Text

Proposed Tech Specs Changes Per Generic Ltr 87-09
	ML20058N772
Person / Time
Site:	Millstone
Issue date:	08/09/1990
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20058N770	List: B13079, Proposed Tech Specs Changes Per Generic Ltr 87-09; ML20058N767;
References
	B13079, GL-87-09, GL-87-9, NUDOCS 9008150065
	Download: ML20058N772 (36)
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i Docket No. 50-336 B13079 ;

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Attachment 1-Millstone Unit No. 2 Pro >osed Revision to Technical Specifications C1anges Suggested by Generic Letter'87 09 i

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August 1990

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9008150065 900809 PDR ADOCK 05000336 P. PDC

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compl+ance 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 !

I provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the specification 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 l 3. At least COLD SHVTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l Where corrective measures are completed that permit operation under the :

ACTION requirements, the ACTION may be taken in accordance with the i specified time limits as measured-from the time it is identified that a l Limiting Condition for Operation is not met. Exceptions to these requirements '

are stated in the individual specifications.

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 i to them )ermits continued operation of the facility for an unlimited period of time. -111s provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with. ACTION requirements.

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 I unit in a MODE in which the applicable Limiting Condition for Operation does l

not apply by placing it, as applicable, in.

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j. APPLICABILUX LIMITING CONDITION FOR OPERATION'(Continued)

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 . j L

This specification is not applicable in MODES 5 or 6. 4

' SURVEILLANCE REQUIREMENTS , 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

! - 4 . 0 . 7, - Each Surveillance Requirement shall be performed within that specified time interval with:

a. A maximum allowable extension not-to exceed 25% of the surveillance time interval, and

b. The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance' interval,' define 7 Sy Specification 4.0.2, shall constitute a failure to meet the OPERABILIM requirements for a Limiting Condition for Operation. The-time limits o? che 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 the 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 the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. This provision shall not l

prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. !

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 ASME' Code Class 1, 2, and 3 pumps and valves e 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, l Section 50.55a(g)(6)(1).

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L 3/4 LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENT 3

.3/4.0 APPLICABILITY BASES L Specification 3.0.1 throuah 3.0.4. establish the general requirements L applicable;to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code !

of Federal Regulations,10CFR50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. 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." ,

Specification 3.0.1 establishes. the Applicability statement within each -

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-individual: specification as the requirement for when (i.e., in which ,

OPERATIONAL MODES or other specified conditions) conformance to the Limiting 4 Conditions for Operation is required for safe operation of the' facility. The ACTION requirements establish those remedial measures that must be taken wi. thin specified time limits when the requirements'of a Limiting Condition for '

Operation are not met.

There are two basic types of ACTION recuirements. The first specifies the remedial measures that permit continuec 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 4 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 specific time limits of the ACTION i equirements are applicabic from the L point in-time it is identified that.a-Limi;,1ng Condition for O n ration'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 problen.i. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when

equipment 3 removed from service. In this case, the allowable outage time MILLSTONE - UNIT 2 B 3/4 0-1

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t 3/4.0 APPLICABILITY BASES (Con't) limits of ACTION requirements are applicable when this limit expires if the surveillaan W aat been completed. Phen a shutdown is required to comply with AC110N requirements, the plant may have entered a MODE in 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 specification becomes applicable if the requirements of tne Litriting Condition for Operation are not met.-

Soecification 3.0.2 establishes that noncompliance.with a specification exists

' when the requirements 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 '

(1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the r remedial measures-of the ACTION requirements is not required when compliance !

L =with a' Limiting Condition of Operation is restored within-the time interval specified in the associated ACTION requirements.

L Speciiication 3.0.3 establishes the shutdown ACTION requirements'that must be implemented when-a_ Limiting Condition for Operation is not met and the condition 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 operation defined by the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as'an operational convenience which permits (routine) voluntary removal of redundant systems or I components from service in lieu of other alternatives that would'not result in '

redundant systems or components being inoperable. This time permits the operator to coordinate the reduction in elet.trical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower MODES of operation permit the shutdown to proceed in 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 l

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 l may be terminated. The time limits of the ACTION requirements are applicable l from the point in time it is identified that a limiting Condition for Operation is not met. Therefore, the shutdown may be terminated if'the ACTION requirements have been met or the time limits of the ACTION requirements have .l not expired, thus providing an allowance for the completion of the required i actions.

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APPLICABILITY BASES The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the COLD SHVTDOWN MODE when a shutdown is required during the POWER MODE of operation. If the plant is in a lower MODE of operation when a shutdown is required, the time _ limit for reaching the next lower MODE of operation ,

applies. However, if a lower MODE of operation is reached in less time than allowed, the total allowance time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced. - For example, .if HOT STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the '

time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit' a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of ;

operation in less than the total time allowed.

l The same principle applies with regard to the allowable outhge time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for_ .

another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification.becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition '

L for Operation is not met in a lower MODE of operation.

l The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 ;

j and 6, because the ACTION requirements of individual specifications define the remedial measures to M taken. ,

l Specification 3.0.4 establishes limitations on MODE changes when a Limiting

!. Condition for Operation is not met. It-precludes placing the facility in a '

higher MODE of operation when the requirements: for-a' Limiting Condition for -

Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted. The purpose of this saecification is to ensure that facility operation is not initiated or that ligher MODES of operation are not !

