Text

Proposed Tech Specs,Incorporating Recommendations of NRC Generic Ltr 87-09 Re Sections 3.0 & 4.0
	ML20147B726
Person / Time
Site:	Mcguire, Catawba, McGuire, 05000000
Issue date:	01/11/1988
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20147B723	List: ML20147B721; ML20147B726;
References
	GL-87-09, GL-87-9, NUDOCS 8801150311
	Download: ML20147B726 (120)
	v • d • e

ATTACHMENT 2 PROPOSED MCGUIRE TECHNICAL SPECIFICATION CHANGES l

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8801150311 880111 PDR ADOCK 05000369 PDR p

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J 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMFNTS 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 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 provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a. At least HOT STAN0BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

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

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

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

This specification is not applicable in MODE 5 or 6. ok when 3.0.4 Entry nto an OPERATIONAL MODE or other specified condition shall notet igg be made er.1=: the conditions for the Limiting Condition for Operation This are T-

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with = t re!! = : er previci=: centained " the SCTICP FCoA provision shall not prevent passage through or to OPERATIONAL MODES as cr.x1 required to comply with ACTION requirements.

Exceptions to these requirements c are stated in the individual specifications. g 3.0.5 Limiting Conditions for Operation including the associated ACTION requirements shall apply to each unit individually unless otherwise indicated as follows:

a. Whenever the Limiting Condition for Operation refers to systems or components which are shared by both unitn, the ACTION requirements will apply to both units simultaneously. This will be indicated in the ACTION section;

b. Whenever the Limiting Condition for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and

c. Whenever certain portions of a specification contain operating parameters, setpoints etc., which are different for each unit, this will be identified in parentheses or. footnotes. (For example,

"...ficw rate of 54,000 cfm (Unit 1) or 43,000 cfm (Unit 2)...").

McGUIRE - UNITS 1 and 2 3/4 0-1

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INSERT FOR SPECIFICATION 3.0.4.

and the associatid 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 v'.ch ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

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

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

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

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

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, j q Spd edios 4.0,L, 4.0.3 Failure) to perform a Surveillance Requireme ithinthe[p:ified 44ae interval /shall constitute : f:ihr: t: :::t the OPERABILITY requirements for a Limiting Condition for Operation. 5 ption; to th :: requirc::nt; + $564T cr :tated in th indi.idual :p; i'i:: tion:. Surveillance Requirements do sg.oM not have to be performed on inoperable equipment. Ac.-T 9A 6 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 I

Condition for Operation have been performed within the stated surveillance interval or as otherwise spec 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:

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

5 prevision ,5h(( nd gged o>.saj c fra ce c)

OM*L M@Es a r regwnd do wp/y adf blTIDa regWremnf, McGUIRE - UNITS 1 and 2 1/4 0-2

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s INSERT FOR SPECIFICATION 4.0.3 The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit 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 .

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No bn]c,5 On D ho]. c APPLICA8ILITY SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued)

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 for Code and applicable Addenda performing insarvice terminology for inservice inspection and testing insoection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frecuencies for performing inservice inspection and testing activities;

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements; and

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

4.0.6 Surveillance Requirements shall apply to each unit individually unless othe mise indicated as stated in Specification 3.0.5 for individual specifica-tions or whenever certain portions of a specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.

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l McGUIRE - UNITS 1 and 2 3/4 0-3

WQ 3/4.0 APPLICABILITY

-c#g (4f yuh G.6 BASES I

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The specifications of tpis section provide the general requirements b licable to each of the LiAiting Conditions for Operation and Surveillance Req rements within Section 3/4.

This specification defines the applicability of each specif f tion $

3. 0. i in terms o efined OPERATIONAL MODES or other specified conditions and is

e. l provided to de 'neate specifically when each specification is applica r i

3.0.2 This sp ification defines those conditions necessary o constitute i compliance with the t ms of an individual Limiting Condition fo Operation !

and associated ACTION r uirement. !

delineates the measures to b taken for those j 3.0.3 The specificati i circumstances not directly pr ided for in the ACTION st ements and whose occurrence would violate the in nt of a specification. For example, Speciff- l cation 3.5.2 requires two indepen ent ECCS Subsystems o be OPERABLE and provides explicit ACTION requirements if one CCCS Subsystem inoperable. Under the requirements of Specification 3.0.3, 'f both the r quired ECCS Subsystems are ed to place the unit in at inoperable, within I hour measures must be initin and at least HOT SHUT 00WN within least HOT STAN08Y within the next d hour Specification 3.6.2.1 requires the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further examp two Containment Spray Systems to be OPERAB nd provides explicit ACTION '

able. Under the requirements of requirements if one Spray System is inop Contai. ent Spray Systems are inoperable, Specification 3.0.3 if both the requir e unit in at least HOT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measure must be initia d to place STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , i at least HOT S TOOWN within the following n the subsequent hours.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUT 00WN wi 3.0.4 This specificati provides that entry into n OPERATIONAL MODE or other specified applicabil y condition must be made with. (1) the full complement of required s tems, equipment, or components 0 RABLE, and (2) all i other parameters as sp ified in the Limiting Conditions for peration being met without regard f allowable deviations and out-of-service rovisions contained in the A ON statements.

The intent of this provision is to ensure that facility opera on is not initiated wi either required equipment or systems inoperable or ot r specified limits beir exceeded.

f E. eptions to this provision have been provided for a limited number l

speci ications when startup with inoperable equipment would not affect plan

! safA y. These exceptions are stated in the ACTION statements of the l

Qppropriatespecifications.

I Q,kdm 3.0.5 A i; ; w ific;t' & delineates the applicability of each

~' specification to Unit 1 and Unit 2 operation.

McGUIRE - UNITS 1 and 2 8 3/4 0-1 b -

O qar foz ases 3.o.l A 3.o.f l

l Scecificatice 2.0.1 thecuch 3.0.a establish the general requirererts acclicarte to Limitino Cenoitions for Operation. These requirerents are based on the I

requirements for Limiting Corditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(21:

"Limiting conditions for c:eration are the lowest functional capability or perfomance levels of equic~ent recuired for safe cperation of the facility. When a limiting condition for cceration of a nuclear reactor is net ret, the licensee shall shut down the reactor or follcw any remedial actien pemitted by the technical specification urtil the condition can be met."

Seecification 3.0.1 establishes the Applicability staterent within each incivicual specification as the rer,uirement for when (i.e., in which OPERATIONAL POCES or other specified cerditions) confomance to the Limitirg The Condittens for Operation is recuired for safe operation of the facility.

ACTION requirements establish those reredial reasures that rust be taken within specified tire limits when the requirements of a Limiting Cordition fer Operation are not met.

There are two basic types of ACTION recuirements. The first seecifies the remedial reasures that pemit continued operation of the facility which is not further restricted by the tire limits of the ACTION recuirements. In this case, cenformance to the ACTION requirements provides an acceptable level c' safety for unlimited continued operatinn as long as tre ACTION requirements The second type of ACT:CN requirement speci#ies a tir4 centinue to be ret.

limit in which confortrance to the conditions of the Liniting Conditien for Operation rust be ret. This time limit is the allowable outage tire to restore er inoperable system or component to CFERABLE status or fer restoring parameters within scecified limits. If these actions are not cercleted witnic the allowable cutage time limits, a shutdown is recuired to place theItfacility ';

in a PCCE or condition in which the specification to lenger applies. ::: tic :'

,00 i-tcrd:d th:t !P: :h td:;r 30TICM r;;;ir: :rt: 5: u::d :: : ~1 -

r v e r,i c r.: : H;b ;;Mt; (r:etir ) . lurt ry : v:1 c' ; ;:t;> 2

; :-t{ ) ' r ::rvi;; ir lieu cf ::t r O't:- t'v;; t':: L id :: r;;u';

r:durd:-t ytt: : Or : r;;r:rt: i:' g 'n:;;r: tic.

The specified tire limits of the ACTION recuirements are acclicable frem the ref :

in time it is identified that a Lleiting CerMtion for Oceratien is act ret. The tire limits cf the ACTION recuirerents are also acplicable when a syster or component is re oved from service for surveillance testing orIrdividual specifica investigation of ccerational problems.

a specified tire limit 'or the coepletion of a Surveillance Pecuirerent een ecuipment is removed free service. In this case, the allewable cutage t'-e

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limits of the ACTION recuirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is recuired to comply with ACTION recuirenents, the plant ray have entered a NODE in which a new specification becomes applicable. In this case, the tire limits of the ACTION requirerents would apply from the point in time that the new specification becories applicable if the requirements of the Limiting Conditien Dr Operation are not met.

Specification 3.0.2 es'.sblishes that noncompliance with a specification exists wnen 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 tir,e interval ecnstitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition Operation is restored within the time interval specified in the associated ACTION requirements, for Specification 3.0.3 establishes the shutdown ACTION recuirements that rust be implementee when a Limiting Condition for Operation is not ret 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 MODE when plant operation cannot be maintained within the limits for 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 pemits (routine) voluntary removal of redundant systers or components from service in lieu of other alternatives that would net result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdcwn before initiating a change in plant operation. This time pemits the operator to coordinate the reduction in electrical gereration with the load dispatcher to ensure the stability and availability of the electrical grid. The tire lirits specified to reach lower MCDES of operation pemit the shutdewn to proceed in a controlled and orcerly manner that is well within the specified maxirum cooldown rate and within the cooldown capabilities of the facility assuring only the minimum recuired ecuipeent is OPEpsABLE. This reduces themal stresses on corponents of the primary ecolant system and the potential for a plant upset that could challence safety systers under conditions for which this specification applies.

f remedial measures pemitting limited continud operati on of the f acility under the provisions of the ACTION recuirements are compb .ed, the shutdover may be teminated. The time lirits of the ACT!ON requi'erents are applicable from the point in tire there was a failure to meet a limiting Condition for Operation. Therefore, the shutdown may be terminated 'f the ACTION requirements have been met or the time limits of the M TION requirerents have rot expired, thus providing an allowerce for the completion of the recuired actions.

