected area(s) and establish a Roving Fire Watch Patrol (as defined in the Bases Section ) in those areas affected by the isolated C02 system(s). In the event that the Roving Fire Watch patrol cannot be maintained in the affected areas, then personnel must be evacuated and the C02 system returned to IJ its normal condition.

b. With one or more of the above required low pressure C02 systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant safe shutdown systems or components could be damaged; for other areas ensure that back-up fire suppression equipment is available and establish an hourly fire watch patrol.

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.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.3 Each of the above required low pressure CO systems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the C02 storage tank level to be > 50$ and pressure to be > 285 psig, and

b. At least once per 18 months by verifying:

1. The system valves, associated ventilation dampers and self closing fire doors actuate manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a "Puff Test".

D. C. COOK - UNIT 2 3/4 7-42 Amendment No.

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PLANT SYSTEMS HALON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.4 The Halon system located in the Unit 2 Control Room Cable Spreading Area shall be OPERABLE.

APPLICABILITY: Whenever equipment in the Halon protected areas is required to be OPERABLE'CTION:

With the above required Halon system inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify that t'e fire detection system and the backup C02 fire suppression system are OPERABLE; otherwise, establish a continuous fire watch with backup fire suppression equipment for the Control Room Cable Spreading Area. 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 '.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 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.4 The above Halon system shall be demonstrated OPERABLE:

a ~ At least once per 6 months by verifying each Halon storage tank to be > 95% of full charge weight and to be > 90% of full charge pressure.

b. At least once per 18 months by:

1. Verifying the system, including associated ventilation dampers, actuates manually and automatically to a simulated test signal.

2. Performance of an air flow test or CO puff test through headers and nozzles to assure no blockage.

D. C. COOK - UNIT 2 3/4 7-44 Amendment No.

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.9.5 The fire hose standpipe connections in the following locations shall be OPERABLE:

1. Auxiliary Building (minimum 12).

2. Access to Diesel Generators (minimum 1).

3. Access to Switchgear Rooms (minimum 1).

4. Access to Control Room (minimum 1).

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the above required hose standpipe connections inoperable, route an additional equivalent capacity fire hose to the unprotected area(s) from an OPERABLE hose standpipe connection within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Restore the fire hose station 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 plans and schedule for restoring the station to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.5 Each of the above required fire hose standpipe connections shall be demonstrated OPERABLE:

a ~ At least once per 31 days by a visual inspection of the fire hose standpipe connection to assure all required equipment is at the connection.

b. At least once per 18 months by:

D. C. COOK - UNIT 2 3/4 7-45 Amendment No.

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PLANT SYSTEMS 3 4.7.10 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.10 All fire rated assemblies (walls, floor/ceilings, cable tray enclosures) separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire dampers, cable and piping penetration seals, and ventilation seals) shall be OPERABLE.

APPLICABILITY: At all times.

ACTION'a

~ With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within one hour either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire detectors per Specification 4.3.3.8 on at least one side of the inoperable assembly and establish an hourly fire watch patrol or secure in the closed position the inoperable sealing device* and establish an hourly fire watch patrol. Restore the inoperable fire rated assembly and sealing device to OPERABLE status within 7 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 inoperable fire rated assembly and/or sealing device, and the plans and schedule for restoring the fire rated assembly and/or sealing device to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.10.1 At least once per 18 months the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by:

a. Performing a visual inspection of the exposed surfaces of each fire rated assemblies.

b. Performing a visual inspection of each fire damper and associated hardware.

Except fire doors on Turbine Driven Auxiliary Feedwater Pump and Hallway enclosures which cannot be locked closed for HELB considerations.

D. C. COOK - UNIT 2 3/4 7-46 Amendment No.

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REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be

OPERABLE, APPLICABILITY: Whenever irradiated fuel is in the stroage pool.

ACTION'

~ Vith no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within+the storage pool or crane operation with loads over the storage pool until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b. At leAst once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.

2. Verifying that the charcoal adsorbers remove greater than or equal-to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm + 10t.

+ The crane bay roll-up door and the drumming room roll-up door may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

~Shared system with Cook Nuclear Plant - Unit 1,

+ This does not include the main load block. For purposes of this specification, a deenergized main load block need not be considered a load.

COOK NUCLEAR PLANT - UNIT 2 3/4 9-12 AMENDMENT NO.

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RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and

b. During any calendar year to < 3 mrem to the total body and to

< 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9 ', a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be within the above limits.

This Special Report shall also include (1) the results of radiological analyses of the drinking water source, and (2) the radiological impacts on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. (Applicable only if drinking water supply is taken from the receiving water body.)

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once per 31 days.

D. C. COOK - UNIT 2 3/4 11-4 Amendment No.

RADIOACTIVE EFFLUENTS LI UID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 5.1-3) when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit "to the Commission within 30 days pursuant to Specification 6.9 ' a Special Report, which includes the following information:

Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to operable status, and Summary description of action(s) taken to prevent recurrence'he provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.3 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with the ODCM, whenever liquid releases are being made without being processed by the liquid radwaste treatment system.

D. C. COOK - UNIT 2 3/4 11-5 Amendment No.

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RADIOACTIVE EFFLUENTS LI UID HOLDUP TANKS*

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tanks.

APPLICABILITY: At all times.

ACTION:

a ~ With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

D. C. COOK - UNIT 2 3/4 11-6 Amendment No.

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RADIOACTIVE EFFLUENTS DOSE NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in UNRESTRICTED AREAS due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation;

b. During any calendar year, to < 10 mrad for gamma radiation and < 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be within the above limits.

b. The provisions of Specifications 3.0 ' and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.2 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once every 31 days.