L entered when corrective action is being taken to"obtain compliance with a i specification by restoring equipment to OPERABLE' status or parameters to l specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard-to the status of the plant before or after a MODE change. Therefore, in this case, '

entry into an OPERATIONAL MODE or other specified condition may be made in-accordance with the provision of the-ACTION requirements. The provisions of r this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

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APPLICABILITY I l

~ BASES (Con't)

When a shutdown is required to comply with ACTION requirements, the provisions I of Specification 3.03 do.not apply because they would delay placing the facility in a lower MODE of operation. -

Specification 3.0.5 delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements 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, train, 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 inop-erable 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. f diesel generators be OPERABLE. The ACTION statement provides for a 72-hour out-of-service time ' henw 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 would dictate invoking the applicable ACTION statement for each of the applicable Limiting Conditions for Operation. 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 .

L 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 1 power source OPERABLE). If they are not satisfied, action is required in <

accordance with this specification.

As a further example, Specification 3.8.1.1 requires in part that two . 1 I. physically independent circuits between the offsite transmission network and j the onsite Class IE distribution system be OPERABLE. The ACTION statement q provides a 24-hour out-of-service time when both required offsite circuits are 1 not OPERABLE. If the definition of OPERABLE were applied without consider-ation of Specification 3.0.5, all systems,: subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable. This would dictate invoking the applic-able ACTION statements for each of the applicable LCOs. However, the provi-sions of Specification 3.0.5 permit the-time limits for continued operation to l L . MILLSTONE - UNT 2 B 3/4 0-4 F i

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BASES (Con't) be consistent with the ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied. In case, this would mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in 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 satis-fled, action is required in accordance with this specification.

In MODES 5 and 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.

Specification 4.0.1 throuah 4.0.5 establish the general requirements applic-able to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10CFR50.36(c)(3):

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

Soecification 4.0.1 establishes the requirement that surveillances must be performed during the 0PERATIONAL MODES or other conditions for which the i requirements of the Limiting Conditions for_ Operation apply unless otherwise stated in an individual Surveillance Requirements. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERAT10i3L MODE for which the requirements of the associated Limiting Condition for Operaen do not apply unless otherwise specified. The Surveillance Requirements assod W d with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time i interval for Surveillance Requirements may be extended. Item a. permits an allowable extension of the normal surveillance interval to facilitate surveil-l lance 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 item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provi-sions are sufficient to ensure that the reliability ensured through MILLSTONE - UNIT 2 8 3/4 0-5

o 7 3/4.0 APPLICABILITY BASES (Con't) surveillance activities is not significantly degraded beyond that obtained from the specified survei', lance interval.

Soecification 4.0.3 establishes the failure to perform a Surveillance Require-ment within.the allowed surveillance interval, defined by the provisions of -

Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed j 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-and that the time limits of the ACTION requirements .

apply from the point in time it is identified that a surveillance has-not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within 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 surveil-lance interval, defined by the provisions of Specification 4.0.2, was a '

violation of the OPERABILITY requirements of a Limiting Condition for Operation.

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 beenl 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 surveil- ,

lance. The basis for this allowance includes consideration for plant condi-tions, adequate planning, availability of personnel,;the time required to perform the surveillance, and the safety significance' of the delay in complet-ing the required surveillance. 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.

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.

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3/4.0 APPLICABILIT1 )

j BASES-(Con't)

Soecification 4'.0.4 establishes the requirement that all applicable 1 surveillances must be met before entry into an OPERATIONAL MODE or other I condition of operation specified in the Applicability statement. The purpose offthis specification is to ensare that system and component OPERABILITY- I requirements or parameter limits are met before entry into a MODE or condition I 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 es startup.

Under the provisions-of this specification, the applicab1'e 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. H 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, t Soecification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and-valves 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 Commission.

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-is 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 '

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.

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' REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS (Continued)

-LIMITING CONDITION FOR OPERATION (Continued) q b) The CEA group (s)- with the inoperable indicator. is fully inserted, and subsequently maintained < fully inserted, while maintaining the ' . withdrawal?

sequence- and THERMAL POWER- level requireds by Specification !

3.1.3.6' and when this :CEAogroup reaches its fully inserted position, the " Full In": limit of the-CEA with the.

inoperable position indicator.is actuated and verifies- this CEA to be fully inserted. Subsequent operation shall be within the limits of: Specification 3.1.3.6.'. ;

4. If the failure: of.the position ddicator channel (s)11s during STARTUP,- the CEA group (s) with .the inoperable position i indicator channel must be moved to the " Full Out" position and I

verified to be fully withdrawn via aJ " Full Out" -indicator !

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . I

c. With a maximum of one- reed switch ' position ' indicator channel per - 1 group or one _ pulse' counting -position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator <

channel at either its fully inserted position ; or _ fully withdrawn '

position, operation may' continue provided:

1. The position of this CEA is verified immediately 'and 'at least i once per '12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter: by its " Full--In";or " Full Out" l limit (as applicable).

2. The fully inserted CEA group (s) containing' the inoperable position channel is subsequently maintained fully, inserted, and 1

3. Subsequent operation is' within the limits : of;- Specification 3.1.3.6.

d. With 'one or more pulse counting position ind'icator channels inoperable, operation. in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided all of the reed switch : position indicator, channels

-are OPERABLE.

SURVEILLANCE REQUIREMENTS .