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The time Ifmits 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 COLO SHUTOCWN MODE when a shutdown is recuired during the POWEP operation. If the plant is in a lower MODE o' operation when a shutdowr is reouired, the time limit for reaching the next lower FCOE of operation ao-plies.

However, if a lower PCDE of operation is reached in less tire than allowed, the total allowable time to reach COLD SFUTDOWN, or cther applicable For example, if HOT STAND 8Y is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the MCDE, is not reduced. time allcwed to reach HOT SHUTC0WN is the next 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months to reach HOT SHUT 00WN is not reduced from the allowable limit of 13 h Therefore, if re;redial measures are ccepleteo that would penrit a return to POWER operation, a peralty is not incurred by having to reach a lower VOCE o' operation in less than the total time allcwed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION reouirerents for one -

specification results in entry into a PODE or condition of operation for another specification in rhich the recuirements of the Limiting Conditien for If the new specification becomes applicable in less Operation are not met.

tire than specified, the difference may be added to the allewable outage limits of the second specification.

of ACTION reouirements for a higher MCCE of operation may not be used to ex the allowable outage time that is applicable when a limiting Conditien for Operation is not met in a lower PCDE of operation.

The shutdown recuirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Soecification 3.0.4 establishes limitations on MODE It precludes changes placina when the facility in a a liriting Condition for Operation is not met.

higher MODE of operation when the requirerents for result in a shutoown to comply with the ACTION requirements if a change in

0 DES were permitted. The purpose of this specification is to ensure that facility operation is cet initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain ccepliance with a specification specified limits.

by restoring equipment to OPERABLE status or pa operation of the facility fer an unlimited period of time provides an accert-able level of safety for centf rued operation without regard to the status the plant before or after a MCCE change.

an OPEPATIONAL PODE or other specified condition may be cade The crevisions in accordance of this with the provisfors of the ACTION reevirerents.

specification should ret, Fewever, be interoreted as endorsing the f ailure to exercise gccd practice ir restoring systems or cceponents to OPE 9ABLE s*stus before plant startup. ii When a shutdown is required to comply with ACTION recuirerents, th of Specification 3.0.4 do not apply because they would delay placing facility in a icwer MODE of operation.

APPLICABILITY g 4SEcr Mcn4 NEKT BASES b hbb I

h 4.0.1 This specification provides that surveillance activities necessar to sure the Limiting Conditions for Operation are met and will be perform durin the OPERATIONAL MODES or other conditions for which the Limiting Co di-tions r Operation are applicable. Provisions for additional surveilla e activitie to be performed without regard to the applicable OPERATIONA MODES or other co itions are provided in the individual Surveillance Requi ements, iSurveillance quirements for Special Test Exceptions need only be rformed when the Specia Test Exception is being utilized as an exception o an individual specif ation.

4.0.2 The provisi s of this, specification provide al owable tolerances for performing surveillan e activities beyond those speci ied in the nominal surveillance interval. Th e tolerances are necessary provide operational flexibility because of sched ing and performance cons derations. The phrase "at least" associated with a s rveillance frequency es not negate this allowable tolerance value and p its the performa e of more frequent surveillance activities.

The tolerance values, taken eit. r indivi ally o'r consecutively over three test intervals, are sufficiently estri tive to ensure that the relia-bility associated with the surveillance ct' ity is not significantly degraded beyond that obtained from the nominal spe. fied interval.

4.0.3 The provisions of this sp ificati n set forth the criteria for determination of compliance with the PERABILIT requirements of the Limiting Conditions for Operation. Under t s criteria, e uipment, systems or componen s are assumed to be OPERABLE if the associated surve 11ance activities have been satisfactorily performed within he specified time 1.terval. Nothing in this provision is to be construed defining equipment, s tems or components OPERABLE, when such items ar found or known to be inop rable although still meeting the Surveillance R uirements.

4.0.4 This spec ication ensures that the surveillance tivities associated with a L iting Condition for Operation have been pe formed within the specified tim interval prior to entry into an OPERATIONAL E or other applicable condi ion. The intent of this provision is to ensure t at surveil-l lance activiti s have been satisfactorily demonstrated on a current asis as required to . et the OPERABILITY requirements of the Limiting Condit1 n for Operation.

Un r the terms of this specification, for example, during initial p ant start or follow lng extended plant outages, the applicable surveillance l

act ities must be performed within i.he stated surveillance interval prior

} p1 cing or returning the systam or equipment into OPERABLE status. ;

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McGUIRE - UNITS 1 and 2 B 3/4 0-2

A rQ$69CT toe B565 40\bS0f l

Soecifications 4.0.1 throuch 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 Reculations, 10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibra-tion, or insrection 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."

Specification 4.0.1 establishes the recuirement that surveillances must be performee during the OPERATIONAL MODES or other conditions for which the recuirements of the Limitino Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this speci-fication is to ensure that surveillances are perfomed to verify the opera-tional status of system! and components and that parameters are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be perfomed when the facility is in an OPERATIONAL MODE for which the recuirements of the associated Limiting Condition for Operation do not apply unless othewise specified. The Surveillance Recuirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the recuirements of a specification.

Seecification 4.0.2 establishes the conditions under whichItemthea.

specified time permits an intervai for Surveillance Requirernents may be extended.

allowable extension of the nomal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., Iten transient conditions

b. limits the or other ongoing surveillance or maintenance activities.

use of the provisions of item a. to ensure that it is not used repeated'y to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the reencrition that the most probable result of any particular su- eillance being perferred is the

e Pequirements. These crovisiers verification of confomance with the Surveillt are sufficient to ensure that the reliability ensured threugh surveillance activities is ret significantly degraded beyond that obtained from the specified surveillance interval.

Soecification 4.0.3 establishes the f ailure to perfom a Surveillance Requirement within the allowed surveillance interval, defined by the provisiers of Specificatien 4.0.2, as a condition that constitutes a failure toUnder meetthethe OPEPMILITY recuirements fer a Limiting Cendition f or Operation.

b provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements bave been satisfactorily performed within the specified time interval. However, nothing in this provision is te 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 Recuirements 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 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 ACT'ON requirements restores comoliance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subiect to enforcement action. 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 recuirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION recuirements are less ttran 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is recuired to comply with ACTION recuirements, e.g.,

Specification 3.0.3, a 24-hcur allowance is provided to pemit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION recuirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditio .s. adecuate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in comr'eting the recuired surveillance. This provision also provides a time limit for the completion of Surveillance Recuirements that become applicable as a consecuence of F0DE changes imposed by ACTION requirements and for completing Surveillance Pequirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the FA-Four allowance, the time limits of the ACTION recuirements are aeolicaM e 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 ACTICV requirements are applicable at the time that the surveillance is teminated.

Surveillance Recuirerents do not have to be performed on inoperable ecuierent because the ACTION recuirements define the remedial measures that apply.

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

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Soecificatien 4.0.4 establishes the requirement that all applicable survi must be ret before entry into an OPERATIONAL MODE or other The condition purpose of of this operation specified in the Applicability statement.

specification is to ensure that system and coroonent OPERAEILITY recuirer or parameter limits are ret before entry into a MCCE or condition for wh Thi these systems and components ensure safe operatien of the facility.

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

Under the provisions of this specification, the applicable Surveillance Requirenents must be perfomed within the specified surveillance interva to ensure that the Lietting Conditions for Operation are met during init plant startup or following a plant outage.

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

Soecification 4.0.5 establishes the requirement that inservice inspectic A5ME Code Class 1, 2, and 3 components and inservice testinn of ASME Coc Class 1, 2, and 3 pumps and valves shall be perfomed in accordance witt periodically updated version of Section XI of the ASME Boiler and Presst Vessel Code and Addenda as required by 10 CFR 50.55a. These reoufrements except when relief has been provided in writing by the Comission.

This specification includes a clarification of the 'recuencies for perf(

the inservice inspection and testing activities recuired by Section XI c This clar-ASME Boiler and Pressure Vessel Code and apolicable Addenda.

is provided to ensure consistency in surveillance intervals throughout -

Technical Specifications and to remove any ambiguities. relative te the frecuencies for perfoming the recuired inservice inscection and testine activities.

Under the ter1rs of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME The requirements Poiler and Pressure of Srecification 4.0.4 Vessel Code and applicable Addenda.

to perfom surveillance activities before entry into an OPERATIONAL MODr other specified condition takes precedence over the ASME Boiler and Pre Vessel Code provision which allows pumps and valves to be tested up to week af ter return to nomal operation. The Technical Specification def of OPERABLE does not allow a grace period before a component, that is r captble of performing its specified function, is declared inoperable an precedence over the ASME Boiler and Pressure Yessel Code provision whic allows a valve to be incapable of perforcing its specified function for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared ineperable.

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.L' APPLICABILITY BASES 4 This specification ensures that inservice insrection of ASME ode Clab.0.52 and 3 components and inservice testing of ASME Code Class , 2 and 3 pumps an Ives will be performed in accordance with a periodic y updated version of Sec XI of the ASME Boiler and Pressure Vessel Co and Addenda as required by 10 50.55a. Relief from any of the above quirements has been provided in writin by the Commission and is not a p of these Technical Specifications.

This specification includes clarification the frequencies for performing the inservice inspection nd testi activities required by Section XI of the ASME Boiler and Pres re ' ssel Code and applicable Addenda, This clarification is provided to ensure onsistency in surveillance intervals thoughout these Technical Specificatio an to remove any ambiguities relative to the frequencies for per rming th required inservice inspection and testing activities.

Under the terms of thiv pecification, the more estrictive requirements of the Technical Sps.cific ions take precedence over t. A5ME Boiler and Pressure Vessel Code a applicable Addenda. For example, the requirements of Specification 4.0.4 perform surveillance activities prio to entry into an 0?dRATIONAL MODE o other specified applicability condition ta s precedence over the ASME Bo' er and Pressure vessel Code provision which al ws pumps to be tested up - one week after return to normal operation. And for xample, the Technic < Specification definition of OPERABLE does not grant a g e period be re a device that is not capable of performing its specified is declared inoperable and takes precedence over the ASME Boile d functi ,\

Pres re Vessel Code provision which allows a valve to be incapable cf I per orMng its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being de '-or -

dnoceraole. _

Sifrwbn 4.0 G T'i: :p;ci'iccticn delineates the applicability of the l surveillance activities to Unit 1 and Unit 2 operations.