D. C. COOK - UNIT 2 3/4 11-10 Amendment No.

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RADIOACTIVE EFFLUENTS DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to A MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas shall be limited to the following:

a. During any calendar quarter to less than or equal to 7.5 mrem to any organ;

b. During any calendar year to less than or equal to 15 mrem to any organ;

c. Less than 0.1% of the 3.11.2.3(a) and (b) limits as a result of burning contaminated oil.

APPLICABILITY: At all times.

ACTION;

a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective action to be taken to assure that subsequent release will be within the above limits.

b. The provisions of Specifications 3,0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.3 DOSE CALCULATIONS Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.

D. C. COOK - UNIT 2 3/4 11-11 Amendment No.

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RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system and the ventilation exhaust treatment system shall be used to reduce the radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas (See Figure 5.1.3) when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas (See Figure 5.1-3) when averaged over 31 days would exceed 0,3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability.

2. Action(s) taken to restore the inoperable equipment to operable status.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.4 Doses due to gaseous releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the ODCM, whenever the gaseous waste treatment system or ventilation exhaust treatment system is not operational.

D. C. COOK - UNIT 2 3/4 11-12 Amendment No.

t, RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to < 3% by volume if the hydrogen in the system is

> 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system > 3S by volume but < 4% by volume and containing > 4%

hydrogen, restore the concentration of oxygen to < 3S or reduce the hydrogen concentration to < 4S within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

b. With the concentration of oxygen in the waste gas holdup system or tank > 4% by volume and > 4% hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to < 3%

or the concentration of hydrogen to < 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months in the system or tank.

c. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS F 11.2.5 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

D. C. COOK - UNIT 2 3/4 11-13 Amendment No."

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RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a ~ With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 4 days by analysis of the Reactor Coolant System noble gases.

-D. C. COOK - UNIT 2 3/4 11-14 Amendment No.

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RADIOACTIVE EFFLUENTS 3 4.11.3 SOLID RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used as applicable in accordance with a PROCESS CONTROL PROGRAM for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

ACTION:

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.

b. With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action(s) taken to restore the inoperable equipment to operable status,

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and

4. Summary description of action(s) taken to prevent a recurrence.

C. The provisions of Specifications 3.0.3 and 6.9.1 ~ 13 are not applicable.

D. C. COOK - UNIT 2 3/4 11-15 Amendment No.

RADIOACTIVE EFFLUENTS 3 4 11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3 '1 '.3.a, or 3.11.2.3.b, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release(s) covered by this report. If the estimated dose(s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this Technical Specification.

b. The provisions of Specifications 3.0.3 and applicable.

6 '.1 ~ 13 are not SURVEILLANCE RE UIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3 and with the ODCM.

D. C. COOK - UNIT 2 3/4 11-17 Amendment No.

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RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION CONTINUED With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by Table 3.12-1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement sa'mples. The locations from which samples were unavailable may then be deleted from Table 3.12-1 provided the locations from which the

'replacement samples were obtained are added to the environmental monitoring program as replacement locations, available.

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d. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.

D. C. COOK - UNIT 2 3/4 12-2 Amendment No..

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPEBATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden+ of greater than 500 square feet producing fresh leafy vegetables in each of the 9 land covering meteorological sectors within a distance of five miles.

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location(s).

b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9 Report which identifies the new location.

The a Special new location shall be added to the radiological 'environmental monitoring program within 30 days, if possible. The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.

c. The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4,12.2 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1, by door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

D. C. COOK - UNIT 2 3/4 12-9 Amendment No.

4 Na J

RADIOLOGICAL ENVIRONMENTAL MONITORING 3 4 12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

The provisions of Specifications 3.0.3 and 6.9.1.13 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.3 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA crosscheck program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

D. C. COOK - UNIT 2 3/4 12-10 Amendment No.

ATTACHMENT 1 TO AEP:NRC:0659M REASONS AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 to AEP:NRC:0659M Page 1 The following is a description of the proposed changes to the Section 6 T/Ss.

T/S 6.1.2 is being added, and places an additional restriction on the Cook Nuclear Plant by requiring the Shift Supervisor or a designated individual during his absence to be responsible for the control room command function. A management directive to this effect signed by the Vice President - Nuclear Operations will be reissued to all station personnel on an annual basis. Designating responsibility for the control room complex places additional restrictions in the T/S and is an improvement to our current T/S. This change is also consistent with Revision 4 and the draft of Revision 5 of the Westinghouse Standard Technical Specifications and T/Ss recently approved for Seabrook - Unit 1, Braidwood - Units 1 and 2, Byron-Units 1 and 2, and Shearon Harris - Unit l.

2) The proposed changes to T/S 6.2.2.b and Table 6 '-1 are being made in order to comply with the requirements of 10 CFR 50.54(m). The proposed T/Ss would require at least one licensed Senior Operator to be in the control room when the facility is in Modes 1, 2, 3 and 4, and would meet the minimum licensed operator staffing requirement that three Senior Operators be on site ~ The Shift Supervisor (SS) has been added to the list in Table 6.2-1 to be consistent with this requirement. These changes allow T/S 6.2.2.c to be deleted, and the paragraphs following T/S 6.2.2.b have been renumbered.

