Text

Proposed Tech Specs 3.0.4,4.0.3,4.0.4 & Tech Spec Bases Section 3.0 & 4.0
	ML20151B809
Person / Time
Site:	Clinton
Issue date:	07/11/1988
From:	; ILLINOIS POWER CO.
To:	;
Shared Package
ML20151B798	List: ML20151B809; U-601170, Application for Amend to License NPF-62,revising Tech Specs 3.0.4,4.0.3 & 4.0.4 & Tech Spec Bases 3.0 & 4.0 & Deleting Tech Specs Statements Which Presently Take Exception to Spec 3.04.Fee Paid;
References
	NUDOCS 8807210115
	Download: ML20151B809 (43)
	v • d • e

Attcchment 2 g

, to U-601170 ,

Page 4 of 46 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION

3. 0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specifiect 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 provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

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

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 'CTION 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 OPERATIONAL CONDITIONS 4 or S.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall

, not be made unless the conditions for the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications. J Q a,s.e. wn e ad40 dtd-8807210115 880711 PDR ADOCK 05000461 P PDC CLINTON - UNIT 1 3/4 0-1

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' Attcchment'2 ~)

.to U-601170 Page 5 of 46 3.0.4 Entry into an OPERATIONAL CONDITION.or other specified condition shall not be made when the conditions for the Limiting Conditions 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 CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facilf*y for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.

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Attcchment 2 .'

l ,

. to U-601170

. APPLICABILITY SURVEILLANCE REQUIREMENTS

4. 0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirerrant.

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 Qwa., shall not exceed 3.25 timer the specified surveillance interval.

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4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABI'.lTY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications. Surveillance requirements do not have to be i performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the l (applicablesurveillanceintervalorasotherwisespecified. j 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Coae Class 1, 2, and 3 corponents 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 AStil esiler and Pressure Vessel Code and applicable Addenda as requir ed by 10 CFR 50, Section 50.55a(g), except where specific written relief has been Jranted by the Commission purstant to 10 CFR 50, Section 50.55a(g)(6)(,).

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 inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days CLINTON - UNIT 1 3/4 0-2

i attschr7nt 2 to I-601170

. Page'7 of 46 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. The time limits of the ACTION requirements are applicable ,

at the time it is identified that a Surveillance Reqairement had 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 OPEP.ATIONAL CONDIT.[0N or other specified applicable condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

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Attcchment .1 )

to U-601170 l Pege 8 of 46 APPLICAE!L}TY SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued)

c. The previsions of Specification 4.0.2 are applicable to the abcve re; sired frequencies for performing inservice inspection and testing activities.

d.

Perforeance of the above inservice inspection and testing activities shall be in addition to other specified Surveilla, ice Requirements, to

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

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Attechment 2

, to U-601170 Pcg2 9 of 46 3/t 0 ADPLICAE!LITY BASES Tre 5;t: 3'iratiens of this section previce the gene al require ets a;;1icat'e te ea:n ef t*.e Lieiting Conditions f or C;e'atior. anc Surveilla :e Re1.i e ests within Section 3/4.

3.0.1 Tnis specification states the applicability of each specification in terns of cefined 0:ERATICNAL CONDITION or other specified appiitability cor.-

dition and is provided to delineate spe:ifically when each spe:ification is applicatie.

3.0.2 This spe:ificaticn defines those condition.. necessary to constitute co.t;1iante with the tern of an individual timiting Condition for Operation and associated ACTION require. ment. ,

3.0.3 This specification delintates the reasur:$ to be taken for those circum-stan:es not directly previded for in the ACTION statemet,n and whose occurren:e toule violate the intent of the spe:ification. For exacrple, 5;e:ification 3.7.2 requires two n.ain control room gir conditiuning subsystems to be OPERABLE and previces esplicit ACTICN requirements if one subsystem is inoperable. U der the requireeents of Specification 3.0.3, if both of the required sutsyste.?s are incperatie, ceasures must be initiated within I hour to place the unit in at least STARTU: within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTOM within the f cile.ing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUiD0a'N within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.0.4 This specification provides that entry into an OPERATIONAL CONDITION rust be cade with (a) the f ull com;1erent of required systems, equipeent or k comperents OPERAELE and (b) all other paraceters, as specifiec in the Limiting Conditions for 0;e ation, being met without regard for alle=atie deviations an:

out-?f-service erevisions contained in the ACTION statements.