McGUIRE - UNITS 1 and 2 B 3/4 0-3

I i

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (

(

ACTION: (Continued)

2. Reduce EiERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and

3. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIC is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater

, RATED THERMAL POWER.

d. The pr:vi;f=n; cf Specificati:n 2.0.t are n:t applicable.

SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

L McGUIRE - UNITS 1 and 2 3/4 2-21 Amendment No. (Unit 1) i Amendment No. (Unit 2) ,

2 IABLE 3.3-1 REACTOR TRIP SYSTEM INSTRIMENTATION j 5 MINIMUM

/

TOTAL NO. CHANNELS CHANNELS APPLICABLE c

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION d Manual Reactor Trip 2 2 1, 2

,, 1. 1 1 2 1 2 3*, 4*, S* 10

2. Power Range, Neutron Flux - High 4 2 3 1, 2 Setpoint

-k Low 4 2 3 n 'yg,,2 2 Setpoint

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

4. Power Range, Neutron Flux, 4 2 3 1, 2 2

{ High Negative Rate S. Intermediate Range, Neutron Flux 2 1 2 l ,2 3

6. Source Range, Neutron Flux

a. Startup 2 1 2 2,, 4

b. Shutdown 2 1 2 3*, 4*, S* 10 2 0 3, 4, and 5 -

S

c. . Shutdown 1

7. Overtemperature AT Four Loop Operation 4 2 3 1, 2 Three Loop Operation (**) (**) (**) (**) l (**

TABLE 3.3-1 (Continued)

N 8 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CilANNELS CHANNELS APPLICABLE

! E FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION

8. Overpower AT

! @ Four Locp Operation 4 2 3 1, 2 Y ro Three Loop Operation (**) (**) (**) (**) (**

9. Pressurize r Pressure-Low 4 2 3 l' 6

10. Pressurizer Pressure--High 4 2 3 1, 2 6 sy

, $ 11. Pressurizer Water Level--liigh 3 2 2 1 6 f ,

w J, 12. Low Reactor Coolant flow

a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 6 [

any oper- each oper-ating loop ating loop ,

b. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1 below P-8) two oper- each oper-

>> ating loops ating loop

$5 6N ga 13. Steam Generator Water 4/sta. gen. 2/sta. gen. 3/stm. gen. 1, 2 gg Level--Low-Low in any oper- each oper-ating stm.

- )h a3 ating sim.

gen. gen.

2z oo CC ,

, 00

O>

l, TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION E

E '

MINIMUM e TOTAL NO. CHANNELS CHANNELS APPLICABLE 10 1 RIP OPERARLE MODES ACTION g FUNCTIONAL UNIT OF CHANNELS Z

m Undervoltage-Reactor Coolant 14.

es Pumps (above P-7) 4-1/ bus 2 3 I [

5 15. Underfrequency-Reactor Coolant -

m Pumps (above P-7) 4-1/ bus 2 3 I Turbine Trip

. 16.

a. Low Fluid Oil Pressure 3 2 2 1 b

b. Turbine Stop Valve Closure 4 -

4 1 1 1$

17. Safety Injection Input from ESF 2 2 1, 2 9 y 1 y 18. Reactor Trip System Interlocks a a. Intermediate Range 2,,

Neutron Flux, P-6 2 1 2 8

b. Low Power Reactor Trips Bloc , P-7 P-10 Input 4 2 3 1 8 O*

2 8 I$

e a P- G Input 2 1 1 a a

&I c. Power Range Neutron 2 3 8 8$

Flux, P-8 4 1

5E

~~

d. Low Setpoint Power 2 3 1, 2 8 Range Neutron Flux, P-10 4

e. Turbine Impulse Chamber 2' I 2 8 jy Pressure, P-13 1 2X UC -

1

i TABLE 3.3-1 (Continued)

TABLE NOTATION With the Reactor Trip System breakers in the closed position, the Control Rod Drive System capable of rod withdrawal.

==

Values left blank pending NRC approval of three loop operation.

AAA f Comply with the provisions of Specification 3.3.2 for any portion of the J7 channel required to be OPERABLE by Specification 3.3.2. 9 N,u. .....z.s... I c._. . _ . _ . _ ..

e... as..

,n s .. ...

...,s

.,y,

.c,_

Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. B elow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDRY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: AEbt

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , j[

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months /'

for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and tFe Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

MCGUIRE - UNITS 1 & 2 3/4 3-6 Amendment No Unit 1)

Amendment N Unit 2)

5 I

TABLE 3.3-3 N

E3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

m

' MINIMUM E TOTAL NO. CHANPC.LS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

{j

1. Safety Injection, Reactor g Trip, Feedwater Isolation, c' Component Cooling Water, Start N Diesel Generators, and Nuclear Service Water

a. Manual Initiation 2 1 2 1, 2, 3, 4 18

b. Automatic Actuation 2 1 2 1,2,3,4 14 u, Logic and Actuation

); Relays

[ c. Containment 3 2 l 2 1,2,3 ISM c' Pressure-High

d. Pressurizer 4 2 3 1,2,3 1 Pressure - Low-Low

e. Steam Line Pressure-Low .

Four Loops 3/ steam line 2/ steam line 2/ steam line 1, 2, 3 15)(

Operating in any steam line Three Loops (**) (**) (**) (**) (**)

Operating

.A -A c

n E TABLE 3.3-3 (Continued) h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c ~

MINIMUM Z= TOTAL NO. CHANNELS CHANNELS APPLICABLE

[ FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

{ 4. Steam Line Isolation m a. Manual Initiation

1) System 2 1 2 1,2,3 22

2) Individual 1/ steam line 1/ steam line 1/ operating 1, 2, 3 23 steam line

b. Automatic Actuation 2 1 2 Logic and Actuation 1,2,3 21 Relays w c. Containment Pressure-- 4 2 3 1. 2, 3 1 High-High

16 Y' d. Negative Steam Line G . Pressure Rate - High Four Loops 3/ steam line 2/ steam line 2/ steam line 3 Operating in any steam lk line Three Loops (**) (**)

Operating

(**) (**) (**)

e. Steam Line Pressure - Low Four Loops 3/ steam line 2/ steam line 2/ steam line #

Operating 1, 2, 3 ISK in any steam line Three Loops (**) (**) (**)

Operating (**) (**)

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION m

e MINIMUM c: TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MCDES ACTION

a S. Turbine Trip &

g feedwater Isolation a

n> a. Automatic Actuation 2 1 2 1, 2 21 Logic and Actuation Relay

b. Steam Generator 3/sta. gen. 2/sta. gen. 2/sta. gen. 1, 2 IdK Water Level-- in any oper- in each oper-High-High ating sta gen. ating stm. gen.

s

c. Doghouse Water 3/ train / 2/ train / 2/ train / 1, 2 2d4 i' Level (Feedwater Doghouse Doghouse Doghouse '

E' Isolation Only)

,6 . Containment Pressure Control 8(4/ train) 4/ train 8 1,2,3,4 26 2 System g/

NE at ee O

Idik WW

TABLE 3.3-3 (Continued)

N ENGINEERfD SAFETY FEATURES ACTUATION SYSTCM INSTRUMENTATION j"x f

F1

' MINIMUM '

TOTAL NO. CHANNEL 5 CHANNELS APPLICABLE /

E TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT OF CHANNELS

1, ,.

u '

./

7. Auxiliary feedwater

$ 2 2 1,2,3 22

" a, Manual Initiation 1 to 2 1,2,3 21

b. Automatic Actuation Logic 2 1 and Actuation Relays

c. Sta. Gen. Water Level-Low-Low u,

3: 1) Start Motor- 2/sta. gen. 3/sta. gen. 1,2,3 19 Driven Pumps 4/sta. gen.

o, in any opera- in each 4

"' ting sta gen. operating stm. gen.

2) Start Turbine- 2/stm. gen. 3/sta, gen 1,2,3 ISMI Driven Pump 4/sta. gen.

in any in each 2 operating operating sta. gen. stm. gen

d. Auxiliary Feedwater 1, 2, 3 24 2/ pump 2/ pump 2/ pump Suction Pressure - Low (Suction Supply Automatic Realignment)

e. Safety Injection Start Motor-Driven Pumps See Item 1. above for all Safety Injection i'itiating functions and requirements

TABLE 3.3-3 (Continued)

N

@ ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION m

MINIMUM E TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

]

7. Auxiliary Feedwater (continued) a f. Station Blackout N Start Motor-Driven Pumps and Turbine-Driven Pump 6-3/ Bus 2/ Bus 2/ Bus 1, 2, 3 9N Either Bus

g. Trip of All Main Feedwater Pumps Start Motor- g Drivea Pumps 2/ pump 1/ pump 1/ pump 1, 2 14 m

1 y 8. Automatic Switchover to 4 Recirculation l RWST Level 3 2 2 1, 2, 3 ISN 9 .' Loss of Power 4 kV Emergency Bus 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 IS$

Undervoltage-Grid ,

Degraded Voltage

10. Engineered Safety Features Actuation System Interlocks

a. Pressurizer Pressure, 3 2 2 1,2,3 20 P-11

b. 4 2 3 1,2,3 20 Low-Low T,yg, P-17

c. Reactor Trip, P-4 2 2 2 1,2,3 22

d. Steam Generator 3/sta gen. 2/sta gen. 2/sta gen. 1,2,3 20 Level, P-14 in any in each operating operating sta gen. sta gen.

TABLE 3.3-3 (Continued)

TABLE NOTATION ,

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam pressure is not blocked.

The previsi;n: ;f Specificati;n 3.0.4 cre net ;pplic;ble.

- These values lef t blank pending NRC approval of three loop operation.

ACTION 3TATEMENIS ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

AC'fION 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

McGUIRE - UNITS 1 and 2 3/4 3-23

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

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

b. With one or more radiation monitoring channels inoptrable, take the action shown in Table 3.3-6. __

c. TheprovisionsofSpecification/3.0.3;nd3.0.tarenotapplicable.

i SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations for the modes and at the frequencies shown in Table 4.3-3.