Other changes made to Table 6.2-1 are editorial. The symbols "¹" and "~" used to signify footnotes have been reversed in order to clarify which footnotes apply to the SS. Also the word "Reactor" has been removed from the title "Senior Reactor Operator License." (This change is also made in T/S 6.2.2.d and 6.2.2.g.) This was done to obtain uniformity throughout the'ection 6 T/Ss ~

The proposed changes described above are consistent with Revision 4 of the Westinghouse Standard Technical Specifications and T/Ss recently approved for Vogtle-Unit 1, Shearon Harris - Unit 1, and Seabrook - Unit 1.

3) A footnote has been added to T/S 6.2.2.d and 6.2,2.f (T/S 6.2 '.c and 6 '.2.e in the proposed, revised T/S pages). This change would allow up to two hours for the unexpected absence of an individual qualified in radiation protection procedures and the unexpected absence of the minimum composition of fire brigade members. We believe that this change is reasonable in that provisions for unexpected absences of short duration are necessary. The to AEP:NRC:0659M Page 2 change is also consistent with Revision 4 and the draft of Revision 5 of the Westinghouse Standard Technical Specifications.

4) The proposed changes to T/Ss 6.3.1, 6.4.1, 6.5.2.3, 6.5.2.9, 6.5.2.10.a, 6.5.2.10.b, and 6.5.2.10.c involve necessary title changes. Specifically, we propose to change the "Plant Health Physics Supervisor" to "Plant Radiation Protection Manager," the "Training Coordinator" to "Training Manager,"

and the "Vice Chairman - Engineering and Construction" to "Senior Executive Vice President - Engineering and Construction." This proposed change would make our T/Ss consistent with the current titles used for these positions.

The proposed changes to T/Ss 6.5.1.2, 6.5.1.3 and 6.5.1.5 affect the qualifications, structure, and quorum of the PNSRC.

The proposed change to T/S 6.5.1.2 is to add the minimum qualifications that the PNSRC members and alternate members must meet. Members and alternates will meet or exceed the minimum qualifications of ANSI N18.1-1971, Section 4.4.

Also, plant operations personnel will meet the qualifications of Section 4.2.2 and maintenance personnel will meet the qualifications of Section 4.2.3. This change is an improvement to our current T/S, and was recently approved for Beaver Valley Unit 2.

The PNSRC would consist of the Assistant Plant Managers, Department Superintendents, and personnel reporting directly to the Plant Manager, the Assistant Plant Managers, or Department Superintendents. All members would meet or exceed the minimum qualifications of ANSI N18.1-1971, Section 4.4.

In addition to the Chairman, the PNSRC membership will consist of a minimum of one individual from each of the functional areas designated in T/S 6.5.1.2. The Quality Control Department for the Cook Nuclear Plant is known as the Safety & Assessment Department. This would eliminate the need to make a T/S change when the company is reorganized or a member has a title change, but will maintain the consistency and expertise of the committee. The Plant Manager would appoint the chairman, members, and alternate members, but would not be a member of the PNSRC himself (the current T/S designates the Plant Manager as the chairman of the PNSRC). This change would establish the PNSRC as a more independent advisory organization to the Plant Manager, instead of requiring the Plant Manager's direct involvement in the work activities of the PNSRC. This change requires that T/S 6.'5.1.3 be revised since the PNSRC Chairman would no longer appoint the alternate members. We believe this to be an improvement to our current T/S. This change is similar to T/Ss approved for Vogtle Unit 1.

to AEP:NRC:0659M Page 3 Proposed changes to T/S 6 '.1 5 clarify the requirements for

~

a quorum of the PNSRC. The Chairman or his designated alternate and at least half of the members including alternates will be required for a quorum of the PNSRC. The restriction that only two alternates are allowed to make up the quorum has been removed from this specification because this restriction is in Specification 6.5.1.3. In Specification 6.5.1.3, the number of alternates that can participate as voting members in the PNSRC is limited to two at any one time. Ve feel this proposed change is an improvement to our current T/Ss as it clarifies the present requirement. This change has also been recently approved in the T/Ss for Beaver Valley Unit 2.

6) The proposed changes to T/Ss 6.5.1 6.a, b, c clarify the

~

subject areas that the PNSRC will review. Specifically, the PNSRC will only perform reviews of subjects that could affect plant nuclear safety or involve an unreviewed safety question. These changes will allow the PNSRC to focus on issues related to plant safety and relieve the PNSRC from the unnecessary burden of reviewing routine or administrative changes. This proposed'change has caused T/S 6 '.1.6.c to be relettered to 6.5.1.6.d.

The criteria of 10 CFR 50.59 state that proposed design changes in the plant and changes in the procedures as described in the FSAR, and tests or experiments not described in the FSAR must be reviewed for an unreviewed safety question if they do not require a change to the T/Ss.

Currently, T/S 6.5.1.7b requires a review per the unreviewed safety question criteria of not only these three areas (design changes, procedure changes and tests or experiments) but also of proposed changes to the T/Ss, the Operating License, and vjolations to the T/Ss and the Operating License. However, only a significant hazards consideration review is performed, as required by 10 CFR 50.92, for proposed T/S and Operating License changes. An assessment of the safety consequences is performed as required by 10 CFR 50 '3, for T/S violations. T/S 6.5.1 7b and

~

T/S 5.1.6d has been clarified accordingly.

Revisions have also been made to T/S 6.5.1 6k to be more

~

consistent with the draft of Revision 5 of the Vestinghouse Standard Technical Specifications and T/Ss recently approved for Seabrook - Unit 1, Shearon Harris - Unit 1, Vogtle - Unit 1 and Callaway - Unit 1.