The intent of this provision is to ensure that unit operation is net initiatec with e ther require: equipre .t or syste-s incperable or other limits being i

excee:ed.

Ex:e;t i ons to this provisien have been provided for a limited r'umter cf spe-cifications when 5thrtup witn inope'able equip'*ent would not af fe:t ;'a t sa'ety. These en:e;tiens a e stated in the ACTION statements of the a::re;riate s:e:ifice: ions.

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Attachment 2 ,

i to U-601170 Page 10 of 46 APPL]CABILITf BASES 4.0.1 This specification provides that surveillance ac.tivities, necessary to ensure the Limiting Conditions for Operation are eet, will be perforced during the OPERATIONAL CONDITIONS or other conditions for which the Limiting Conditions for Operation arc- applicable. Provisions for additional s.-rveillance activities, to be perf ormed without regard to the applicable OPERATIONAL CONDITIONS or other conditions, are provided in the individual Surveiliance j

Requirrtents. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utili:ed as an exception f to an individual specification.

4.0.2 The provisions of this specification provide alle able tolerances for performing surveillanie activities beyond those specified in the nominal M surveillance interval. These tolerances are necessary to provide ep-rnt' -:'

flexibility because of scheduling and perfornance considerations. The phrase "at least" associated with a surveillance frequency does not negate this alle-able tolerance; instead, it permits the mcre frequent performance of surveillance activities.

The tolerance values, taken either individually or consecutively over three test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for deter-mination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation. Under these criteria, equiprent, systers, or corpo-nents are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily perforced within the specified time interval. Nothing in this provision is to be construed as defining equiptent, systems or components OPERABLE, when such items are found or known to be ino;erable although still l eeeting the Surveillance Requirements.

4.0.4 This specification ensures that surveillance activities asscciated with a Limiting Condition for Operation have been perfo-red within the s;eci-fied time interval prior to entry into an applicable OPERATIONAL CONDITION or other specified applicability condition. The intent of this provision is to ensure that surveillance activities have been satisfactcrily det0nstrated on a current basis as required to neet the OPERA!!LITY re:virements of the Liriting Concition for Operation.

L'nce the terms of this specification, f or example, d., ring initial plant star;up or follo.ing extended plant outage, the a;plicable surseillance activi-tie; must be perforced within the stated surveillance interval prior to ;1acirg

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or returning the syst.ee er equipment into OPERABLE status.

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1 Attachnint 2 l i

to U-601170 Page 11 of 46 APPLICAEILITY BASES

4. 0. 5 inis 5:e:if t:aticn ensures that inservice inspe: tion of 15MI Ccce Class 2, 2 ane : c: :ve .ts and inservi:e testing of ASMI Co:e C ass I, 2 e< 3 pe;s and salves will be performed in accorcan:e with a peric:v. ally up; ate:

version of f ection )! of the ASME Boiler and Fressure Vessel Ccde and Addenda, as re;uired by 10 CTR 50, Se: tion 50.55a. Relief from any of the abeve require-trents tas been p cJted in writing by the Com-ission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies of perform-ing the inservice inspection and testing activities required by Section XI of the ASME Boiler ..: Pressure Vessel Code and applicele Ad enda. This clarifi-cation is provide: to ensure consistency in surst'llance inter.als throughout these Technical 5;e:ifications and to ree. ve any ambiguities relative to the frequencies for perforcing the required inservice inspection and testing a:tivities.

Under the terms of thL specification, the m:re restrictive re;. ire erts of the Te:hnical Spe:ifications take pre: eden:e Over the ASME B iler an: Pressure vessel Cede anc a;;1icatie Addenda. For eaa ;1e, the require e .ts of Spe:ifi-cation 4.0.4, to perform surseillance activities prior to entry into an CFERA-T10NAL CO@lTION o- other spe:ified applicability condition, . takes pre: eden:e eser the ASME Boiler anc Pressure Vessel Code provision which alle.s psps to be tested up to one week after return to nornal operation. And, for exampic, the Te:hnical Specification definition of CPERABLE does not g-a t a g a:e period before a de, ice that is not capable of performing it s;e:ifie: function is declared in:;e atie, and takes pre: eden:e eser the ASME Boiler and Fressure Vessel code provision which allo s a sahe te be incapable of ;erforcing its spe:ified functicr for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being de:lared in:pe-a:ie.