4.1.3.3 . Each position indicator channel ..shall be determined -te ~be '0PERABLE i by verifying the pulse counting position indicator channels and the- reed t switch position indicator channels agree within 6 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Deviation circuit is inoperable, then compare the pulse counting position indicator and reed switch position-indicator channels- at-least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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L1J.J.EQ!ilIQR1RLLUINittilAILO!i 8603ATLQL@H110RIE UMITINGCONDITIONFOROPERATION 3.3.3.1 The 3.3-6 limits. shall be OPERABLE withradiation monitoring their alarm / trip setpointsinstrumentation c 6P.fLIQ@lLII_Y.1 withinshown in Table the specified 8CllQti: As shown in Table 3.3-6 a.

value shown in channel Table 3.3-6With a radiation mon alarm

b. within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or, adjust declare thetrip the tpoint se/ t setpoint exceeding the channel inoperable, o within the limit ACTION shown in TabWith one or more radia are not applicable. le 3.3-6 SMEMTS monitoring channels e, take theinoperablTh 4.3.3 on 3.0.3 Each demons.1trated radiation OPERABLE by monitoring the frequencies shown in Table of the 4CHANNEL performanceinstrumentation CALIBRATION channel shall and CH IONAL TEST operations durin

.3-3 CHECK be g the modes a ,nd at theCHANNEL MILLSTONE - UNIT 2 3/4 3-26

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INSTRUMENTATION m 3.4.3~.3 MONITORING INSTRUMENTATIONr <

y RADIATION MONITORING l ,

' LIMITING CONDITION FOR OPERATION' l 3.3.3.1- -The radiation monitoringL ins'trument'ation channels shown 'in - Table J

-3.3-6l shallibe OPERABLE with their alarm /tripisetpoints within the specified limits.

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' APPLICABILITY: ' As' shown in Table 3.3-6.

ACTION:l .

l - a ., Witha~radi$tionmonitoringchannelalarm/tripsetpointexceeding"the ,

--value shownrin Table 3.3-6, adjust the setpoint to'within'the limit- c>

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 'or declare the' channel.Linoperabla.

.b.- 'Withsone or more radiation' monitoring channel $' inoperable, take th'e . !

>> ACTION shown in< Table 3.3-6. , Thel provisions of- Specification 3.0.3 -

' 4 1

are not applicable.

SURVEILLANCE' REQUIREMENTS-11 e, 4 . 3 . 3' .1 - .Each radiation monitoring. .instrumentationi lchannel . shall? be ,

demonstrated . OPERABLE by the performance. of: the: CHANNEL : CHECK, CHANNEL f

CALIBRATION and CHANNEL FUNCTIONAL' TEST operations 1during;the mcdes and at the p

frequencies shown in Table 4.3-3.-

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-MILLSTONE - UNIT 2 3/4 3-26 k

4 . 4r

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,' , (INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued) ,

An OPERABLE quadrant symmetric incore detector segment group shall consist of a mir.imum of three OPERABLE rhodium incore detector srgments in 90*F symmetric fuel assemblies. !

I

.. APPLICABILITY: When.the incore detection system is used for: ;

a. Monitoring the AZIMUTHAL POWER TILT,- l

b. Recalibration of the excore neutron flux detection system, or

c. Monitoring the'UNRODDED' INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate.

ACTION:

With the incore detection system inoperable, do not use the system for- the

' above applicable monitoring or calibration functions. -The provisions ~ of specifications 3.0.3 are' not applicable. ,

SURVEILLANCE REQUIREMENT 4

4.3.3.2 The incore detection system shall be demonstrated OPERABLE:

a. By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use and at least once per 7 days thereafter when required for.:

1. Monitoring the AZlMUTHAL- POWER TILT.

2 Recalibration of the excore neutron flux detection system.

3. Monitoring the UNRODDED INTEGRATED RADIAL PEAKING FACTOR or the

. linear heat rate.

b. At least once per 18 months by performance of. a CHANNEL-CAllBRATION operation which exempts the neutron detectors but-includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core. ;

5 MILLSTONE - UNIT 2 3/4 3-31 Amendment No. AB, # 9 1

l d m ,

j

,4 = INSTRUMENTATION SEISMIC INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 3.3.3.3o The seismic monitoring instrumentation channels shown in Table 3.3-7 i shall be OPERARLE.

APPLICABILITY:- ALL MODES.

ACTION:

a- With the number 'of OPERABLE seismic monitoring channels less than required-by Table 3.3-7, restore the inoperable channel (s) to OPERABLEt status within 30 days. The provisions of Specification 3.0.3 are not applicable,

b. With one or_more seismic monitoring channels inoperable for_more -l than 30 days, prepare and submit a.Special1 Report to the Commission pursuant'to_ Specification 6.9.2 within the next 10 days outlining the cause.oflthe malfunction and the plans for: restoring _the system to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.3.'3.3 Each of the above seismic monitoring instrumentation channels 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.

MILLSTONE - UNIT 2' 3/4 3-32

j 1. j

.L ,

L j I INSTRUMENTATION-1

. 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: -ALL' MODES-

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 thej radwaste gas decay- tanks until: the inoperable channel (s) is: restored ;to OPERABLE' ~ status. The provisions of Specification 3.0.3_are not applicable.

b. 'With one or more .requiped ' 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 .causelofc the;'malfaction and the- plans- for.

y restoring the channel (s) to OPERABLETstatus. 4 SURVEILLANCE REQUIREMENTS

4.3.3.4- Each meteorological monit'oring instr _umentation channel shall ~ be

' demonstrated OPERABLE- by the performance :of the CHANNEL CHECK and CHANNEL '

CALIBRATION operations at the frequencies shown in TABLE 4.3-5.