7) The proposed change to T/S 6.5.1.7.c will require the Vice President - Nuclear Operations to be notified, in addition to the NSDRC, of any disagreements between the PNSRC and the Plant Manager. At the present time, the Vice President-Nuclear Operations is the Chairman of the NSDRC and to AEP:NRC:0659M Page 4 therefore would be notified when the NSDRC was notified; However, this change will ensure the Vice President-Nuclear Operations would be notified in the future if, for whatever reason, the Vice President - Nuclear Operations is not a member of the NSDRC. This change will also make our T/Ss consistent with Revision 4 and the draft of Revision 5 of the Westinghouse Standard Technical Specifications.

8) Changes to T/S 6.5.2.2 are being proposed as a result of the recent reorganization and changes in personnel. The member-ship list has been changed to update the members'itles.

Additional members may be added to the NSDRC by the Senior Executive Vice President - Engineering and Construction.

This will allow us the flexibility of adding qualified personnel to the committee without requiring a T/S submittal.

9) The proposed change to T/S 6.5.2.6 is made to clarify that only the Plant Manager has line responsibility for operation of the facility. This is a clarification of an existing T/S and therefore is considered an improvement.

10) The proposed change to T/S 6.5.2.7.a would eliminate the review by the NSDRC of the safety evaluations of lower-tier plant procedures. The NSDRC's review is redundant to PNSRC review and, historically, a safety concern has never been identified. Therefore, we believe the NSDRC workload in this area is not warranted. The NSDRC will, however, continue to review safety evaluations of the top-tier Plant Manager Instructions, which establish the policies that govern all other plant procedures and changes thereto.

The proposed change to T/Ss 6.5.2.8 h, i, and j (T/Ss 6.5.2.8 g and h on the proposed revised pages) clarifies the NSDRC audit requirements on fire protection. The require-ments that were in T/Ss 6.5.2.8 h, i and j have been rephrased and combined into T/Ss 6.5.2 ' g and h. This change is administrative (for clarification). The change is also consistent with the draft of Revision 5 of the Westing-house Standard Technical Specifications and T/Ss recently approved for the following plants: South Texas - Unit 1, Callaway - Unit 1, Seabrook - Unit 1, Byron - Units 1 and 2, and Vogtle - Unit 1. The paragraphs following T/Ss 6.5.2.8 h, i and j (T/Ss 6.5.2.8 g and h) have only been relettered.

12) The proposed T/S 6..5.3, "Technical Review and Control," has been added to the administrative controls section to ensure that activities affecting nuclear safety will continue to be adequately controlled and that technical reviews will be performed once these activities are removed from the PNSRC responsibilities. Transfer of review and approval to AEP:NRC:0659M Page 5 responsibilities from the PNSRC to appropriate persons/

groups will occur after the Plant Manager approves, in writing, that those persons/groups designated are qualified.

T/S 6.5.3.1.a specifies how procedures required by Specification 6.8, other procedures, and changes to procedures that affect plant nuclear safety are reviewed and approved. The review would be done by a qualified individual/

group other than the individual/group that prepared the procedures or the changes. The Plant Manager will approve administrative procedures, Security Plan implementing proce-dures and Emergency Plan implementing procedures.

Procedures other than those mentioned above will be approved by the appropriate department head as designated in writing by the Plant Manager. Requirements for temporary changes to procedures that do not change the intent of the approved procedures have been included in this specification, Temporary changes will be approved for implementation by two members of the plant staff, at least one of whom holds a Senior Operator license. These requirements for temporary changes to procedures are contained in our current T/Ss under Specification 6.8.3. By including temporary changes to procedures in Specification 6.5.3.1.a, T/S 6.8.3 would be redundant and has therefore been deleted in the proposed T/S pages'/Ss 6.5.3.1.b and 6.5.3.1.c address proposed changes or modifications to plant nuclear safety-related structures, systems, components, and proposed tests and experiments that affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or T/Ss. Each of the above items will be reviewed by a qualified individual/group other than the individual/group who wrote the document, and will be approved prior to implementation by the Plant Manager.

T/S 6.5.3 1 d specifies the individuals who approved the

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reviews performed in accordance with Specification 6.5.3.1.a, 6.5.3.1.b, and 6.5.3.1.c will be members of the plant management staff and will meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions, It is also specified in T/S 6 '.3.led that the review will determine whether or not additional cross-disciplinary review is necessary. T/S 6.5.3.1.e specifies that the review will include a determination of whether or not an unreviewed safety question is involved.

T/Ss 6.5.3.1.f and 6.5.3.1.g specify the review process Plant Security Plan and Emergency Plan and their for'he implementing procedures.

to AEP:NRC:0659M Page 6 T/S 6.5.3.2 will require records of the above activities to be distributed to the Plant Manager and the PNSRC and/or NSDRC for required reviews.

These proposed changes are an enhancement to the existing T/Ss. The addition of Specification 6.5.3 ensures that adequate controls are in place and that technical reviews are performed of activities that affect nuclear safety.

These proposed changes are similar to the T/Ss recently approved for Callaway - Unit 1 and South Texas - Unit l.

13) The proposed changes to T/S 6.6.1 clarify the actions to be taken for reportable events. The proposed specification requires that the Commission be notified and a report submitted as required by 10 CFR 50 '3 in the case of a reportable event. This is not an additional requirement; it is a clarification that 10 CFR 50.73 must apply to reportable events. This proposed change is consistent with the draft of Revision 5 of Westinghouse Standard Technical Specifications and the T/Ss recently approved for South Texas - Unit 1, Callaway - Unit 1, Shearon Harris - Unit 1, Byron - Units 1 and 2, Braidwood - Units 1 and 2, and Seabrook - Unit l.