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Attachment 2 to U-601170 Page 12 of 46 3/4.0 APPLICABILITY BASES Specifications 3.0.1 through 3.0.4 establish the genercl requirements 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, 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. Wen 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 individual Specification as the requirement for when (i.e. , in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The AC710N requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Ope::ation are not met. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) volund ~y reewal of a system (s) or component (s) from service in l lieu of other alternatives that would not result in redundant systems or components being inoperable. .

There are two basic types of ACTION requirements. The first specifies the ,

remedial measures that permit continued operation of the facility which is not I 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 conforman:e to the conditions of the Limiting Condition for Operation must he ruet. This time limit is the allowable outage time to ,

reatore an inoperable system or component to OPERABLE status or to restore j parameters within specified limits. If these actions are not completed within I the allowable outage time limits, a shutdown is required to place the f acility l in an OPERATIONAL CONDITION or other specified condition in which the l Specification no longer applies. l 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 f rom 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 CLINTON - UNIT 1 B 3/4.0-1

a Attcchment 2 to U-601170 Page 13 of 46 3/4.0 APPLICABILITY BASES equipment is removed from service. In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been cocpleted. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL C0KDITION 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 the Limiting Condition for Operation are not met.

Specification 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) comp?etion 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.

Specification 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 shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements. It ir not intended 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 systees or components being inoperable. One hour is allosed to prepare for an orderly shutdown before initiating a change in 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 specitied to reach lower C0KDITIONS of operation permit the shutdown to proceed *.n a controlled and orderly manner that is well within the specified ;

maximum cooldown rate and within the cooldown capabilities of the facility 1 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 l may be terminated. The time limits of he 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 cor.pletion of the required actions.

CLINTON - UNIT 1 B 3/4.0-2

Attschasnt 2 d to U-601170 Page 14 of 46 3/4.0 APPLICABILITY ,

i 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 !

COLD SHUTDOWN when a shutdown is required during POWER operation . If the plant is in a lower CONDITION of operation when a shutdown is required, the i time limit for reaching the next lower CONDITION of operation applies.

However, if a naver CONDITION of operation is reached in less time than

allowed, the total all: v ble time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced. For example, if STARTUP 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 licit 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 CONDITION of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one Specification results in entry into an OPERATIONAL CONDITION 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 diffarence may be added to the allevable outage time limits of the second Specification. However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower CONDITION of operation.

The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual Specifications define the i remedial measures to be taken.

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Specificatien 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher CONDITION of operstion when the requirements for a Limiting Condition for Operation are not met and continued noncompliance I to these conditions ecold result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this i Specification is to ensure that facility operation is not initiated or that !

higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a Specification by restoring equipment to OPERABLE status or parameters to 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 change in OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL I CONDITION or other specified condition may be cade in accordance with the provisions of the ACTION requirements. The provisions of this Specification should not, however, be interpreted ar endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

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Attcchment 2 )

to U-601170 Page 15 of 46 3/4.0 APPLICABILITY i

! BASES ,

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 CONDITION of operation.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations,10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, 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 for operation will be met."

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Condition for Operation apply unless otherwise stated in an individual Surveillance Requirement. 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 an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requit ements of a Specification.

) Specification 4.0.2 establishes the conditions under which the specified time

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interval for Surveillance Requiretents may be extended. Item "a." permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient l conditions or other ongoing surveillance or maintenance activities. Item "b." I 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. Tb?

limits of Specification 4.0.2 are based on engineering judgement and the ,

recognition that the most probable res"It nf any particular surveillance being performed is the verification of conformance with the Surveillance J Requirements. These provisions are sufficient to ensure that the reliability j ensured through surveillance activities is not signiftcantly degraded beyond that obtained from the specified surveillance interval,

]a Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the i i provisions of Specification 4.0.2, as a condition that constitutes a f ailure i

CLINTON - UNIT 1 B 3/4.0-4

i Attcchment 2 to U-601170 Fage 16 of 46 3/4.0 APPLICABILITY BASES to meet the OPERABILITY requirements for 4 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 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 interval and that the time limits of the ACTION requirements apply from the point in time it is xJentified that a surveillance has not been performed and not at the time that th. 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 f ailure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement actf.on. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requiriments of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable stage 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 would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the 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 CONDITION changes imposed by ACTION requirements and for completing Surveillance Requit eents that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. 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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Attcchment 2 to U-601170 Page 17 of 46 3/4.0 APPLICABILITY BASES )

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION 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 an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant I shutdown as well as startup.