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.. 1 MILLSTONE - UNIT 2 .3/4 3-36

i i s. 1 [' a t-t INSTRUMENTATION FIRE DETECTION INSTRUMENTATION ~

LIMITING CONDITION FOR OPERATION 3.3.3.7i : As : al minimum, the fire r detection instrumentation for. each fire-detection zone shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: Whenever equipment :in that fire detectica zone is required to' be OPERABLE. .j ACTION:

l With the number of OPERABLE fire detection instrument (s) less than the minimum-- 1 number of OPERABLE requirements of Table 3.3-10:

a. Within 1: hour ' 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 located 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 }

i temperatures? at least once; per hour at the locations listed -in Specification l4'.6.1.5. ;

i b ', ' Restore 'the inoperable instrument (s) to OPERABLE status within .14 days ' or, in" lieu of any 'other report required by Specification '

6.6.1, ' prepare and submit a Special Report- to the' Commission pursuant to Specification 6.9.2 within the -next 30 days outlining i the action taken, 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.-

l SURVEILLANCE REQUIREMENTS q 4.3.3.7.1 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 a1 CHANNEL FUNCTIONAL--TEST.- Fire detectors _

which are not accessible during plant operation shall_ be demonstrated OPERABLE !

by the performance of a CHANNEL FUNCTIONAL 1 TEST :during each COLD SHUTDOWN ,

exceeding 24-hours unless performed in the previous 6 months.

4.3.3'.7.2 The circuitry . associated with- the supervision of -the above fire

. detection instruments - and circuits, per NFPA 72-D, shall be _ demonstrated OPERABLE at least once per 6 months.

4.3.3.7.3 The nonsupervised circuits, associated with detector alarms, between the. instrument and the control room shall be demonstrated OPERABLE at sleast once-per 31 days.

i

. MILLSTONE - UNIT 2. 3/4 3-43 . Amendment No. JE,,JJp, JJJ l

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i

' INSTALLATION. , ,

ACCIDENT MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.8- The accident ' ' monitoring , instrumentation . channels shown -in' Table 3.3-11 shall be OPERABLE.

5 APPLICABILITY: MODES 1, 2, and 3.

ACIIQH: :[

a. . Actions' per-Table- 3.3 ll.

SURVEILLANCE REQUIREMENTS- !

'4.3.3.8- Each~ accident : monitoring instrumentation. channel shall be L

Ldemonstrated ' 0PERABLE . by- performance of the CHANNEL- CHECK' and CHANNEL

-CALIBRATION operations at the frequencies shown in Table 4.3-7.-

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MILLSTONE - UNIT 2 3/4 3-46 Amendment Jhi. EJ !

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i INSTRUMENTATION ,

RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR'0PERATION' '

3'.3.3.9 The radioactive liquid effluent monitoring' instrumentation channels

'shown in . Table 3.3-12; shall-be OPERABLE with applicable' alarm / trip setpoints-settto ensure that the limits of Specification 3.11.1.1 are not exceeded; The "

setpointsi shall: be! determined -- in accordance with - methods and parameters ' as e described in,the 00CM. 1 o

L. , APPLICABILITY: As shown~ in Table 3.3-12. -t

' ACTION:.

a. -With a- radioactive liquid ' effluent monitoring instrumentation-channel ~ alarm / trip setpoint less conservative than required by the above specification, .without delay suspend - the . release of radioactive liquid effluents monitored by the affected channel, or declare the - channel inoperable, or change the setpoint so it is ,

acceptably conservative. '

b.. With the' number of channels less than' the minimum channels operable requirement, take the- ACTION shown -in ' Table 3.3-12. Exert best efforts to restore the inoperable monitor-to OPERABLE status within 30 days and, if unsuccessful, explain in the next . Semiannual Effluent Report why the inoperability was not corrected in a timely manner. Releases need not be terminated after 30' days-provided the specified-actions are continued.

c. The provisions of, Specification 3;0.3 are _not applicable.

l

' SURVEILLANCE REQUIREMENTS 4.3.3.9- Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE.

f CHECK, CHANNEL . CALIBRATION,- and CHANNEL FUNCTIONAL TEST = operations at- the frequencies shown in Table 4.3-12.' . ,

i MILLSTONE - UNIT 2 3/4 3-50 Amendment No. JEA

--. ,-.*- _, +w J ,i, .- t,%, .-y-., - , . ,,-2

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INSTRUMENTATION RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION ,

3.3.3.10 IThe radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall= be OPERABLE with applicable alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.- The setpoints shall be determined in accordance with methods and parameters as.

' described;in the 00CM .

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

.i

a. With a radioactive gaseous effluent monitoring instrumentation l l channel alarm / trip setpoint less conservative.than required by the above specification, without. delay suspend the. release of ,

radioactive- gaseous effluents monitored by the affected channel, or l declare the channel inoperable, or change the L setpoint so it is-acceptably conservative..

'I

b. With the number of channels less than the minimum channels (OPERABLE

- requirement, take the ACTION shown in Table ' 3.3-13. Exert best l efforts to restore the inoperable monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Effluent Report why the -inoperability was not corrected in a timoly l manner. Releases- need.not be terminated after 30 days provided the -

specified actions are continued.

c. The provisions of Specification 3.0.3 are notl applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous 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 4.3-13. ,

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1 4

MILLSTONE - UNIT 2 3/4 3-56 -

Amendment No. J M

.i

. 0 w ..

REACTOR COOLANT SYSTEM-RELIEF VALVES-LIMITING CONDITION FOR OPERATION

.3.4.3- . Two' power operated relief valves (PORVs) and their .associatd block j yalves- shall . be OPERABLE. j

. APPLICABILITY: -MODES-1,-2, and?3.