14) The proposed changes to T/S 6.7.1 clarify the actions to be taken in the event a safety limit is violated. The requirement to have the facility in at least hot standby within one hour has been removed from this specification since Section 2 of the T/Ss. contains the requirement. The requirement to report the safety limit violation to the Commission within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months would be changed to notifying by the NRC Operations Center as soon as possible and 'elephone in all cases within one hour. Paragraphs 6.7.1.c and 6.7.1.d have been relettered to 6.7.1.b and 6,7 alee with no changes to the text. An additional requirement is that restart of the unit would not take place until authorized by the Commission.

The additional requirements and clarifications of these proposed changes are considered an improvement to the existing T/Ss. These changes would make our T/Ss consistent with Revision 4 and the draft of Revision 5 of the Westinghouse Standard Technical Specifications.

15) The proposed changes to T/S 6.8.1 are to delete refueling operations, surveillance and test activities of safety-related equipment, and Fire Protection Program implementation from this list. Appendix A of Regulatory Guide 1.33, November 1972 adequately addresses these items and therefore there is no need to list them as separate items. Due to these items being deleted, the remaining items were relettered.

B to AEP:NRC:0659M Page 7

16) The proposed change to Specification 6 '.2 specifies that temporary changes shall be reviewed prior to implementation.

17) An additional requirement to include documentation of all challenges to the PORVs is proposed to be added to the monthly reactor operating report (T/S 6,9.1.10) ~ Although T/Ss require a report of PORV challenges to be submitted on an annual basis, this monthly requirement has been added to make our T/Ss consistent with Revision 4 of the Westinghouse Standard Technical Specifications. The mailing address to which these reports are submitted has been corrected.

This change is viewed as an enhancement to the current T/Ss.

18) In T/S 6.9.2, additional reference specifications have been added to the activities identified. This proposed change will make this list more complete than the current T/Ss and therefore is considered to be an improvement. Co'rresponding references in Section 3 '/4.0 have been revised to adequately reflect the requirements in Specification 6.9.2 and are included in Attachment 2. Additional editorial changes to the Section 3 '/4.0 pages have been made.

Specifically, to the extent possible, symbols have been written in words for clarification.

19) T/S 6.9.1.13 was deleted by Amendment No. 87. to the Unit 1 T/Ss and Amendment No. 73 to the Unit 2 T/Ss. However, the corresponding references in Section 3.0/4.0 have not been removed. The proposed revised T/S pages delete these references.

The remaining changes are made to correct several editorial errors. A description of these editorial caps' changes is given below.

These changes do not change the intent or meaning of the T/Ss themselves, but are considered to be an improvement in the quality of the T/Ss.

a) In T/S 6.2.2.e (T/S 6.2.2.d in the re~ised pages), the "ALL" should be written as "All," since it is not part of the phrase CORE ALTERATIONS that is defined in Section 1 of the T/Ss. (Words defined in Section 1 should be typed in all )

b) In T/S 6.2.2.f (T/S 6.2.2.e in the revised pages),

"Fire Brigade" was changed'to lower case (fire brigade),

c) Following T/S 6 '.1, the heading FUNCTION was added for clarification.

to AEP:NRC:0659M Page 8 d) In T/S 6 '.2.3, "Alternate Members" and "Temporary Altefnate Members" have been changed to lower case.

e) In T/S 6.5.2.6, "Designated and Temporary Alternates" has been changed to all lower cases.

In T/S 6.7.1, "Safety Limit" was changed to lower case ~

g) T/Ss 6.14, 6.15, and 6.16 have been renumbered to T/Ss 6.13, 6.14, and 6.15. In the current T/Ss, Section 6 '3 had previously been deleted.

h) The index pages for Section 6 have been revised to reflect the proposed changes made in this submittal.

Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:

(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or (3) involve a significant reduction in a margin of safety.

Criterion 1 The changes requested in this letter affect only the Administrative Controls section of the T/Ss. Ve believe the revised Administrative Controls will enhance the safe operation of the Cook Nuclear Plant. Therefore we believe these changes will not involve a significant increase in the probability or consequences of a previously evaluated accident.

Criterion 2 These changes are purely administrative in nature. Plant systems, components and operation will not be altered by these changes. Therefore, we believe this change will not create the possibility of a new or different kind of accident than has previously been analyzed or evaluated.

Criterion 3 Since these changes are administrative in nature, they will not impact the ability of the plant systems and components to perform their safety function. Therefore we believe these changes will not involve a significant reduction in a margin of safety.

to AEP:NRC:0659M Page 9 The Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14780) of amendments considered not likely to involve a significant hazards consideration. The first example is that of a purely administrative change to the T/Ss: for example, a change to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature. We believe that the changes requested in this letter are of the type specified in this example. Since these changes are administrative in nature, they do not reduce a margin of safety, do not increase the probability or consequences of a previously analyzed accident, and do not introduce the possibility of a new accident.

Therefore, we believe these changes do not involve a significant hazards consideration as defined by 10 CFR 50.92.

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization. ~ ~

6-1 Facility Staff 6-1

6. 3 FACILITY STAFF VALIFICATIONS 6.4 TRAINING.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE Function. 6-4 Composition. 6-4 Alternates. 6-5 Meeting Frequency. 6-5 Quorum. 6-5 Responsibilities. 6-5 Authority.. 6-6 Records. 6-6 6..5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE Function....... 6-6 Composition 6-7 Alternate Members. 6-7 COOK NUCLEAR PLANT - UNIT 1 XVII

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Consultants. 6-8 Meeting Frequency.. 6-8 6-8 Quorum.'eviev.