Under tha trovisions of this Specification, the epplicable Surveillance Requirems must Lc performed within the specified surveillance interval to assume th. .ne Limiting Conditions for Operation are met during initial plant startup or 'ollowing 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 CONDITION of operation. i Specification 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 l 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 l Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that 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, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that 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.

CLINTON - UNIT 1 B 3/4.0-6

Attcchment 2

', to U-601170 Pcgs 18 of 46 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE" with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLIC ABI L_I_T,Y: As shown in Table 3.3.1-1.

ACTION:

a. For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdown Position.

1. With one of the four channels required for any Trip Function inoper-able, operation may continue provided the inoperable channel is niaced in the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .jThe provisions of (Specification 3.0.4arenotapplicable.y

2. With two of the four channels required for any Trip function inoper-able, place one channel in the tripped condition within one hour provided no tripped channel for that Trip Function already exists.

Qne provisions of Specification 3.0.4 are net applicable. 2 ' l

3. With three of the four channels required for any Trip function inoperable, take the ACTION required by Table 3.3.1-1.

b. For Reactor Mode Switch Shutdown Position take the ACTION as shown in Table 3.3.1-1. l SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the f requencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS !. hall be performed at least once per 18 months. Reactor protection system di'.isional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST SYSTEM during each refueling outage such that all trip functions are tested at least once every four fuel cycles.** ,

"A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance provided at least two OPERABLE channels are monitoring that parameter.

- Manual testing for the purpose of satisfying Specification 4.3.1.2 is not required until af ter shutdown during the first regularly scheduled refueling outage.

CLINTON - UNIT 1 3/4 3-1

Attcchment 2 to U-601170 Pogo 19 of 46 INSTRUMENTATION 3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.3.2 The containment and reactor vessel isolation control system (CRVICS) channels shown in Table 3.3.2-1 shall be OPERABLE

with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With a CRVICS channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. For CRVICS Main Steam Line Isolation Trip Functions: ,

1

1. With one of the four chan.als required for any Trip Function inopera-ble, operation may continue provided the inoperable channel is placed ,

in the tripped condition within 46 hourjThe provisions of Speci l l

Qication 3.0.4 are not aSnlicable. F l

2. With two of the four channels required tar any Trip Function inopera-ble, place one channel in the tripped co dition within one hour ,

orovided no trioped channel for that Trip runction already exists.

(The provisions of Specificauon J.u.4 are not applicable) # l )

3. With three of the four channels required for any Trip Function inoperable, t&ke the ACTION required by Table 3.3.2-1.

c. For other CRVICS Isolation Trip Ftnctions:

1. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition ** withi 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .J The provisions of Specification 3.0.4 are]

(otapplicable.f

For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance provided at least two OPERABLE channels are monitoring that parameter. .

For other CRVICS Isolation Trip Function, a channel may be placed in an in-operable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance provided the requirements of Table 3.3.2-1 are fulfilled.

- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

CLINTON - UNIT 1 3/4 3-11

Attcchment 2

to U-601170 TABLE 3.3.3-1 (Continued) Pcg2 20 of 46 ,,

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ,

ACTION ACTION 30 - With the number of OPERABLE channels less than requircJ by the Minimum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place th i operable channel in the tripped condition within I hou

or declare the associated system inoperable.

b. With more than one channel inoperable, declare the associated system inoperable.

ACTION 31 - Deleted.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than the Minieur 1 OPERABLE Channels per Trip Function requirement, place the l inoperable channel (s) in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 34 - Deleted.

ACTION 35 - With the number of OPERABLE channels less than required by the i Minimum OPERABLE Channels per Trip Function requirement, restore l the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the associated ADS valve or ECCS inoperable.

ACTION 36 - With the number of OPERABLE channels less than required by the i Minimum OPERABLE Channels per Trip Function requirement:

a. For one trip system, plac M at trip system in the tripped condition within one hou W or declare the HPCS system l inoperable. '

b. For both trip systems, declare the HPCS system inoperable.

ACTION 37 - With the number of CPERABLE channels less than required by the Minimum OPERABLE Channels per Trip function requirement, place at least one inoperable channel in the tripped condition within I hour

or declare the HPCS system inoperable.