AQllQH:.

a'. : With' one ori more PORV(s) . inoperable, withinT 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either ' restore-

the PORV(s) -to OPERABLE status or: close the associated block

-valve (s) and remove power from the block valve (s); otherwise, be in

at least HOT STANDBY within the next- 6' hours and in : COLD = SHUTDOWN-

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

r b .' With one or more block' valve (s) inoperable,nwithin 8 ; hours either restore the block valve (s) to OPERABLE status or' close the block -

valve (s)' and remove power from the block ~. valve (s);i otherwise, be in !

at least- HOT STANDBY within' thei next 6- hours and in COLD SHUTDOWN within the following'30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . l SURVEILLANCE REQUIREMENTS l 4.4.3.1 Each PORV shall be demonstrated OPERABLE:

a.- Once per 31 days by performance of' a CHANNEL FUNCTIONAL -TEST, excluding valve operation, and ;

i

b. Once:per IB months by performance of:a CHANNEL CALIBRATION.

i 4.4.3.2 ~ Each block valve shall be demonstrated .0PERABLE once per 92 days by i operating the valve through one: complete cycle of full- travel. This demonstration is not required if -'a PORV block valve is closed and power' removed to meet Specification 3.4.3 a or b.

b

.: MILLSTONE - UNIT 2 3/4 4-3 Amendment No. # , JE, S y

,. 1 REACTORC00EANTSYSTEM SPECIFIC ACTIVITY-LIMITING CONDITION FOR OPERATION 3.4.8' The specific activity of the primary coolant shall be limited to:

a, s 1.0 #Ci/ gram DOSE EQUIVALENT I-131, and b., s'100/E yCi/ gram.

1-APPLICABILITY:~ MODES 1,-2, 3, 4, and 5.

ACTION:

MODES 1, 2, and 3*:

?

a. With-the specific activity of the primary coolant > 1.0 yCi/ gram- '

DOSE EQUIVALENT'I-131 but within-the allowable limit (below and to-the left of the line) shown on Figure 3.4-1, operation may continue for up to 48~ hours. Entry into an OPERATIONAL MODE'or other

'specified condition is permitted pursuant to Specification 3.0.4-when subject to this ACTION statement.

b. With the specific activity of-.the primary coolant > 1.0 pCi/ gram DOSE = EQUIVALENT I-131 for more than'48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be T in HOT STANDBY with Tavg < 515'F within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ..

c. With the specific activity of'the primary coolant > 100/E pCi/ gram, "-

4 be in HOT 1 STANDBY with T,yg < 515'F within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . [

MODES 1, 2~,-3,'4 and 5::

d. With the specific activity of the primary coolant!> 1.0 #Ci/ gram DOSE EQUIVALENT I-131 or > 100/E #Ci/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-2 until the specific activity of the primary coolant is restored to within its limits.

With T,yg 2 515'p,.

l l

I MILLSTONE - UNIT 2 3/4 4-13 Amendment No. Ji, JJJ, JJE

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co .t o .. :

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 l valves (PORVs) with a lift setting'of -t 1 450 psig, or-

b. A reactor coolant.' system vent of A ilL3' square inches.

APPLICABILITY: ~ When the temperature of one or more ;of the RCS cold legs is 1275'F, except when the reactor vessel head-is removed..

ACTION:

a. With one PORV inoperable, either restore the inoperable PORV to OPERABLE status.within 7 days-or depressurize and vent the RCS-through a 2.1.3 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 both PORVs have been- i restored to OPERABLE status.

b. With both PORVs inoperable, depressurize and vent.the RCS through a 2 1.3-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 have been restored to,0PERABLE.

status, c.- In the event either the PORVs 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.

1 l

MILLSTONE - UNIT 2 3/4 4-21a 1

y m - , e w- --g

. l t

- REACTOR COOLANT SYSTEM.

STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION l 1

3.4.10 The structural integrity of ASME. Code Class 1, 2, and 3 components: "

- shall be maintained in accordance with Specification 4.4.10.

APPLICABILITY: ALL MODES

.i '

ACTION:

a .- 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*F above the minimum ,

temperature required by NDT considerations. 4 J

.l

b. With the structural integrity, of.-any ASME Code Class 2 component (s) not conforming to the above requirements,- restore the structural i integrity of the affected component (s) to within .its limit or '

isolate the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the-Reactor Coolant System l temperature above 200*F.

c. 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 to within its limit or ' isolate the affected component from service. .

SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the inspection requirements-for ASME Code Classes 1, 2, and 3 components delineated in ' 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 l', August 1975 -

1 i

MILLSTONE - UNIT 2 3/4 4-22 Amendment No. 79 u

. o RE%CTOR COOLANT SYSTEM-l REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION-FOR OPERATION'

! 3.4.11 At least one reactor coolant system vent path consisting of at least two. valves in series capable of being powered from emergency buses L shall be OPERABLE and closed at each of the, following locations:

a. Reactor Vessel head

b. Pressurizer stream space.

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

ACTION: .

a. With the Pressurizer vent path inoperable, STARTUP and/or. POWER OPERATION may continue provided that 1) the inoperable vent:

l path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path and ii) one power operated relief valve (PORV) and its. associated '

block valve is OPERABLE; otherwise, restore either the ,

inoperable vent path or one PORV _and its associated block valve to OPERABLE status within 30 days, or 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 path to OPERABLE status,

b. With the Reactor Vessel Head vent path . inoperable, STARTUP !

and/or POWER OPERATION may continue provided that the

~

l inoperable vent path: is maintained closed. with power removed

from the valve actuator of all -the valves . in the inoperable vent path; restore the ' Reactor Vessel Head vent path to OPERABLE status within 30 days or submit a Special Report to I 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 path to OPERABLE status.