6-8 Audits.... 6-9 Authority 6-10 Records.. 6-10 6.5 ' TECHNICAL REVIEW AND CONTROL. 6-10 6.6 REPORTABLE EVENT ACTION. 6-12 6.7 SAFETY LIMIT VIOLATION.. 6-12 6.8 PROCEDURES.. 6-12 6.9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS.. 6-13 6.9.2 SPECIAL REPORTS 6-17 6.10 RECORD RETENTION 6-18 6.11 RADIATION PROTECTION PROGRAM.. 6-19 6.12 HIGH RADIATION AREA. 6-19 6.13 PROCESS CONTROL PROGRAM PCP 6-20 6.14 OFFSITE DOSE CALCULATION MANUAL ODCM 6-21 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6-21 COOK NUCLEAR PLANT - UNIT 1 XVIII

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization. 6-1 Facility Staff 6-1 6.3 FACILITY STAFF UALIFICATIONS 6-4 6.4 TRAINING. 6-4 6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE Function. 6-4 Composition. 6-4 Alternates. 6-5 Meeting Frequency. 6-5 Quorum. 6-5 Responsibilities 6-5 Authority 6-6 Records. 6-6 6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE Function. 6-6 Composition ~ ~ ~ ~ ~

' ~ ~ ~ ~ 6-7 Alternate Members. 6-7 COOK NUCLEAR PLANT - UNIT 2 XVII

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Consultants 6-8 Meeting Frequency. 6-8 Quorum. 6-8 Review 6-8 Audits 6-9 Authority.. 6-10 Records. 6-10 6.5.3 TECHNICAL REVIEW AND CONTROL. 6-10 6.6 REPORTABLE EVENT ACTION 6-12 6.7 SAFETY LIMIT VIOLATION. 6-12 6.8 PROCEDURES 6-12 6.9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS 6-13 6.9.2 SPECIAL REPORTS 6-17

'6.10 RECORD RETENTION. 6-18 6.11 RADIATION PROTECTION PROGRAM. 6-19 6.12 HIGH RADIATION AREA. 6-19 6.13 PROCESS CONTROL PROGRAM PCP 6-20 6.14 OFFSITE DOSE CALCULATION MANUAL ODCM 6-21 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6-21 COOK NUCLEAR PLANT - UNIT 2 XVIII

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6,1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the control room complex, a designated individual) shall be responsible for the control room command function. A management directive to this effect signed by the Vice President - Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATIONS 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

Lines of authority, responsibility, and communication shall be established and defined for the highest management level through intermediate levels to and including all operating organization positions. These relationships shall'e documented and updated, as appropriate, in the form of organizational charts. These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

The Vice President - Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance', however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

FACILITY STAFF 6.2.2 The Facility organi,zation shall be, subject to the following:

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

COOK NUCLEAR PLANT - UNIT 1 6-1 AMENDMENT NO.

ADMINISTRATIVE CONTROLS

b. At least one licensed Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in Mode 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room.

c. An individual qualified in radiation protection procedures shall be on site when fuel i's in the reactor.

d. All CORE ALTERATIONS shall be directly supervised by a licensed Senior Operator trained or qualified in refueling and CORE ALTERATIONS (SO-CA) who has no other concurrent responsibilities during this operation.

A site fire brigade of at least 5 members shall be maintained onsite at all times. The fire brigade shall not include 3 members !

of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

f. The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter 82-12).

g. The Shift Supervisor, Assistant Shift Supervisor, and Unit Supervisor shall hold a Senior Operator License.

h. The Operations Superintendet must have held a Senior Operator License at Cook Nuclear Plant or a similar reactor.

The individual qualified in radiation protection procedures and the composition of the fire brigade may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence provided immediate action is taken to positions.

fill the required COOK NUCLEAR PLANT - UNIT 1 6-2 AMENDMENT NO.

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION*

LICENSE APPLICABLE MODES CATEGORY 1,2,3 6i 4 56 6 SS

- 1

- +

SOL 1 None OL 2 1 Non-Licensed 5* 1 Shift Technical.Adv. 1 None Does not include the licensed Senior Operator - CA supervising CORE ALTERATIONS.

Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

Shared with Cook Nuclear Plant Unit 2.

COOK NUCLEAR PLANT - UNIT 1 6-3 AMENDMENT NO.

ADMINISTRATIVE CONTROLS 6' FACILITY STAFF UALIFICATIONS 6.3 ' Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents'.4 TRAINING 6 '.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and of 10 CFR Part 55.

6.4.2 A training program for the fire brigade shall be maintained under the direction of the Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSRC shall be composed of Assistant Plant Managers, Department Superintendents, or supervisory personnel reporting directly to the Plant Manager, Assistant Plant Managers or Department Superintendents from the functional areas listed below:

Licensing Activities Technical Support Safety 6 Assessment Radiation Protection Operations Maintenance The Chairman, his alternate and other members and their alternates of the PNSRC shall be designated by the Plant Manager. In addition to the Chairman, the PNSRC membership shall consist of a minimum of one individual from each of the areas designated above.

PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

COOK NUCLEAR PLANT - UNIT 1 6-4 AMENDMENT NO.

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 No more than two alternates shall participate as voting members in PNSRC activities at any one time.

MEETING FRE UENCY 6.5.1.4 The PNSRC 'shall meet at least once per calendar month and as convened by the PNSRC Chairman or his designated alternate.