ACTION 38 With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specifications 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 39 - With the number of OPERABLE channels one less than the Total Number of Channels, pla the inoperable channel in the tripped condition within I hou , operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 40 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

Restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

% T provisions of Specification 3.0.4 are not applica CLINTON - UNIT 1 3/4 3-38

Attachment 3 [

to U-601170 Page 22. of 46 INSTRUMENT ATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.4.2 The end of-cycle recirculation pump trip (E0C-RPT) system instrumen-tation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is > to 40% of RATED THERMAL POWER.

j

.A.C.T ION:

a. Vith an end-of-cycle recirculation pump trip function instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the :

channel setpoint adjusted consistent with the Trip Setpoint value.

b. With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . p ha orovisions of Soecification 3.0.4 #

[are not applicabley

c. With two of the four chsnnels required for any Trip Function inoperable, place one channel in the tripped condition within one hour Drovided no trippedchannelforthatTrioFunctionalreadyexists.JTheprovisions j G pecification 4.u.4 are not applicablej ,

d. With three of the four channels required for any Trip Function inoperable, reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations at the f requencies shown in Table 4.3. 4. 2-1.

4.3.4.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months. Divisional logic and portions of the channel coincident logic shall ,

be manually tested independent of the SELF TEST SYSTEM during each refueling outage such that all trip functions are tested at least once every four fuel cycles.*

Manual testing for the pu-oose of satisfying Specification 4.3.4.2.2 is not required until af ter shutdown during the first regularly scheduled refueling outage. :

CLINTON - UNIT 1 3/4 3-52

-. - - =

Attechnent 2

to U-601170 Page 22 of 46 INST RUMENT ATION 3/4.3.7 HONITORING INSTRUMENT ATION RADI ATION HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE, with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3.7,1-1.

ACTION:

a. With a radiation monitoring instrumentation channel alarm / trip setpoint exceeding the value shown in Table 3.3.7.1-1, 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 required by Table 3.3.7.1-1.

c. TheprovisionsofSpecification6fi.0.3bnd3.0.kfenotapplicable.

SURVEILLANCE REQUIREMENTS i

4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABL[ by the performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations for the conditions and at the f requencies shown in Table 4.3.7.1-1.

i l

)

i l

a

\

CLINTON - UNIT 1 3/4 3-70

^

Attachment 2 ,

to U-601170 Pega 23 of 46 ;

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

i APPLICABILITY: At all times. ;

ACTION:

i

a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit > hecial Report to the Commission pursuant to Specification 6.9.2 v +' m the next 10 days outlining the cause of the malfunction and the plav- 4 e restoring the instrument (s) to OPERABLE status,

b. The provisions of Specificatic @ 0.3(and 3.0.4]are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event > 0.02g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CAllBRATION perforr.ed within 5 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed i to determine the magnitude of the vibratory ground mction. 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 unit features important to safety l

l l

I 1

i i

i CLINTON - UNIT 3 3/4 3-75 l i

Attachment 2

to U-601170

Peg 2 24 of 46 INSTRUMENT ATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

b. The provisions of SpecificatioMand 3.0.4}re not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of * *a CHANNEL CHECK and CHANNEL CAllBRATION operations at the frequencies shown in T; 'e 4.3.7.3-1.

t 1

I CLINTON - UNIT 1 3/4 3-78

. VI Attcch2nt 2 to U-601170 Paga 25 of 46 INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7 The traversing in-core probe system shall be OPERABLE with:

a. Four movable detectors, drives and readout equipment to map the core and

b. Indexing equipment to allow all four detectors to be calibrated in a common location.

APPLICABILITY: When the traversing in-core probe is used for:

a. Recalibration of the LPRM detectors and

b. Monitoring the APLHGR, LHGR, MCPR, or MFLPD.*

ACTION:

With the traversing in-core probe system inoperable, do not use the system for the above applicable monitorina or calibration functions. The provisions of SpecificatioQ.0.3Jffid 3.0.4)are W not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use when required for the LPRM or calibration functions.

I I

l

0nly the detector (s) in the location (s) of interest are required to be OPERABLE.

CLINTON - UNIT 1 3/4 3-91

L Attach:snt 2

. to U-601170 i-age 26 of 46 INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detection channels shall be OPERABLE with their trip setpoints adjusted to actuate at a chlorine concentration of 1 5 ppm.

APPLICABILITY: All OPERATIONAL CONDITIONS and *.

ACTION:

a. With one chlorine detection channel inoperable, restore the inoperable detection channel to OPERABLE status within 7 days, or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of at least one control ronm emergency filtration system subsystem in the chlorine mode of operation.

b. With both chlorine detection channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of at least one control room emergency filtration system subsystem in the chlorine mode of operation.