1 SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1. Verifying all manual isolation valves in each vent path are locked-in the open position.

2. Cycling each valve - in the vent path through at least once y complete cycle-of full travel from the control room during COLD ~

S11UTDOWN or REFUELING. -i

3. Verifying flow through the reactor coolant vent system vent paths during venting during COLD SHUTDOWN or REFUELING.

MILLSTONE - UNIT 2 3/4 4-23 Amendment No. 79, 72, J/E

h v ;

CGMTAINMENT SYSTEMS !

l LMJAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with: i a.- Both doors closed except when the air lock is being used for normal .

transit entry and exit through the containment, then at least one i air lock door shall. be closed, and

'b. An overall air lock leakage rate of_ s 0.05 L, at P, (54 psig).

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

ACTION: ! .

a. = With one containment air lock door inoperable: I

1. Maintain at least the OPERABLE air lock door closed and either- i restore the inoperable air-lock door to OPERABLE status within i 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next-required overall air lock' leakage test provided.that the ,

OPERABLE air lock door is verified to'be locked closed at least once per 31 days.

3. 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 .

4. Entry into an OPERATIONAL MODE or other specified condition L under the provisions of Specification-3.0.4 shall not be.made {

if the inner air-lock door is inoperable,

b. With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed;- restore the inoperable- air lock to OPERABLE status within l 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be.:in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock:shall be demonstrated OPERABLE:

a. After each opening, except when the air lock is being used for 4 multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying no detectable seal leakage be pressure decay when the volume between _

the door seals is pressurized to greater than or equal to 25 psig for at least 15 minutes.

MILLSTONE - UNIT 2 3/4 6-6 Amendment No. #

4

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3 3, _ as 4

i3'/4;7 PLANT SYSTEMS.

3.4.7.1 -TURBINE CYCLE

SAFETY VALVES LIMITING CONDITION FOR OPERATION' i 3.7.1.l All main'. steam line code safety valves shall be _0PERABLE.

APPLICABILITY: . MODES 1, 2, and 3.

j ACTION:

- a .= With -both reactor' coolant loops ' and associated steam generators in; 'l operation. and with. one or more main steam line-code -safety valves '1 inoperable, operation- in MODES zl,- 2, and 3 may proceed provided, :

that- within- 4. hours, either the ' inoperable valve :is .restoi;W to; -

i OPERABLE status "or the Power Level-High' trip setpoint is. n/ aced -

. -per Table ; 3.7-1;- otherwise, be in at least - HOT STANDBY with1h 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 . .i

-SURVEILLANCE REQUIREMENTS 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 Specification 4.0.5.

l MILLSTONE - UNIT 2 3/4 7-1 Amendment No N!, #7 u

.y .-

4.

PLANT SYSTEMS AUXILIARY FEE 0 WATER PUMPS-LIMITING CONDITIONS FOR OPERATION'

-3.7.1.2 At least three ' steam generator _ auxiliary. feedwater pumps- shall be OPERABLE with:

capable : of being

a. Two- feedwater pumps powered from separate-OPERABLE emergency busses,-and One feedwater pump capable- of being powered from an OPERABLE

b. . ' steam ~ supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:-

a. ' With; one auxiliary feedwater pump- inoperable, restore ' the required auxiliary feedwater pumps to OPERABLE status within 72. hours- or be in at least HOT STANDBY within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s- and in H0T.

SHVTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. _ With - two auxiliary feedwater pumps . inoperable be in~ at least 'H0T

~ STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . and in- HOT SHVTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore- at least =one auxiliary feedwater pump to OPERABLE status' as soon as possible. Entry into an OPERATIONAL MODE-. or other specified condition under the provisions of Specification _3' 0.4:- shall not be made 'with three auxiliary feedwater pumps inoperable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump.shall be demonstrated OPERABLE:

a. At least once per 31 days by:

1. Starting each pump from the control room,

'2. Verifying that:

a) Each motor driven pump develops a discharge pressure of 21070 psig on recirculation flow, and b) The steam turbine driven pump develops a discharge pressure of 21080 psig on recirculation flow when the secondary steam supply pressure is greater than 800 psig.

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

1 IMILLSTONE-UNI 3/4 7-4 Amendment No. O , M , S.

1 l

PtANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINAT[DN LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of those quantities of byproduct material listed in 10 CFR 30.71 or 0.1 microcuries, including alpha emitters, shall be free of 10.005 microcuries of removable contamination. ,

APPLICABILITY: AT ALL TIMES.

ACTION: '

a. Each sealed source with removable contamination in excess of the -

above limit 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 REQUIREMENTS ;

4.7.7.1.1 Test Reauirements - 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 Freauencies - Each category of sealed

sources shall be tested at the frequencies described below,

a. Sources in use (excludina startuo- sources or_qyiousiv sub.iected to core flux) - At least once per six months for all sealed sources

containing radioactive material

l MILLSTONE - UNIT 2 3/4 7-19 i 1

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PLANT SYSTEMS-l-

3/4.7.9 FIRE SUPPRESSION SYSTEMS f1RE E PPRESSION WATER SYSTEM:

LIMITING-CONDITION FOR OPERATION .

.1'

, 3.7.9.1 The fire suppression water system shall be OPERABLE with: ,

a. Three . hight pressure-. pumps, each with 'a ' capacity. .of at le~ast 1800 gpm ' with~ their discharge aligned- to the fire ' suppression..

header,, <

i

b. : Two' water . supplies. - each with1 a minimum -contained volume'-of. ;

200,000 gallons, and ' 3

c. An . OPERABLE flow path . capable of. taking. . suction from fthe ~ fire- t water tanks 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 water flow alarm :

device 'on each sprinkler, hose standpipe or spray' system' riser required-to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.3. 3 APPLICABILITY: At: all times.