UORUM 6.5.1.5 A quorum of the PNSRC shall consist of the Chairman or his designated alternate and at least three members including 'alternates.

RESPONSIBILITIES 6.5.1.6 The PNSRC shall be responsible for:

Review of all Plant Manager Instructions (PMIs) and revisions thereto.

Review of safety evaluations for (1) plant site procedures and revisions thereto which affect the nuclear safety of the plant; (2) changes or modifications to nuclear safety-related structures, systems or components; and (3) tests or experiments which affect plant nuclear safety to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59.

c. Review of (1) proposed procedures and revisions to procedures, (2) changes to equipment, systems, or facilities, and (3) proposed tests or experiments which may involve an unreviewed safety question as defined in 10 CFR 50.59.

d. Review of proposed changes to Appendix "A" Technical Specifications or the Operating License and rendering determinations in writing with regard to whether or not the proposed change constitutes a Significant Hazards Consideration.

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Chairman of the NSDRC.

Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential nuclear safety hazards'OOK NUCLEAR PLANT - UNIT 1 6-5 AMENDMENT NO.

ADMINISTRATIVE CONTROLS

h. Performance of special reviews, investigations of analyses and reports thereon as requested by the Chairman of the NSDRC.

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

3 ~ Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the NSDRC ~

Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluations, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear Operations and to the NSDRC ~

1. Review of changes to the PROCESS CONTROL PROGRAM, OFFSITE DOSE CALCULATION MANUAL, and radwaste treatment system.

AUTHORITY 6.5.1.7 The PNSRC shall:

a ~ Recommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6 (a) through (d) above.

b. . Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) through (c) above constitutes an unreviewed safety question.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President - Nuclear Operations and the NSDRC of disagreement between the PNSRC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS

,6.5.1.8 The PNSRC shall maintain written minutes of each meeting and copies shall be provided to the Chairman of the NSDRC.

6.5.2 NUCLEAR SAFETY AND DESIGN REVIEW COMMITTEE NSDRC FUNCTION 6.5.2.1 The NSDRC shall function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering COOK NUCLEAR PLANT - UNIT 1 6-6 AMENDMENT NO ~

ADMINISTRATIVE CONTROLS

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices COMPOSITION 6.5.2.2 The NSDRC shall be composed of the following regular members:

1. Vice President - Nuclear Operations (NSDRC Chairman)

2. Section manager, Nuclear Safety and Licensing - Nuclear Operations (NSDRC Secretary)

3. Plant Manager - Donald C. Cook Nuclear Plant

4. Executive Assistant to the President - Indiana Michigan Power Company

5. Senior Executive Vice President - Engineering & Construction

6. Senior Vice President and Chief Engineer

7. Senior Vice President - Electrical Engineering

8. Senior Vice President - Engineering and Design

9. Vice President - Mechanical Engineering

10. Vice President - Project Management and Construction

11. Assistant Vice President - Nuclear Engineering

12. Division Manager - Environmental and Technical Assessment

13. Division Manager - Design

14. Director - Quality Assurance

15. Group Manager - Electrical Systems Additional members and Vice Chairman may be appointed by the Senior Executive Vice President - Engineering and Construction.

ALTERNATES 6.5.2.3 Designated alternate members shall be appointed by the Senior Executive Vice President - Engineering and Construction or such other person as he shall designate. In addition, temporary alternate members may be appointed by the NSDRC Chairman to serve on an interim basis, as required.

Temporary alternate members are empowered to act on the behalf of the regular or designated alternate members for whom they substitute.

COOK NUCLEAR PLANT - UNIT 1 6-7 AMENDMENT NO.

ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSDRC Chairman to provide expert advice to the NSDRC.

6.5.2.5 The NSDRC shall meet at least once per six months.

gUORUM 6.5.2.6 A quorum, the minimum number of regular members and alternates required to hold a NSDRC meeting shall be eight members,'of whom no more than two shall be designated or temporary alternates. The Chairman or acting Chairman+shall be present for all NSDRC meetings. If the number of members present* is greater than a quorum, then the majority participating and voting at the meeting shall not have line responsibility for operations of the facility. For the purpose of a quorum, only the Plant Manager is considered to have line responsibility.

REVIEW 6.5.2.7. The NSDRC is responsible for assuring that independent** reviews of the. following are performed:

a ~ The safety evaluations for 1) changes to Plant Manager Instructions, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.

Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.

d. Proposed changes in Technical Specifications or this operating license.

e. Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

Regular NSDRC members are expected to attend the meeting whenever possible, and alternates may attend as voting members only on an irregular basis. If both a regular member and his alternate attend a meeting, only the regular member may participate as a voting member, and the alternate is considered a guest,

- Independent reviews may be performed by groups which report directly to the NSDRC and which must have NSDRC membership participation.

COOK NUCLEAR PLANT - UNIT 1 6-8 AMENDMENT NO.

t ADMINISTRATIVE CONTROLS

f. Significant operating abnormalities or deviations from normal expected performance of plant equipment that affect nuclear safety.

and

g. All REPORTABLE EVENTS.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components'.

Reports and meeting minutes of the PNSRC.

AUDITS 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the NSDRC. These audits shall encompass:

a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training, and qualifications of the entire facility staff at least once per 12 months.

C. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR SO, at least once per 24 months.

e. The Facility Emergency Plan and implementing procedures .at least once per 12 months.

f. The Facility Security Plan and implementing procedures at least once per 12 months.

g. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel.

h. The fire protection equipment and program implementation at least once per 12 months using either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year.

i, The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.