The provisions of Specification 3.0.4 are not aoolicable M Q

SURVEILLANCE REQUIREMENTS 4.3.7.8 Each of the above required chlorine detection channels shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

When irradiated fuel is being handled in the secondary containment.

l i

CLINTON - UNIT 1 3/4 3-92

Attach 2nt 2 J to U-601170 L Page 27 of 46 8

INST RUMENT ATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.10 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pur-suant 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. JL --

b. The prnvisions of SpecificatioMnd 3.0.4)are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

l l

CLINTON - UNIT 1 3/4 3-94 .

Attachm:nt 2 to U-601170 Page 28 of 46 ;

I INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive liquid ef fluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be 0FERABLE with their alarm / trip setpoints set l to ensure that the limits of Specification 3.11.1.1 are not exceeded. The <

alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION ,

MANUAL (ODCM).

APPLICABILITY: During releases via this pathway.

ACTION:

a. With a radioactive liquid ef fluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specifi-cation, 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 less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Restore the inoperable instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent ;

Release Report why the inoperability was not corrected in a timely manner. j

c. The provisions of Specificatio and 3.0. not applicable.

SURVEILLANCE REQUIREMENTS !

4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrattd OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the f requencies shown in Table 4.3.7.11-1.

CLINTON - UNIT 1 3/4 3-95

6-At t schzen t 2

', to U-601170 Page 29 of 46 INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.12-1 shall be OPERABLE with their alarm / trip setpoints set ensure that the limits of Specification 3.11.2.1 and 3.11.2.6 are not ceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.12-1.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specifi-cation, immediately suspend the release of radioactive gaseous effluents monitored by the affected char.nel, 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 3.3.7.12-1.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected in a timely canner,

c. The provisions of SpecificatioMand 3.0.4 not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.12 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 4.3.7.12-1.

l CLINTON - UNIT 1 3/4 3-101

q Attachmsnt 2 l to U-601170 Page 30 of 46 '

l REACTOR COOLANT SYSTEM y

3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chenistry of the reactor coolant system shall be saintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: At all times.

ACTION:

a. In OPERATIONAL CONDITION 1:

1. With the condactivity, chloride concentration, or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concen-tration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity less than 10 pmho/cm at 25 C and with the chloride concentration less than 0.5 ppm, this need not be reported to the Commissisii.diind thew Qrovisions ai specification 3.0.4 are not appin.evie#~

2. With the conductivity, chloride concentration, or pH exceeding the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval or with the conductivity and chloride concen- l tration exceeding the limit specified in Table 3.4.4-1, for more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3. With the conductivity exceeding 10 pmho/cm at 25 C or chloride con-centration exceeding 0.5 ppm, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. In OPERATIONAL CONDITIONS 2 and 3 with the conductivity, chloride concen-tration or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. At all other times:

1. With the:

a. Conductivity or pH exceeding the limit specified in Table 3.4.4-1, restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. Chloride concentration exceeding the limit specified in Table 3.4.4-1 restore the chloride concentration to within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or perform an engineering ev'aluation to !

determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation prior to proceeding l to OPERATIONAL CONDITION 3.

CLINTON - UNIT 1 3/4 4-16 l

l

Attcchment 2 '

to U-601170

- REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY .

LIMITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

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

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 af fected component (s) prior to increasing the Reactor Coolant System 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 (s) to within its limit or isolate the affected component (s) from service.

[ The provisions of Specification 3.0.4 are not applicable. A SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5.

CLINTON - UNIT 1 3/4 4-28

Attcchuant 2 '

to U-601170 Page 32 of 46

, REACTOR COOLANT SYSTEM

[0LDSHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 lwo# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless one recirculation pump is in operation, then at least one shutdown cooling mode loop shall be in operation *'## with each loop consisting of at least:

a. One OPERABLE RHR pump, and

b. One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 4.

ACTION:

a. With less than the above required RHR shutdown cooling mode loops OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

b. With no RHR shutdown cooling mode loop or recirculation pump in operation, within one hour establish reactor coolant circulation by an citernate method and monitor reactor coolant temperature and pressure at least once per hour.

(c. The provisions of Specification 3.0.4 are not applicabT %

SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residue.1 heat removal system, recirculation pump, or alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1

0ne RHR shutdown cooling mode loop may be inoperable for up to 2. hours for surveillance testing provided the other loop is OPERABLE and in operation.