ACTION:

a. With one pump and/or. one water -supply inoperable, restore the inoperable equipment to OPERABLE status within. 7 dayshor, in lieu of any 'other report required ' by Specification 6.6.1, prepare z and :

submit;a Special Report to the Commission pursuant to: Specification ;

j. 6.9.2 within the next 30 days. outlining:the: plans and procedures to L be used to provide for the loss'of: redundancy-in:this: system.' The l- provisions ~of Specification 3.0.3 are not applicable.>

b. With two pumps. inoperable, est'ablish a continuous fire watch of the I turbine building with backup > fire " suppression equipment- within 1

, hour; restore the' inoperable equipment to :0PERABLE. status within '

L 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 nexti 30 days- outlining the' action taken,-the .cause of the:inoperability and the plans and schedule - for restoring the equipment to '0PERABLE status. The pro /isions of Specification 3.0.3 are not applicable. .

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i MILLSTONE - UNIT 2 3/4 7-33 Amendment No. JJ, f), JJJ sy .f

, ,ftANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The following spray and/or sprinkler systems shall be OPERABLE:

a. Diesel Generator Rooms

b. Diesel Generator Day Tank Rooms

c. Cable Vault (Aux. Building) 1 Sprinkler

2. Deluge A Cable Vault (Turbine Building)

. Hydrogen Seal Oil Unit

f. Turbine Building Northeast Corner

g. Turbine Building 31'6"/14'6" North

h. Turbine Building 31'6"/14'6" - South ,

i. Lube Oil Room

j. Aux. Building (-45'6") General Area

k. Aux. Building (14'6") Truck Access ;

1. Turbine Bearing

m. Steam Generator feed Pumps APPllCABilllY' "benever equipment in the .; pray / sprinkler protected areas is required to a O!AABLE.

ACTION:

a. With one or more of the above required spray and/or ..3tems inoperable, establish a continuous fire watch with backup fire uppression equipment for the unprotected area (s) within I hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission aursuant to Specification 6.9.2 l

wit 11n the next 30 days outlining tie action takeit the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, j t. The provisions of Specification 3,0.3 are not applicable.

S,URVEILLANCE REQUIREMENT ,,

4.7.9.2 Each of the above required spray and/or sprinkler systems shall be demonstrated OPERABLE:

MILLSTONE - UNIT 2 3/4 7-37 Amendment No. M , 9 , JJp, 111

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PLANT SYSTEMS l ElRE HOSE STATIONS !

LIMITING CONDITION FOR OPERATION 3.7.9.3 The fire hose stations shown in Table 3.7-2 shall be OPERABLE. ,

APPLICABILITY: Whenever equipment in the areas protected by the fire hose

stations is required to be OPERABLE.*

ACTION:~ i

a. With' one or more of the fire hose stations shown in Table 3.7-2 inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within I hour or ;

establish a continuous fire watch with backu) fire suppression 1 equipment for the unprotected area (s). If t ie inoperable hose i station (s) is not the primary means of fire suppression, then route l l the additional fire hose (s) or establish a continuous fire watch >

l with fire suppression equipment within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. The prov'isions of Specification 3.0.3 are not applicable, i

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~

SURVEILLANCE REQUIREMENTS 4.7.9.3 Each of the fire hose stations shown in Table 3.7-2 shall be demonstrated OPERABLE: '

a. At least once per 31 days by visual ' inspection of the station to I l asture all required equipment is at the station. The exception to i the above will be the containment hose stations. The equipment will '

be located outside containment except when the unit is in cold !

shutdown.

b. At least once per 18 months by:

1. Removing the hose for inspection and re-racking, ar,d i

2. Replacement of all degraded gaskets in couplings.

1

c. At least once per 3 years by* *

1. Partially opening each hose station valve to verify valve .

OPERABILITY and no flow blockage, j

2. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose i station. ,

i

Containment hose stations shall be operable in MODE 5 when required to i' support maintenance activities and MODE 6.

t MILLSTONE - UNIT 2 3/4 7-39 Amendment No. AB, JJE

, ,PEANT SYSTEMS 3/4.7.10 PENETRATION FIRE BARRIERS LIMITING CONDITION FOR OPERATION 3.7.10 All fire rated assemblies (wall s, floor / ceilings, cable tray enclosures, and other fire barriers) separating safety-related fire areas or separaQg portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventilation duct penetration seals) shall be OPERABLE.

APPLICABILITY: At all times unless otherwise determined that the separation of safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area is not required based on the MODE of operation.

ACTION:

a. With one or more of the above required fire rated assemblies and/or penetration sealing devices inoperable, within I hour: !

1. Determine that the fire areas / zones on both sides of the affected fire rated assembly and/or penetration sealing device are monitored by either an OPERABLE fire detection or automatic suppression system at the fire barrier and establish a fire watch patrol that inspects both areas at least once per hour, E

2. Establish a continuous fire watch on at least one side of the affected fire rated assembly and/or penetration seal, E

? femporarily repair the inoperable fire rated assembly and/or sealing device and classify it as temporary.

All temporary or inoperable fire rated assemblies and/or sealing devites shall be permanently repaired within 30 days, or implement ACTION 1 or 2 above,

b. The provisions of Specification 3.0.3 are not applicable.