McGUIRE - UNITS 1 and 2 3/4 3-40

INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection 5 stem shall be OPERABLE with:

a. At least 75% of the detector thimbles,

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

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

APPLICABILITY: When the Movable Incore Detection System is used for:

a. Recalibration of the Excore Neutron Flux Detection System,

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. N Measurement of F 3g and F (Z) d 9 (

ACTION:

With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification / 3.0.3 = d 3.0.0 are not applicable.

gURVEILLANCEREQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by normclizing each detector output when required for:

a. Recalibration of the Excore Neutron Flux Detection System, or

b. Monitoring the QUADRANT P.Ta'ER TILT 'ATIO, or 4

c. Measurement of F n

aH and Fq (Z)

(

McGUIRE - UNITS 1 and 2 3/4 3-45 Arcendment No. f(Unit 1)

Amendment No. f;(Unit 2)

t INSTRUMENTATION SEISMIC INSTRUMENTATION

_A

'!'iTING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

b. TheprovisionsofSpecification/3.0.3:nd3.0.1arenotapplicable.

e SURVEILLANCE REQUIREMENTS

~

Each of the above seismic monitoring instruments shall be demon-

. . ERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION anj n.ilA0G CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above accessible seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the seismic event. Data shall be retrieved from accessible actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. Data retrieved from the triaxial time-histrry accelerograph shall include a post-event CHANNEL CALIBRATION obtained by actuation of the internal test and calibrate function immediately prior to removing data. CHANNEL CALIBRATION shall be performed immediately after insertion of the new recording media in the triaxial time-history accelo-graph recorder. A Special Report shall be prepared and submitted to the Commission pursuant tc Specification 6.9.2, with a copy to Director, Office of Nuclear Reactor Regulation, Attention: Chief, Structural and Geotechnical Engineering Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 10 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

Amendment No. 1 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-46 Amendment No. 20 (Unit 1) 4-13-83

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

APPLICABILITY: At all times.

ACTION:

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report ,

to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b. TheprovisionsofSpecification/3.0.3:nd3.0.4arenotapplicable.

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

McGUIRE - UNITS 1 and 2 3/4 3-49

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

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

ACTION:

a. With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in Table 3.3-11 inoperable, restore the inoperable instrumentu,) to OPERABLE status within 14 days or within the next I hour e;;ablish 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 that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations given in Specification 4.6.1.5.1 or 4.6.1.5.2.

b. With more than one if of the Function A fire detection instruments s in any fire zone s..own in Table 3.3-11 inoperable, or with any Function B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adja.ent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) bith the inoperable instrument (s) at least once per hour, uni'sss the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or mon' tor the contain-ment air temperature at least once per hour at the locations given /;

in Specification 4.6.1.5.1 or 4.6.1.5.2. J

c. The provisions of Specification / 3.0.3 cd 2.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above re' quired fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

Each of the above required fixed temperature / rate of rise detection instruments shall be demonstrated OPERABLE as follows:

AmendmentNo./(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-58 Amendment No. y (Unit 1)

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. 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 (00CM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation '

channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radio-active liquid effluents monitored by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown O in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.

c. TheprovisionsofSpecification/3.0.3ad3.0.4arenotapplicable. [

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.

McGUIRE - UNITS 1 and 2 3/4 3-66 Amendment No (Unit 1)

Amendment No. (Unit 2)

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the 00CM.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release )f radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within the time soecified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified,

c. The provisions of Specification / 3.0.3 end-a-e-+ are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.

1 McGUIRE - UNITS 1 and 2 3/4 3-71 AmendmentNo.d(Unit 1)

I Amendment No./ (Unit 2)

INSTRDMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CON 0! TION FOR OPERATION 3.3.3.10 The Loose-Part Detection System shall be OPERABLE.

APPLICABILITY: MODES 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 pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring.

the channel (s) to OPERABLE status.

b. The provisions of Specification / 3.0.3 :nd 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS , 4.3.3.10 Each channel of the Loose-Part Detection Systems 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 , and

b. An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and

c. A CHANNEL CALIBRATION at least one per 18 months.

McGUIRE - UNITS I and 2 3/4 3-78 1

REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 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.

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.

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*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.

d. Th; pr;vi;ien; ;f 5;;;ific;ti;n 3.0.4 cr; n t opplic;bi;.

4 SURVEILLANCE REQUIREMENTS 4,4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C 4.b of Regulatory Guide 1.14, Revision 1, August 1975.

i i

McGUIRE - UNITS 1 and 2 3/4 4-39

l PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION (

LIMITING CONDITION FOR OPERATION l

3.7.9 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. With a sealed source having removable contamination in excess of the abcve limits, immediately withdraw the sealed source from use and i

j e' the r:

I

1. Decontaminate and repair the sealed source, or

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

I

b. The provisions of Specification / 3.0.3 u d 3.0.i are not applicable.

(

$URVEILLANCE REQUIREMENTS 4.7.9.1 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 sh'all have a detection sensitivity of at h t 0.005 cicrocurie per test sample.

4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall te tested at the frequency described below.

a. Sources in use - At least once per 6 months for all sealed. sources containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogen 3),

and

2) In any form other than gas.

McGUIRE - UNITS I and 2 3/4 7-30

PLANT SYSTEMS 1

3/4.7.10 FIRE SUPPRESSION SYSTEMS

' FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water System shall be OPERABLE with:

a. At least two fire suppression pumps (either A and C or 8 and C),

each with a capacity of 2500 gpm, with their discharge aligned to if i the fire suppression header; and

b. An OPERABLE flow path capable of taking suction frnm Lake Norman and P

transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valven to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each Deluge or Spray System required to be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.

APPLICABILITY: At all times.

ACTION: 8

a. With one of the above required pump and/or one water supply inoperable,

" restore the inoperable equipment to OPERABLE status within 7 days or

' provide an alternate backup pump or supply. The provisions of Specifi-cation) 3.0.3 ;nd 2.0.? are not applicable. ,

b. With the Fire Suppression Water System otherwise inoperable '

establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

' McGUIRE - UNITS 1 and 2 3/4 7-32 Amendment No. (Unit 1)

Amendment No. (Unit 2)

l l

I I

i PLANT SYSTEMS I LIMITING CONDITION FOR OPERATION (Continued) ,

APPLICABILITY: Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.

ACTION:

a. With one or more of the abOve required Spray and/or Sprinkler Systems f inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant 4 systems or components could be damaged; for other areas, establish a l

hourly fire watch patrol.

b. The provisions of Specification / 3.0.3 e-4 0.0.4 are not applicable.

SURVEILLANCE REQUIREMENT 0 4.7.10.2 Each of the above required Spray and/or Sprinkler Systems shall be '

demonstrated OPERABLE: ;

3

a. At least once per 31 days, by verifying that eLch valve (manual, power-operated, or automatic) in the flow path which is accessible during plant operation is in its correct position, hI S

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

c. At least once per 18 months:

1) By performing a system functional test which includes simulated ,

automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path I actuate to their correct position on a Fire Detection i test signal, and ,

i b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle i

of full travel.

2) By a visual inspection of the dry pipe spray and sprinkler headers to verify their integrity; and 3 3) By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.

4) By verifying that each valve (manual, power-operated, or g automatic) in the flow path which is inaccessible during plant operation is in its correct position. Q'

d. At least once per 3 years, by performing an air flow test through each open head spray / sprinkler header and verifying each open head i

spray / sprinkler nozzle is unobstructed.

Amendment No (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-35 Amendment No (Unit 1)

PLANT SYSTEMS HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.10.3 The following Halon Systems shall be OPERABLE:

a. Elevation 716 ft. - Auxiliary Building Room No. Equipment 600 B Turbine Driven Aux, FW Pump - Unit 1 601B Turbine Driven Aux FW Pump - Unit 2

b. Elevation 733 f t. - Auxiliary Building Room No. Equipment 703-704 Diesel Generators - Unit 1 714-715 Diesel Generators - Unit 2 APPLICABILITY: Whenever equipment protected by the Halon System is required to be OPERABLE.

ACTION:

a. With one or more of the above required Halon Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire ,

suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol,

b. TheprovisionsofSpecification/3.0.3end3.^.0arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.10.3 Each of the above required Halon Systems shall be demonstrated OPERABLE:

a. At least once per 31 days, by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct position,

b. At least once per 6 months, by verifying Halon storage tank weight to be at least 95% of full charge weight and pressure to be at least 90% of full charge pressure, and

c. At least once per 18 months, by:

1) Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and auto-matica11y, upon receipt of a simulated actuation signal, and

2) Performance of a flow test throu'gh headers and nozzles to assure no blockage.

McGUIRE - UNITS 1 and 2 3/4 7-36

I PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION

+

3.7.10.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

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

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7-5 inoperable, provide gated wye (s) on the nearest OPERABLE hose station (s). One outlet of the wye shall be connected to the standard length of hose provided for the hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station. Signs shall be mounted above the gated wye (s) to identify the proper bose to use. The above action shall be accomplished within I hour if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. TheprovisionsofSpecification)3.0.3end3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS , 4.7.10.4 Each of the fire hose stations shown in Table 3.7-5 ' hall be demonstrated OPERABLE:

a. At least once per 31 days, by a visual inspection of the fire hose strtions accessible during plant operations to assure all required equipment is at the station,

b. At least once per 18 months, by:

1) Visual inspection of the stations not accessible during plant i

operations to assure all required equipment is at the station,

2) Removing the bose for inspection and re-racking, and

3) Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c. At least once per 3 years, by:

1) Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage, and

2) Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, j

whichever is greater.

McGUIRE - UNITS I and 2 3/4 7-37

s t

PLANT SYSTEMS 3/4.7.11' FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.11 All fire barrier penetrations (walls, floor / ceilings, cable tray enclosures and other fire barriers) separating safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable piping, and ventilation duct penetration seals) shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire barrier penetrations and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a continuous fire watch on at least one side of the affected assembly, or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly and establish an hourly fire watch patrol, b, TheprovisionsofSpecification[3.0.3:nd3.0.earenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.11.1 At least once per 18 months the above required fir e barrier '

penetration sealing devices shall be verified OPERABLE, by performing a visual inspection of:

a. The exposed surfaces of each fire rated assembly,

b. Each fire vindow/ fire damper /and associated hardware, and

c. At least 10% of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made. This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal (

degradation is found. Samples shall be selected such that each penetration seal will be inspected every 15 years.