The shutdown ccoling pump may be removed from operation for up-to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

1. The shutdown cooling mode loop may be removed from operation during hydrostatic testing.

CLINTON - UNIT 1 3/4 4-31

Attcchment 2

to U-601170 l Page 33 of 46 PLANT SYSTEMS 3/4.7.5 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 10 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 micro-curies of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission Regulations.

h

b. The provisions of Specificatiorp 3 n 3 Gd 3.0.4]are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.5.1 Test Requirements - 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.

4.7.5.2 Test Frequencies - Each category of sealed sources, excluding startup sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below,

a. Sources in use - At least once per six months for all sealed sources containing radioactive material:

i

1. With a half-life greater than 30 days, excluding Hydrogen 3, and

2. In any form other than gas.

b. Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

CLINTON - UNIT 1 3/4 7-15

i

Attechment 2

'. to U-601170

RADIOACTIVE EFFLUENTS Page 34 of 46 (

DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid ef fluents released to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICAPILITY: 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 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance witF. the above limits.

L.-

b. The provisions of Specificatiodh"77bf3}and 3.0.4}are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions f rom liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

l l

CLINTON - UNIT 1 3/4 11-5

Attachment 2 to U-601170 Page 35 of 46 RADI0 ACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE. The appro-priate portions of the system shall be used to reduce the radioactive r.aterials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.

APPLICABillTY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that include", the following information:

1. Explanation of why liquid radwaste was being disebarged without treat-ment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

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

3. Surrary description of action (s) taken to prevent a recurrence.

b. The provisions of Specificatio and 3 0.4 not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be pro- l jected at least once per 31 days in accordance with the methodology and l parameters in the ODCM. l 4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE

l by meeting Specifications 3.11.1.1 and 3.11.1.2.

CLINTON - UNIT 1 3/4 11-6

. Attechnant 2

. to U-601170 Page 36 of 46 RADIOACTIVE EFFLUENTS LIQUID HOLOUP TANKS *

@ lTING CONDITION FOR OPERATION .

3.11.1.4 The quantity of rcdioactive material contained in Lich of the following unprotected outdoor tanks shall be limited to less than or egal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Cycle Condensate Storage Tank

b. RCIC Storage Tank

c. Outside temporary tank APPLICABILITY. At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, irrcediately suspend all additions of radioactive material to the tank, 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, e~ d describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.

b. The provisions of Specificatio and 3 not applicable.

SURVEILLANCE REQUIREMENTS _,

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

l l

I l

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.

CLINTON UNIT 1 3/4 11-7

Attachment 2 i to U-601170 Pege 37 of 46 RADIDACTIVE EFFLUENTS DOSE - NOBLE GASES g

LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or squal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION

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

A.

b. The provisions of Specificatio M and 3.0 3 are not applicable.

SURVEILLANCE REQUIREMENTS .

4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. l 1

l I

l CLINTON - UNIT 1 3/4 11-12

Attschrant 2

.' to U-601170

. RADI0 ACTIVE EFFLUENTS DOSE - 10 DINE-131,10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION r,

3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives gret.ter than 8 days in gaseous effluents released to areas at and beyond the SITE SOUNDARY (see Figure 5.1.3-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

1 APPLICABILITY: At all times. I ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133, tri-tium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous ef fluents exceeding any of the above limits prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above licits,

b. The provisions of Specificatiok0.31and 3.0.4 not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

CLINTON - UNIT 1 3/4 11-13

4 Attcchm2nt 2

to U-601170 Pcge 39 of 46 RADIOACTIVE EFFLUENTS b\

GASEOUS A3CdASTE (OFFGAS) TREATMENT LIMITING CONDITION FOR OPERATION l

3.11.2.4 The GASEOUS RADWASTE (OFFGAS) TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser steam jet air ejector system is in operation.

ACTION:

e

a. With gaseous radsaste from the main condenser air ejector system being discharged without treatment for more than 7 dsys, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

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

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

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

b. The provisions of Specificatio and 3.0. not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.2.4 The GASE0US RADWASTE (0FFGAS) TREATMENT SYSTEM shall be verified to be in operation once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the main condenser air ejector is in use to ensure that the main condenser offgas treatment system is functioning.

CLINTON - UNIT 1 3/4 11-14

Attcch:2nt 2 to U-601170 Page 40 of 46 i .I RADIDACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the pro- (

jected doses due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) would exceed 0.3 mrem to any organ in a 31-day period.

APPLICABILITY: At all times other than when the VENTILATION EXHAUST TREATMENT system is undergoing routine maintenance.