( SURVEILLANCE REQUIREMENTS , 4.7.10 The above required fire rated assemblies and penetration sealing g devices shall be verified to be OPERABLE by a visual inspection:

a. At least once per 18 months for fire doors and fire dampers,

b. At least once per 18 months for fire barrier penetration seals, on at least 10% of the total number of penetration seals. If any of the penetration seals in the inspection sample are found to be inoperable, then an additional 10% sample of the total number of penetration seals shall be visually inspected. Sampling and inspection shall continue until all of the seals in a sample ere found OPERABLE or 100% of the seals are inspected,

c. Prior to returning a fire rated assembly and/or penetration sealing j device to OPERABLE status following repairs or maintenance.

MILLSTONE - UNIT 2 3/4 7-41 Amendment No. AB, JJS i

RADIDACTIVE EFFLUENTS DOSE. LIOUIDS LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to any REAL MEMBER OF THE PUBLIC from radioactive materials in liquid effluents from Unit 2 released from the site (see Figure 5.1-1) shall be limited:

a. During any calendar quarter to s 1.5 mrem to the total body and to 1 5 mrem to any organ, and

b. During any calendar year to s 3 mrem to the total body and to 1 10 mrem to any organ.

APPLICABILITY: At all times, i

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 6.9.2, a Special Re> ort which identifies the cause(s) for exceeding the limit (s) and cefines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during tl.e remainder of the calendar year so that the cumulative dose or dose commitment to any REAL MEMBER OF THE PUBLIC from such releases during the calendar year is within 3 mrem to the total body and 10 mrem to any organ,

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS ,, , 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 11 of the REM 0DCM.

4.11.1.2.2 Relative accuracy of conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REMODCM.

a MILLSTONE - UNIT 2 3/4 11-2 Amendment No. Jpf -l

)

~ .

i RADIOACTIVE EFFLUENTS j DOSE. NOBLE GASES l

SURVEILLANCE REQUIREMENTS l 3.11.2.2 The air dose offsite (see Figure 5.1-1) due to noble gases released from Unit 2 in gaseous effluents shall be limited to the following: i

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

, b. During any calendar year, to s 10 mrad for gamma radiation and !

1 20 mrad for beta radiation. l APPLICABIllTY: At all times. .

ACTION: :

1 !

a. 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 i Special Report which identifies the cause(s) for exceeding the ,

limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the ,

remainder of the current calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation. '

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS , 4.11.2.2.1 Dose Calculations. Cumulative dose contributions for the current '

calendar quarter and current calendar year shall be determined in accordance :

with Section II of the REM 0DCM once every 31 days.

4.11.2.2.2 Relative accuracy or conservatism of the calculations shall be !

confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I of the REM 00CM. ;

n t

i MILLSTONE - UNIT 2 3/4 11-4 Amendment No. J9f. .

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ge

RADI0 ACTIVE EFFLUENTS DOSE. RADIOI0 DINES. RADIDACTIVE MATERIAL IN / ARTICULATE FORM. AND BSD10NUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to any REAL MEMBER OF THE PUBLIC from iodine 131, iodine-133, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents from Unit 2 released offsite (see Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter to 5 7.5 mrem to any organ;

b. During any calendar year to s 15 mrem to any organ.

APPLICABILITY: At all times. I ACTION:

a. With the calculated dose from the release of radiciodines, radioactive materials in particulate form, or radionuclides other than 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 to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any REAL MEMBER OF THE PUBLIC from such releases during the calendar year is within 15 mrem to any organ,

b. The provisions of Specification 3.0.3 are net applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Date Calculationi. Cumulative dose contributions for the- current o

calendar quarter and current calendar year shall bs determined in accordance with Section 11 of the REMODCM once every 31 days.

4.11.2.3.2 Relative accuracy or conservatism of the calculations shall be i confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section I of the REMODCM.

l i

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MILLSTONE - UNIT 2 3/4 11-5 Amendment No. JSA j

_ . _ _ _ _j

E ,

4

RADIOACTIVE tFFLUENTS 3/4 11.3 TOTAL DOSE I

LIMITING CONDITION FOR OPERATION 7'

3.11.3 The dose of dose commitment to a REAL MEMBER OF THE PUBLIC from the Millstone Site is' limited to s 25 mrem to the total body or any organ (except the thyroid, which is limited to 5 75 mrem) over a period of 12 consecutive months.

. APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2, 3.11.2.2, or 3.11.2.3, prepare and submit a Special Report to the Commission aursuant to Specification 6.9.2 and limit the subsequent releases suc1 that the dose.or dose commitment to any REAL MEMBER OF THE PUBLIC from the Millstone Site is limited to s 25 mrem to the total body or any organ (except thyroid, which is

. limited to s 75 rem) over 12 consecutive months. This *pecial Report shall include an analysis which demonstrates that radiation exposures to any REAL MEMBER OF THE PUBLIC from the Millstone Site (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard. If the estimated doses exceed the above limits, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete,

b. The provisions of Specification 3.0.3 are not applicable.

SVRVEILLANCE REQUIREMENTS 4.11.3 Dose Calculations. Cumulative dose contributions from liquid and gaseous effluents and direct radiation from . the Millstone Site shall be determined in Specifications 4.11.1.2.1, 4.11.2.2.1 and 4.11.2.3.1 and in accordance with Section II of the REMODCM once per 31 days.

MILLSTONE - UNIT 2 3/4 11-6 Amendment No. Jpf J

v t e Letter Sequence Request
TAC:77535, (Open)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval... Other: A09139, Advises That Util Will Respond to NRC Re Generic Ltr 87-09 by 910115
MONTHYEAR1990-08-09 [Table View]

B13079, Proposed Tech Specs Changes Per Generic Ltr 87-09

Text

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