COOK NUCLEAR PLANT - UNIT 1 6-9 AMENDMENT NO.

ADMINISTRATIVE CONTROLS The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months,

k. The PROCESS CONTROL PROGRAM and implementing procedures for solidification of radioactive wastes at least once per 24 months.

1. The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4 once per 12 months.

', Rev. 1, April 1975 at least

m. Any other area of facility operation considered appropriate by the NSDRC.

AUTHORITY 6.5.2.9 The NSDRC shall report to and advise the Senior Executive Vice President - Engineering and Construction, AEPSC, on those areas of responsibility specified in Sections 6 '.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of NSDRC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSDRC meeting shall be prepared, approved and forwarded to the Senior Executive Vice President - Engineering and Construction, AEPSC, within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6 '.2 ' above, shall be prepared, approved and forwarded to the Senior Executive Vice President - Engineering and Construction, AEPSC, within 14 days following completion of the review.

C. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Executive Vice President - Engineering and Construction, AEPSC, and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.5.3 TECHNICAL REVIEW AND CONTROL 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:

a. Procedures required by Specification 6.8 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved. Each such procedure or procedure change shall be reviewed by a qualified individual/group other than the individual/group which prepared the procedure or procedure change, but who may be from the same organization as the individual/group which prepared the procedure or Procedures other than Plant Manager Procedures procedure'hange.

COOK NUCLEAR PLANT - UNIT 1 6-10 AMENDMENT NO.

ADMINISTRATIVE CONTROLS shall be approved by the appropriate department head as previously designated in writing by the Plant: Manager. The Plant Manager shall approve Security Plan implementing procedures, Emergency Plan implementing procedures and Plant Manager Procedures.

Temporary changes to procedures which do not change the intent of the approved procedures shall be approved for implementation by two members of the plant staff, at least one of whom holds a Senior Operator license, and documented. The temporary changes shall be approved by the original approval authority within 14 days of implementation. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change prior to implementation.

Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager. Each such modification shall be reviewed (reference T/S 6.5.3,lee) by a qualified (reference T/S 6.5.3,1.d) individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group which designed the modifications. Proposed modifications to plant nuclear safety-related structures, systems and components shall be approved prior to implementation by the Plant Manager.

c ~ Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report or Technical Specifications shall be prepared, reviewed, and approved.

Each such test or experiment shall be reviewed by qualified individuals/groups other than the individual/group which prepared the proposed test or experiment to assure cross-disciplinary review as appropriate for the proposed test or experiment.

Proposed tests and experiments shall be approved before implementation by the Plant Manager.

d. Individuals who approved the reviews performed in the accordance with Specification 6.5 '.1a, 6.5.3.1b, and 6.5 3 lc, shall be

~ ~

members of the plant management staff previously designated by the Plant Manager and shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline.

Each review shall include a determination of whether or not an unreviewed safety question is involved. Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to the Plant Manager approval for implementation.

f. The Emergency Plan and implementing procedures shall be reviewed at least once per 12 months. Recommended changes to the COOK NUCLEAR PLANT - UNIT 1 6-11 AMENDMENT NO.

ADMINISTRATIVE CONTROLS plan and implementing procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2.7 and approved by the Plant Manager. NRC approval shall be obtained as appropriate.

g. Recommended changes to the Security Plan and implemeriting procedures shall be reviewed pursuant to the requirements of Specifications 6.5.1.6 and 6.5.2 ' and approved by the Plant Manager. NRC approval shall be obtained as appropriate.

6.5.3.2 Records of the above activities shall be provided to the Plant Manager, PNSRC and/or the NSDRC as necessary for required reviews.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50 '3, and

b. . Each REPORTABLE EVENT shall be reviewed by the PNSRC, and the results of this review shall be submitted to the NSDRC and the Vice President - Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is violated:

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PNSRC. This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.

c. The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Vice President-Nuclear Operations within 14 days of the violation.

d. Operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

COOK NUCLEAR PLANT - UNIT 1 6-12 AMENDMENT NO.

ADMINISTRATIVE CONTROLS

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November 1978.

b. Security Plan implementation.

c. Emergency Plan implementation.

d. PROCESS CONTROL PROGRAM implementation.

e. OFFSITE DOSE CALCULATION MANUAL implementation.

f. Quality Assurance Program for effluent'nd environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and changes thereto, including temporary changes,,shall be reviewed prior to implementation as set forth in Specification 6.5 above.

6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 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 Regional Administrator unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT - UNIT 1 6-13 AMENDMENT NO.

ADMINISTRATIVE CONTROLS 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover 'all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their yssociated man rem exposure according to work and job functions , e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. The complete results of steam generator tube in-service inspections performed during the report period,(reference Specification 4.4.5.5.b).

c. Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.

1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2 This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

COOK NUCLEAR PLANT - UNIT 1 6-14 AMENDMENT NO.

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.

6.9.1.7 The annual radiological environmental operating reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land-use census required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of 3.12-2 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the radiological environmental monitoring. program including sampling methods for each sample type, size, and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sample locations keyed to a table giving distances and directions from one reactor; the result of land-use census required by the Specification 3.12.2; and the results of participation in the Interlaboratory Comparison Program required by Specification 3.12.3.

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Regulatory guide 1.21, "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive 3

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station;however, for units with sep'arate radwaste systems, the submittal shall specify the releases of radioactive material for each unit.

COOK NUCLEAR PLANT - UNIT 1 6-15 AMENDMENT NO

ML17328A114

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