ACTION: :

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

1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

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

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

b. The provisions of Specificatio and 3.0.4 not applicable.

I SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at :

I least once per 31 days in accordance with the ODCM, when the ventilation exhaust treatment system is not in use.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be con-sidered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

CLINTON - UNIT 1 3/4 11-15

Attechnent 2 I to U-601170 Page 41 of 46 j l

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE .

LIMITING CONDITION FOR OPERATION l

3.11.2.6 The concentration of hydrogen in the snain condenser of fgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABILITY: Whenever the main condenser air ejector is in operation.

I ACTION:

a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. TheprovisionsofSpecificatioh.0T31and3.0.4faIenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously monitoring the waste gases in the main condenser offgas treatment system whenever the main condenser evacuation system is in operation with the hydrogen monitors required OPERABLE by Table 3.3.7.12-1 of Specification 3.3.7.12.

l l

6 CLINTON - UNIT 1 3/4 11-16

i Attachn nt 2 i to U-601170 Pap 42 of 46 ,

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTION:

a. With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately pro-cessed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/

or the solid waste system as necessary to prevent recurrence.

b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS C0hiROL PROGRAM, (1) test the improperly processed waste in each container to ensure that it meets the burial ground and shipping require-ments, and (2) take appropriate administrative action to prevent recurrence,

c. The provisions of Specificatio and 3.0.4 e not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g. , filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium :

sulfate solutions) shall be verified in accordance with the PROCESS CONTROL l PROGRAM.

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION l of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be deterrined in accordance with the PROCESS CONTROL PRCGRAM, and a sub-sequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCdSS CONTROL PROGRAM.

b. If the initial test specimen from a batch of waste fails to verify SOLIDI-FICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste.

CLINTON - UNIT 1 3/4 11-18

Attcchnent 2 to U-601170 Page 43 of 46 l

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION t

3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 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 1 3.11.2.3.b, calculations shall be made including direct radiation contri- l butions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If ,

I such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the correc-tive action to be taken to reduce subsequent releases to prevent recur-rence of exceeding the above limits and includes the schedule for achieving '

l conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a HEMBER OF THE PilBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar l year that includes the release (s) covered by this report. It shall also ;

describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the i estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, ,

the Special Report shall include a request for a variance in accordance !

with the provisions of 40 CFR Part 190. Submittal of the report is con-sidered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of Specificatio and 3.0.4 not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous ef fluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2', and 4.11.2.3, and in accordance with the methodology and parameters in the ODCH.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor and from rad aste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a.

CLINTON - UNIT 1 3/4 11-20

Attechm nt 2

, to U-601170

, Page 44 of 46 RADIOLOGICAL ENVIRONMENTAL MONITORING MONITORING PROGRAM LIMITING CONDITION FOR OPERATION (Continued) 3.12.1 ACTION (Continued):

identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

TheprovisionsofSpecification3.0.3{dtn- not applicable.

d.

SURVEILLANCE REQUIREMENTS

' 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

CLINTON - UNIT 1 3/4 12-2

-

Attachment 2 to U-601170 3f Page 45 of 46 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden

of g iater than 50 m 2 (500 ft 2) producing broad leaf vegetation.

For elevated or mixed-mode releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify within a distance of 5 km (3 miles) the location in each of the 16 meteorological sectors of all milk animals and all gardens of greater than 50 m2 producing broad leaf vegetation. ;

APPLICABILITY: At all times.

ACTION: ,

a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calcu-lated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specifica-tion 6.9.1.7.

b. With a land use census identifying a location (s) that 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 accor-dance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s),

excluding the control station location having the lowest calculated dose i or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land l use census was conducted. Pursuant to Specification 6.9.1.7, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

c. The provisions of Specificatio and 3.0.4 e not applicable. I I

i

Broaa leaf vegetation sempling of at least three different kinds of vegetation may be performed at the site boundary in each of two dif fer ent direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Tab?e 3.12-1.4c shall be followed, including analysis of control samples.

CLINTON - UNIT 1 3/4 12-13

Attcch22nt 2 ,,

4 to U-601170 ;

Page 46 of 46 j

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM l LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approver by the Commission, that correspond to samples required by Table 3.12-1.

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 pursuant to Specification 6,9.1.6.

b. The provisions of Specificatio 0.3(and 3.0 h not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

i m

CLINTON - UNIT 1 3/4 12-15 l l

ML20151B809

Text

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