McGUIRE - UNITS 1 and 2 3/4 7-40

E .

REFUEL 1NG OPERATf0NS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 3000 pounds" shall be prohibited from travel over fuel assemblies in the storage pool. Truck casks shall be carried along the path outlined in Figure 3.9-1 in the fuel pit and fuel pool area.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

a. With the requirements of the above specification not satisfied, place the crane load in a safe condition,

b. The provisions of Specification / 3.0.3 ;.,d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly and control rod, shall be verified to be less than 3000 pounds prior to moving it over fuel assemblies.*

Weir gates of the spent fuel pool may be moved by crane over the stored fuel provided the spent fuel has decayed for at least 17.5 days since last being part of a core at power.

McGUIRE - UNITS 1 and 2 3/4 9-8

REFUELING OPERATIONS 3/4.9.10 WATER LEVEL - STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

a. With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

b. TheprovisionsofSpecification/3.0.3;nd2.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

McGUIRE - UNITS 1 and 2 3/4 9-13

t 1

REFUELING OPERATIONS 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM -

LIMITING CONDITION FOR OPERATION 3.9.11 The Fuel Handling Ventilation Exhaust System shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With the Fuel Handling Ventilation Exhaust System inoperable, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until the Fuel Handling Ventilation Exhaust System is restored to OPERABLE status,

b. TheprovisionsofSpecificationp3.0.3:,,d3.^.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.9.11.1 The Fuel Handling Ventilation Exhaust System shall be determined to be operating and discharging through the HEPA filters and charcoal adsorbers at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever irradiated fuel is being moved in the storage pool and during crane operation with loads over the storage pool.

4.9.11.2 The above required Fuel Handling Ventilation Exhaust System shall be demonstrated OPERABLE:

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

1) Verifying that the system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1%

and uses the test procedure guidance of Regulatory Positions C.S a C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 35,000 cfm + 10%;

2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordar.te with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and McGUIRE - UNITS 1 and 2 3/4 9-14

REFUELING OPERATIONS 3/4.9.12 FUEL STORAGE - SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.12 Fuel is to be stored in the spent storage pool with:

a. The boron concentration in the spent fuel pool maintained at greater than or equal to 2000 ppm; and

b. Storage in Region 2 restricted to irradiated fuel which has decayed at least 16 days and one of the following:

1) fuel which has been qualified in accordance with Table 3.9-1; or Fuel which has been qualified by means of an analysis using NRC \

2) approved methodology to assure with a 95 percent probability at W a 95 percent confidence level that k,7f is no greater than 0.95 including all uncertainties; or h

3) Unqualified fuel stored in a checkerboard configurttion. In the event checkerboard storage is used, one row between normal storage locations and checkerboard storage locations will be vacant.

APPLICABILITY:

4 During storage of fuel in the spent fuel pool.

ACTION:

a. Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined a fuel assembly has been placed in the incorrect Region until such time as the correct storage location is determined. Move the assembly to its correct location before resumption of any other fuel movement.

b. Suspend all actions involving the movement of fuel in the spent fuel pool if it is determined the pool boron concentration is less than 2000 ppa, until such time as the boron concentration is increased to 2000 ppm or greater.

The provisions of Specification) 3.0.3 = d 3..' are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.9.12a. Verify all fuel assemblies to be placed in Region 2 of the spent fuel pool are within the enrichment and burnup limits of Table 3.9-1 or that k,ff 5,0.95 by checking the assemblies' design and burnup documentation or the assemblies' qualifying analysis documentation respectively. .

b. Verify at least once per 31 days that the spent fuel pool boron con-centration is greater than 2000 ppm.

Amendment No. (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 9-16 ,

Amendment No. (Unit 1)

-RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDI1 ION FOR OPERATION 3.11.1.L The dose or dose commitment to a MEM8ER OF THE PUBLIC from radioac.ive materials in liquid effluents released, from each unit, to UNRESTr.ICTED AC,iAS (see Figure 5.1-4) shall be limited:

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

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

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, 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 which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliante with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.*

b. The provisiens of Specification / 3.0.3 ar.d 3.0. ' are not applicable.

SURVEILLANCE REQUIREMENTS ._,

4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

A These requirements are applicable only if the drinking water supply is taken from the river 3 miles downstream of the plant discharge.

McGUIRE - UNITS 1 and 2 3/4 11-5

RADI0 ACTIVE EFFLUENTS LIQUID RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall ce OPERABLE and appropriate portions of the system shall be used to reduce releases of radio-activity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: 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, 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 includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or g 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. TheprovisionsofSpecification/3.0.3cr.J3.0.'arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when water systems are being released without being processed by its Radwaste Treatment System.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be demon-strated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

MCGUIRE - UNITS 1 and 2 3/4 11-6 Amendn.ent No. 49 (Unit 1)

Amendment No. 30 (Unit 2) 11/22/85

RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor ta.h shall be limited to 1.4s than or equal to 10 Curies, excluding tritium and dissolved or entraine( noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately 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, and describe the events leading to this condition in the next Semiannual Radioactive' Effluent Release Report.

b. TheprovisionsofSpecification/3.0.? ad 0.0 i are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a repre-sentative sample of the tank's contents at least once per 7 days when radio-active materials are being added to the tank.

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.

McGUIRE - UNITS 1 and 2 3/4 11-7

RADI0 ACTIVE EFFLUENTS CHEMICAL TREATMENT PONOS LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each chemical treatment pond shall be limited by the following expression:

A 264 I

< 1. 0 excluding tritium and dissolved or entrained noble gases, Where:

A) = pond inventory limit for single radionuclide "j", in Curies; C

3 = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", microCuries/ml; V = design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microCuries/ Curie per milliliter / gallon.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive, material in any of the above listed ponds exceeding the above limit, immediately suspend all additions of radioactive material to the pond and initiate corrective action to reduce the pond contents to within the limit.

b. Theprovisionsof5pecification/3.0.3 cad 3.0.0arenotapplicable.

SURVEILLANCE REOUIREMENTS 4.11.1.5 The quantity of radioactive material contained in each batch of slurry (used powdex resin) to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of the slurry, and batches to be transferred to the chemical treatment ponds shall be limited by the expression:

p Cb < 6.0 x 10s I cm j pCi/ml 3

Where:

Q) = concentration of radioactive materials in wet, drained slurry (used powdex resin) for radionuclide "j", excluding tritium, dissolved or entrained noble gases, and radionuclides with less than an 8 day half-life. The analysis shall include at least Ce-144, Cs-134, Cs-137, Co-58 and Co-6C, in picoCuries/ gram. Estimates of the Sr-89 and Sr-90 batch concentration shall be included based on the most .

recent monthly composite analysis (within 3 months); and C) = 10 CFR 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", in microcuries/millil. iter.

McGUIRE - UNITS 1 and 2 3/4 11-8

RADI0 ACTIVE EFFLUENTS DC3E - NOBLE GASES LIMITING CONDITIOR FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:

During any calendar quarter: Less than or equal to 5 mrad for gamma a.

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

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 gaseous 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 which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. TheprovisionsofSpecification/3.0.3 Mad 2.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS _

4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 cays.

McGUIRE ' UNITS 1 and 2 3/4 11-13

i

\

RAD 10ACT!VE EFFLUENTS DOSE - IODINE-131 AND 133, TRITIUM AND RADI0 ACTIVE MATERIALS IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 5.1-3) shall be limited to the following:

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

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

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131 and 133, tritium, and radioactive materials in particulate form, with half-lives greater than 8 days, in gaseous 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 which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases and tne proposed corrective actions to be taken to assure that subsequent releases will be in compliance with tba above limits,

b. TheprovisionsofSpecification/3.0.3cri3.0.5arenotapplicable.

SU_RVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 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 00CM at least once per 31 days.

McGUITE - UdITS 1 and 2 3/4 11-14

RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to to gaseous effluent releases, from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 5.1-3) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEM8ER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess 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 includes the following information:

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

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

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

b. TheprovisionsofSpecification/3.0.3:nd3.0.?arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when gaseous Ns streams are being released without being processed by its Radwaste Treat- gs ment System. E s

4.11.2.4.2 The installed Gaseous Radwaste Treatment System shall be demon-strated OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

MCGUIRE - UNITS 1 and 2 3/4 11-15 Amendment No. (Unit 1)

Amendment No. (Unit 2)

--44/22/85 -

l l

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLOUP SYSTEM shall be limited to less than or equal to 2% by volume whenever the hydrogen concentra-tion exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 2% by volume but less than or equal 4% Ly volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

. b. With the concentration of oxygen in the W4STE GAS HOLOUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, and immediately take ACTION a. above, &

(

c. TheprovisionsofS(cificationf3.0.3;nd2.0.0arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP SYSTEM shall be determined to be within the above limits by monitoring the waste gases in the WASTE GAS HOLOUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.9.

T McGUIRE - UNITS 1 and 2 3/4 11-16

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 49,000 Curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b. TheprovisionsofSpecification/3.0.3-and3.0.1arenotapplicable.

SURVEILLANCE REQUIREMENTS

~

4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be with'in the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

3/4 11-17 McGUIRE - UNITS 1 and 2

RA0X0ACT1VE EFFLUENTS

-3/4.11.3 SOLIO RADIOACTIVE WASTE I .

I 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 inadequately processed 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 CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.

c. TheprovisionsofSpecificationp3.0.3 cad 3.0.4arenotapplicable.

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 i sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative -

SOLIDIFICATION parameters can be determined in accordance with the !

PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICA-fl0N. SOLIDIFICATION of the batch may then be resumed using the afternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; l

l McGUIRE - UNITS 1 and 2 3/4 11-18 l

RADIOACTIVE EFFLUENTS

' 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.1'1. '4 'The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mre.w.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials i in liquid or gaseous effluents' exceeding twice the limits of !

Specification 3.ll.1.2a., 3.11.1.2b., 3.ll.2.2a., 3.ll.2.2b.,

3.ll.2.3a.,-or 3.ll.2.3b., calculations should be made including

-direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Specifica-tion 3.11.4 have been exceeded. If such is the case, 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 defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving 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 MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct-radiation, for the calendar 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 4

or concentrations. If the 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. TheprovisionsofSpecification/3.0.3rd2.2.'arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose ccntributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions fren direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the

~

methodology and parameters in the 00CM. This requirement is applicable only under conditions set forth in ACTION a. of Specifi, cation 3.11.4.

McGUIRE - UNITS 1 and 2 3/4 11-20

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12-1, identify locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program within 30 days. The specific locations from which sarales were unavailable may then be deleted from the monitoring program. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples and 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 00CM reflecting the new location (s).

d. The provisions of Specification / 3.0.3 ene-}-G-4-are not' applicable.

SURVEILLANCE RE0VIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected

- pursuant to Table 3.12-1 from the locations given in the table and figure in the 00CM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and tha detection capabilities required by Table 4.12-1.

1 I

9 3/4 12-2 McGUIRE - UNITS 1 and 2

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 greater than 50 m2 (500 fta) producing broad leaf vegetation. (For elevated 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 locations 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) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of a Licensee Event Report, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples ar3 currently being obtained in accordance with Specification 3.12.1, add the new location to the Radiological Environmental Monitoring Program. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pathway) may be dele ed from this monitoring program after October 31 of the year in which this land use census was conducts.d. In lieu of a Licensee Event Report and pursuant to Specification 6.9.1.7, the next Semiannual hdioactive Effluent Release Report shall con-tain the following infermation: (1) the new location (s), (2) revised figure (s) and table (s) for the 00CM reflecting the new location (s),

and (3) if samp'es cannot be obtained, an explanation of why samples are not obtainasle (substitute representative locations shall be included, if possible),

h

c. The provisions of Specific:ation/ 3.0.3 xd 3.0. ? are not applicable.

"Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12-1.4c shall be followed, including analysis of control samples.

Amendment No. (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 12-13 Amendment No. (Unit 1) 6

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on rac'9sctive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Specification 3.1.2.1 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.provisionsofSpecificaticn/3.0.3a..d2.0.4arenotapplicable.

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.

s McGUIRE - UNITS 1 and 2 3/4 12-15

ATTACHMENT 3 PROPOSED CATAWBA TECHNICAL SPECIFICATION CHANGES

4 D

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMEN 3/4.0 APPLICABILITY LIMITING CONDITION FOR OFERATION 3.0.1 Compliance wit % the Limiting Conditions for Operation contained in the succeeding specific:stions is required during the OPERATIONAL MODES or other conditions specified therein; except that uoon f ailure to meet the Limiting .

Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncomplian:e with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met witnin 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply oy placing it, as applicable, in:

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

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

c. At least COLD SHUTCOWN witnin the suosequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

This specification is not applicable in MODE 5 or 6. #%

(Aco 3.0.4 mace #- Entry into an for the conditions OPERATIONAL the Limiting ConditionMODE or are for Operation other metMspecifie This pro-

< tncut rsi::nce :n ; m i; ion; c;ntaind 'n tn; 2CT:C" c wirem;nt;. 8 sision shall not orevent passage through or to OPERATIONAL MODES as recuired to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

3.0.5 Limiting Conditions for Operation including tne associated ACTION requirements sna11 apply to each unit indivicually unless otnerwise indicateo as follows:

a. Whenever the Limiting Condition for Operation refers to systems or comconents wnich are snared by both units, the ACTION recuirements will apply to botn units simultaneously. This will ce indicated in the ACTION section;

b. Whenever the Limiting Condition for Coeration aoolies to only one unit, this will be icentified in the APPLICABILITY section of tne specification; and

c. Whenever certain portions of a specific'ation contain operating parameters, setpoints etc., *nich are different for eacn unit, this will be identified in parentheses or footnotes. (For example, ").

". . . flow rate of 54,000 cfm (Unit 1) or 43,000 cfm (Unit 2). .

CATAW8A - UNITS 1 & 2 3/4 0-1

I/

f INSERT FOR SPECIFICATION 3.0.4.

and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

l

J l

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated ir, an individual Surveillance Rcquirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

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

b. The. combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interv 1 .gg g.2., gd M """' ilk 4.0.3 FailuretoperformaSurveillanceRequirementwithinthe[sp:ified t+ e interval shall constitute ; f;i h r: t: = :t the'0PERABILITY requirements for a Limiting Condition for peration. Lcepti:ns :: thes r;puf r==t: 4- LsatLT ar ;t:t;d i n th: '-di idu:' :::::i 'i c:t i =: . Surveillance Requirements do pg.oM

. g -r notnavetobecerformedon{noperaole,equipmeng neo co<gi,ance w g

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be inade unless the Surveillance Requirement (s) associated with the Li,miting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.3

4. 0. 5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components snall 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 snall be ;:erformed in accordance with Section .<I of the ASME Soiler and Pressure Vessel Code and applicable Addenda as requirea Oy 10 CFR Part 50, Section 50.55a(g), except where soecific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);

b podsion h d nok F M N P357 CP w s g % q A Acid *F"~^b CATAW8A - UNITS 1 & 2 3/4 0-2

INSERT FOR SPECIFICATION 4.0.3 The time limits of the ACTION requirements are applicable at-the time it is identified.that a Surveillance Requirement has not been performed. The ACTION-requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit 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 .

r I

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

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

Required frequencies for ASME Boiler and Pressure Vessel performing inservice Code and applicable Addenda inspection and testing terminology for inservice activi tie _s inspection and testir.a activities Weekly At least once per 7 days Monthly At least once yer 31 days At least once per 92 days Quarterly or every 3 months At least once per 184 days Semiannuaily or every 6 months At least once per 276 days Every 9 months At least once per 366 days Yearly or annually

c. The provisions of Specification 4.0.2 are acolicable to the above required frecuencies for performing inservice inscection and testing activities;

c. Performance of the acove inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements; and

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

l l

4.0.6 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in Specification 3.0.5 for individual specifica-l tions or whenever certain portions of a specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.

l l

CATAWBA - UNITS 1 & 2 3/4 0-3

h h sa w \%b 3/4.0 APPLICABILITY BASES ine specifications of this sectio, provide the general recuirements (falicable to each of the Limiting Con itions for Operation and Surveillance Req 'rements within Section 3/4 In ,he event of a disagreement between tne requi ments stated in these fechnicai Specifications and those stated in a applica e Federal Regulation or Act,'the requirements stated in the appl isole Federal R ulation.or Act, shall take precedence and shall be met. {,

3.0.1 . is specification defines the apolicability of each soand .ification is in terms of de ed OPERATIONAL MODES or other specified conditio provided to delin te specifically wnen each specification is a _licaole.

3.0.2 This sp ification defines those conditions neces ary to constitute 1 compliance with the t ms of an individual Limiting Conditi for Operation I and associated ACTION r uirement.

3.0.3 This specifica ion delineates the measures

be taken for those j circumstances not directly p ovided for in the ACTION tatements and wnose l For examole, Soecifi-occurrence weuld violate the tent of a specificati n. l cation 3.5.2 reauire< two indeo dent ECCS subsyst s to be OPERABLE and j provides explicit ACTION recuirem ts if one ECC subsystem is inoperacle.

Under the requirements of Specifica ion 3.0.3, f both the required ECCS subsystems are inocerable, within 1 ur meas res must be initiated to place the unit in at least HOT STANDBY withi theaext 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least HOT further example, Specifica-ShuTC0kN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

tion 3.6.2.1 recuires two Containment So Systems to be OPERABLE and provices explicit ACTION requirements if one Sor y stsm is inoperable. Uncer tne requirements of Specification 3.0.3 i both e required Containment Soray Systems are incoerable, witnin 1 ho measure must ce initiated to olace tne unit in at least HOT STANOBY with' the next 6 .ours,.in at least HOT SHUTOChN within the following 6 nours, a in COLD SHUTD0' within the subsecuent ,

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It is acceptable to nitiate and comole e a recuction in CPERATIONAL M00ES in a snorter time inter al than required in t.. ACTICN statement anc to acd tne unused portion of t s allowable out-of-servi e time to tnat provicec for coeration in suoseque lower OPERATION MODE (S). / ated allowaole out-o'- I service times are acclic- le regardless of the OPERATICP L MODE (S) in whien the inoperacility is di covered but the times provided fo achieving a moce recuction are not apol, cable if the inoperability is discov "ed in a moce i lower than ne accli able mode. For examole, if the Containm nt Soray Sjstem was discove. red to

inoperaole wnile in STARTUP, the ACTICN 5. tement acula attained allow uo t) 156 h urs to acnieve COLD SHUTC0%N. If HOT STANDBY .

i in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months rat, r than tne allowed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months would stil. ce availacie However, 4f this before the 91 t would be required to be in COLO SHUTCOWN. provicec system war d acovered to be inocerable while in HOT STANOBY, tne 6 nou, to achie'<e 0T STANOBY would not be additive to the time availaole to ac..i eve150 l l

COLO SnUTP WN so that the total allowaole time is reduced frsi 156 nours t.

' .ours.

' 0.4 This specification provides that entry into an OPERATIONAL MCCE c:

l specified acclicability condition must be made with: (1) tne full

! othe com lement of required systems, equicment, or components OPERABLE and (2) all l

other i:arameters as specified in tne Limiting Conditions for Coeration ceing ]

l 1

CATAWBA - UNITS 1 & 2 3 3/4 0-1

l. ._

(9 TUSERT foR G56 3al 4 3.o Y ~

Soecificatier 2.0.1 thecuch 3.0.a establish the general requirererts applicarle to Liratino Concitions for Operation. These requirements are based on the requirements for Limiting Corditions for Operation stated in the Coce of Federal Regulations, 10 CFR 50.36(c)(2):

"Limiting conditions for operation are the lowest functional capat,ility or perfomance levels of equiprent reevired for safe operation of the facility. When a limiting condition for oceration of a nuclear reactor is n:t ret, the 1icensee shall shut down the reactor or follow any remedial actien pemitted by the technical specification until the condition can be ret."

Specification 3.0.1 establishes the Applicability staterent within each inoivicual specification as the requirement for when (i.e., in which OPERATIONAL MOCES or other specified cerditions) confomance to the Limitirg Conditiens for Operation is reovired for safe operation of the facility. The ACTION requirements establish those reredial reasures that must be taken within specified tire limits when the requirements of a Limiting Ccrdition fcr Operation are not met.

There are two basic types of ACTION recuirerents. The first specifies the remedial reasures that pemit continued operation of tne facility which is not further restricted by the tire limits of the ACTION re uirements. In this case, cenfomance to the ACTION requirerents provides an acceptable level e' safety for unlinited continued operatien as long as tre ACTION requirements continue to be ret. The second type of ACT:CN requirerent speci'ies a tire limit in which conforrance to the conditions of the Liniting Condition for Operation rust be ret. This time limit is the allowable outage tire to restore ar inoperable system or coeponent to CFERASLE status or fer restoring parameters within s;ecified limits. If these actions a e not completed withir requireo to place the facility the allowable cutage time limits, a shutdown i in a PCCE or condition in which the specification no lenger acolies. :t i: '

-not '-terd d th:t P: :hutd wr 'CTION :cuir: :nt; 50 ;;;d :: Or :::r: tic v ri:n : "ich p: 't: ' 0;ti 0) v;lurt:ry ~0t:1 0' : :/;ter' ' c- -

't:- :t've; ; t w;u'd r:t ::u't

-:: per:-tl:) # e ;;r"ic: ir '! u Of oth:r

^n r:dund:nt :y:ter: Or :Orp; rent: tr' g i ::Or:CO.

The specified tire limits of the ACTION reouirements are ecolicable from the reint in time it is identified that a Limiting C:rdition for Operation is cet ret. The time limits c' the ACTION recuirerants are af sn applicable when a systN" or component is recoved from service for surveillance Irdividual scecificatienstesting may orfr:lude investigation of ccerational problems.

a specified time limit for the ccepletien of a Surveillance Fecuirerent w.er, eculpment is removed frer service. In this case, the allewable cutage t' e

1 limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is recuired to comply with ACTION recuirenents, the plant may have entered a MODE in which a new specification oecomes applicable. In this case, the tire limits of tne ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Conditice for Operation are not met.

Scecification 3.0.2 establishes that noncompliance with a specification exists wnen the requirements of the Limiting Condition for Operatien 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) implerentation of the ACTION requirements within the specified tire interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition Operation is restored within the time interval specified in the associated ACTION requirements.

Scc Seecification 3.0.3 establishes the shutdown ACTION recuirements that must be implementee when a Limiting Condition for Operation is not ret 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 MODE when plant operation cannot be maintained within the limits for 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 pemits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would net result in redundant systems or components being inoperable. One Four is allowed to prerare for an orderly shutdewn before initiating a change in plant operation. This tima pemits the operator to coordinate the reduction in electrical gereration with the load dispatcher to ensure the stability and availability of the electrical grid. The tire lirits specified to reach lower MCCES of operation permit the shutdcwn to proceed in a contrnlled and orderly manner that is well within the specified maxirum cooldown rate and within the cooldown capabilities of the f acility assuming only the minimum recuired equipment is OPERABLE. This reduces thermal stresses on corponents of the primary ecolant system and the potential for a plant upset that could challence safety systers under conditions for which this specification applies.

l

! If remedial measures pennitting limited continued operation of the facility l under the provisions of the ACTION recuirements are completed, the shutdowr l may be teminated. The time lirits of the ACTION requirerents are applicable from the point in tire there was a failure to meet a limiting Condition for Operation. Therefore, the sFutdown may be terminated if the ACTION i requirements have been met or the time limits of the ACTION requirerents have l not expired, thus providing an allowence for the completion of the recuired actions.

l l . _ .

The time limits of Specification 3.0.3 allow 37 heurs for the plant to be in the COLD SHUTDOWN MODE when a shutdown is recuired during the POWER WO operation. If the plant is in a lower MODE o' operation when a shutdewn is recuired, the time limit for reaching the next lower FCCE of operation ao-plies.

However, if a lower PCDE of operation is reached in less tire than allowed, the total allowable time to reach COLD SFUTOOWN, 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 SHUT 00WN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because to reach HOT SHUT 00WN is not reduced from the allowable limit of 13 ho Therefore, if remedial reasures are corpleted that would pentit a return to POWER operation, a penalty is not incurred by having to reach a lower PODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage tire limits cf the ACTION requirements, if corpliance with the ACTION recuirerents for one specification results in entry into a PODE or condition of op Operation are not met.

If the new specificatien becomes applicable in less tire than specified, the difference may be added to the allewable cutage limits of the second specification.

of ACTION requirerents for a higher MCCE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Conditien for Operation is not met in a lower PCCE of operation.

The shutdown recuirements of Specification 3.0.3 do not apply in F00ES S and 6, because the ACTION requirements of individual specifications define the recedial measures to be taken.

Specification 3.0.4 establishes limitations nn MODE It precludes placinochanges when the facility in aa limiting Condition for Operation is not ret.

higher MODE of operation when the requirerents for a result in a shutdown to comply with the ACTION recuirements if a change in "CDES were permitted. The purpose of this specification is to ensure that facility operation is net initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain ccepliance with a specification specified limits.

by restoring equipment to OPERABLE status or pa operation of the facility fer an unlimited period of time orovides an accert-able level of safety for centfrued 6peration without There' ore, inregard to the this case, status ertry inte of the plant before er after a MOCE change. be made in accordance an OPEPATIONAL PODE or other specified condition ma.sThe previsions of this with the provisions of the ACTION reovirerents.

specificatien should rot, however, be interpreted as endorsing the f ailure to exercise gced cractice ir restoring systems or cerponents to OPEPABLE s*atus befere plant startup. ii s When a shutdewn is refluired to comply with ACTION recuirerents, the of Specificatien 3.0.4 do not apply because they would delay placing f acility in a lower MODE of ceeration.

l APPLICABfLITY BASES (

met witho t regard f r allow le devia 'ons and t-of-serv'ce provisi ns contain in the A ION st ements.

e intent f this ovision 's to ensur that fa lity oper ion is not ini ated with either r quired e ipment or systems i operable o other spec' fi limits ing exc ded.

Excep ons to is prov' ion have en provi d for a l' ited numbe of pecifica ions,wh STARTUP ith inope able eoui .ent would ot affect lant safety. These e eptions re stated n the ACTI N stateme s of the propr' ate (specif' ations. ,

spudica.h 3. 0. 5_ s spci'inti= delineates the applicability of each specification to unit 1 and Unit 2 operation.

4.0.1 This specification provides that surveillance activities necess l

[ toe ure the Limiting Conditions for Operation are met and will be perfo .ed during e OPERATIONAL MODES or other conditions for which the Limitin ondi-tions for eration are applicable, Provisions for additional surv lance NAL MODES bC activities to e performed without regard to the applicable OPERA equirements.

d or other condit ns are provided in the individual Surveillanc Surveillance Requi ements for Special Test Exceptions need o y be performed q when the Special Tes Exception is being utilized as an e eption to an individual specificati .

TV

't 4.0.2 The provisions f this specification pr ide allowable tolerances

(

for performing surveillance tivities beyond thos specified in the nominal surveillance. interval. lerances are ne ssary to provide operational N @g W) because g "flexibility These of scheduling nd perform ce considerations.

The phrase 0 at least" associated with a survei ance f quency does not negate this p (pc allowable tolerance value and permits erformance of more frequent surveillance activities.

g The tolerance values, taken her indiv' ually or consecutively over three test intervals, are suffi ently restrict e to ensure that the reliability

- associated with the surveilla e activity is not nificantly degraded beyond that obtained from the nomi i specified interval.

4.0.3 The provisi s of this specification set fort, the criteria for determination of com iance with the OPERABILITY recuiremen of the Limiting Conditions for Ope tion. Under this criteria, equipment, sy ems or components are assumed to b OPERABLE if the associated surveillance activ ies have been satisfactorily erformed within the specified time interval. Noth' g in this provision is o be construed as defining equipment, systems or compo ts OPERABLE, en such items are found or known to be inoperable although +fil meeting S e Surveillance Requirements. Items may be determined inocerable .

durin se, during surveillance tests, or in accordance with this specificat. n.

Ther ore, ACTION statements are entered when the Surveillance Requirements sn Id have been performed rather than at the time it is discovered that the

[t5tswerenotperformed. (

CATAWBA - UNITS 1 & 2 B 3/4 0-2

'k T ps6q T 700 B565 % 0.5 Specifications 4.0.1 throuch 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on :te Surveillance Pequirements stated in the Code of Federal Reculation:, ~

10 CFR 50.36(c)(3):

"Surveillance requirements are requirerents relating to test, calibra-tion, or insrection 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."

Specification 4.0.1 establishes the reouirement that surveillances must be performec curing the OPERATIONAL MODES or other conditions for which the recuirements of the Limitine Conditions for Operation apply The unless purpose ofotherwise this speci-stated in an individual Surveillance Requirement.

fication is to ensure that surveillances are perfomed to verify the opera-tional status of systems and components and that parameters are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Recuirements do not have to be perfomed when the facility is in an OPERATIONAL MODE for which the reouirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Recuirerents associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the recuirements of a specification.

Scecification 4.0.2 establishes the conditions under which thea.specified Item permits an t 4e interval for Survei'ilance Requirements may be extended.

allowatele extension of the normal surveillance interval to facilitate surveillance scheduling and consideratir.) of plant operating conditions that ray not be suitable for conducting the surveillance; e.g., Item transient conditions

b. limits the or other ongoing surveillance or maintenance activities.

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 ,iudgment and the reencritien that the most prcbable *esult of any particular surveillance beino perferred is the These provistor>

verification of conformance with the Surveillarce Requirerents.

are sufficient to ensure that the reliability ensured through surveillance activities is ret significantly degradeo beyond that obtained from the specified surveillance interial.

Specification 4.0.3_ establishes the failure to perfor.t a Surveillance Requirerent within the allowed surveillance interval, defined by the provisiers of Specificatien 4.0.2, as a condition that constitutes a failure toUnder meetthethe OPEP/P!LITY requirerents fer a limiting Cendition "or Operation.

6 provisions of this specification, systens and componu ts are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily perfor ed within the specified time interval. However, nothing in this provision is te be construed as implying that systems or cceconents 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 Recuirements 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 identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion cf the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores comoliance with the requirements of Specification 4.0.3. However, this does not necate the fact that the failure to have perforced the surveillance withfr. the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Cordition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirerent and is, therefore, a reportable event under the recuirements of 10 CFP 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

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

Specification 3.0.3, a 24-bcur allowance is provided to permit a delay in implementing the ACTION recuirements. This provides an adequate time limit to complete Surveillarce Requirements that have not been performed. The purpose of this allowance is to permit the ccepletion of a surveillance before a shutdown is required to cor. ply with ACTION recuirements or before other reredial measures would be recuired that may preclude corpletion of a surveillance. The basis for this allowance includes consideration for plart conditions, adecuate planning, availability of personnel, the tire recuired to perform the surveillance, and the safety sienificance of the celay in comp'etin; the recuired surveillance. This provision also provides a time limit 'or the completion of Surveillance Recuirements that become topidcable as a consecuerce of PODE chances imposed by ACTION requirements and for completing Surveillance Pecuirerents that are applicable when an exception to th! requirements of Specification 4.0.4 is allowed. If a surveillance is net completed within the 24-Feur allowance, the tire limits of the ACTION recuirtments are acclicer'e at that tire, When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the tire lir.its of the ACTION requirements are app'.icable at the tire that the survtillarce is teminated.

Surveillance Recuirerents do not nave to be performed on inoperable eouipment because the ACTION recuirerents define the reredial reasures that apply.

However, the Surveillance Pecuirerents have to be cet to demonstrate that ineperable equipment has been restored to OPE W LE status.

b Specificatien 4.0.4 establishes the requirement that all applicable surveillarces must be met before entry into an OPEF.ATIONAL MODE or other The condition purpose of of this operation specified in the ApplicaH lity statement.

specification is to ensure that system and cocoonent OPERAPILITY recuirerents or parameter limits are ret before entry into a MCCE or condition for This which these systems and components ensure safe operatien of the facility.

provision applies to changes in OPERATIONAL MODES or other spe-ified conditions associated with plant shutdown as well as startup.

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

When a shutdown is recuired to comply with ACTION reouirements, the provisiors -

of Specification 4.0.4 co not apply because this would delay placing the facility in a lower MODE of operation.

Specification 4.0.5 establishes the requirernent that inservice inspection of A5ME Code Class 1. 2, and 3 componer ts and inservice testino 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 Crde and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Comission.

This specification includes a clarification of the 'recuencies for perfoming the inservice inspection and testing activities recuired by Section XI of the This clarification ASME Boiler and Pressure Vessel Code and applicable Addendr..

is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frecuencies for perfoming the required inservice inscection and testing activities.

Under the terrs of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Poiler and Pressure Yessel Code and applicable Addenda. The requirements of Srecification 4.0.4 to perfom surveillance activities before entry into an OPEFATIONAL 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 cne week af ter return to nomal op3Mtion. The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is rot capeble of performing its specified function. is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a va've to be 1. capable of per'orring its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months be' ore being declared ineperable.

APcLICABILITY BASES 4.0.4 This specification ensures that the surveillance activities as the(ciated with a Limiting Condition for Operation have been cerformec witn The intent of this provision is to ensure that s vei'-

appi f catQe condition.

lance actVrities nave ceen satisfactorily demonstrated on a current o is as required tu eet the OPERABILITY requirements of the Limiting Condi' on for Operation.

Unde- the ter:t. of this specification, for example, curi. initial plant STARTUP or following xtended plant outages, the aoplicable urveillance activities must be pert ..ed within tne stated surveillanc interval prior to placing or returning the stem or equiament into OPERAB status.

4.0.5 This specificatio ensures that inservice nspection of ASME Coce Class 1, 2 and 3 components and 'nservice testing o ASME Code Class 1, 2 anc 3 pumos and valves will be perfor. d in accordanc with a periodically uccatec version of Section XI of the ASME B 'ler an% or ssure vessel Code and Accenca as required oy 10 CFR Sn.55a. Relief rom an of the aoove requirements nas been crovided in writing by the Comrissi nd is not a part of these Technical Scecifications.

This specification :ncludes a c rificati of ne frequencies for cer-k a testinC ac Jvities recuired by Section (I

} forming tne inservice ir.sc.ction lof tne ASME Boiler and Pr sure 'essel Code and a licaole Accenda. Tnis clarification is oroviced cc sure consistency in rveillance any intervals amoiguities relathe tnroughout tnese Tecnnical S ecifications and to remo to the frequencies for per'orming tne recuired inservic inspection anc testing activities.

Under tne terms f this specification, the more restric.4 ve recuirements l

of tne Tecnnical S cifications take orececenceFor over the ASME examole, tne_r iler anc wirements of Jressure Vessel ce and acclicable Accenda.

Specific,ation 4 4 to perform surveillance activities criar to en *y into an CPERATICNAL M E or otner scecified acclicability condition takes or recence over tne AS Boiler and Pressure Vessel Code provision wnicn allows o mos to '

ce teste up to 1 week after return to normal operation. And for eximoi.

tne Te nical Specification definition of OPERABLE does not grant a grace ;

i cerio cefore a cevice that is not cacaole of performing its specified funct n r is clarea inoperable and takes precedence over tne ASME Boiler ana Pressure V sel Code provision wnich allows a valve to be incacaule of performing its /

ecified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being ceclared inoperacle. - - ,,,,,_ / ,

,L 5pede.%,'ea M hhnedg3 % a g,ca,i, g 4, 3,gey,ncc_

o.chivM s M L{d i exI M 2 operadwns.

l CATAWBA - UNI'5 1 & 2 B 3/4 0-3

(I POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and

3. Identify at:1 correct the cause of the out-of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

d. Th: pr;;i:f:n: Of Sp::ffic:ti;n 3.0.4 er; net ;ppli;; tie.

SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when aoove 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CATAWBA - UNITS 1 & 2 3/4 2-14

TABLE 3.3-1 k REACTOR TRIP SYSTEM INSTRUMENTATION E

g MINIMUM

, TOTAL NO. CHANNELS CHANNELS APPLICABLE I

c. FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5

gl 1. Manual Reactor Trip 2 1 2 1, 2 1

~ 2 1 2 3*, 1*, S* 10 i m 2. Power Range, Neutron Flux

a. High Setpoint 4 2 3 1, 2

b. Low Setpoint 4 2 3 1###, 2

3. Power Range, Neutron Flux 4 2 3 1, 2 2/

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2/

R High Negative Rate u

5. In ermediate Range, Neutron Flux 2 1 2 l###, 2 3

6. Sour ce Range, Neutron Flux

a. Startup 2 1 2 2## 4 7

o. Shutdown (Unit 1) 2 1 2 3*, 4*, S* 10 g (Unit 2) 2 1 2 3, 4, 5 5' (_

7. Overtemperature AT

, Four Loop Operation 4 2 3 1, 2 6 8 . Overnower AT kk Fous Loop Operation 4 2 3 1, 2 g 5E fg gg 9. Pressurizer Pressure-Low 4 2 3 1 55 M

22 hh 00 h .

TABLE 3.3-1 (Continued) k> REACIOR TRIP SYSTEM INSTRUMENTATION MINIMUM 10TAL NO. CHANNELS CHANNELS APPLICABLE

. ACTION OF CHANNELS 10 TRIP OPERABLE MODES c FUNCTIONAL UNIT 3 4 2 3 1, 2

d 10. Pressurizer Pressure-High Pressurizer Water Level-High 3 2 2 1

e. 11.

n

12. Reactor Coolant Flow-Low 2/ loop in

a. Single Loop (Above P-8) 3/ loop 2/ loop in 1 any oper- each oper-ating loop ating loop Two Loops (Above P-7 and 3/ loop 2/lotp in 2/ loop 1

b. each oper-two oper-below P-8) ating loops ating loop

{ 3/ste gen

Steam Generator Water 4/sta 2/sta gen 1, 2 Y 13.

gen in any each

'd Level--Low-Low operating operating sta gen sta gen 3 1

14. Undervoltage-Reactor Coolant 4-1/ bus 2 6f Pumps (Above P-7)

NE 15. Underfrequency-Reactor Coolant 4-1/ bus 2 3 1

@@ Pumps (Above P-7)

"" Turbine Trip

16. 2 3 1#### 7

a. Stop Valve EH Pressure 4 Fg

b. Turb ne Stop Valve Closure 4 4 1 1#### f

$$ 17. Safety injection Input 2 1, 2 9 2 1

from ESF 05

TABLE 3.3-1 (Continued)

TABLE NOTATIONS

0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rcd withdrawal.

- Comply with the provisions of Specification 3.3.2, for any portion of the g/

channel required to be OPERABLE by Specification 3.3.2.

Th; prai:ica; ;f Sp;;ific;ti;n 3.0.1 ;r: n;t applic;t,le.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

1. 1. 1. Above the P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , [

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed f or up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months [

for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or

b. Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

CATAWBA - UNITS 1 & 2 3/4 3-5 AmendmentNo.!(Unit 1)

AmendmentNo./(Unit 2)

IABIL 3.3-3 9

(NGINLLHlD SAILlY FEAIURES ACIUAI10N SYSTEM INS 1RUMENIAll0N h

MINIMUM 101AL NO. CilANNELS CHANNELS APPLICABLE E ACIl0N IUNC110NAL UNil Of CllANNELS 10 IRIP OPERA 8LE MODES

]

Safety injection (Reactor 1.

1 rip, Phase "A" Isolation,

" Ieedwater Isolation, Control Room Area Vesitilation Opera-tion, Auxiliary feedwater-Motor-Driven Pump, Purge &

Exhaust isolation, Annulus Ventilation Operation, -;

Auxiliary Building filtered l w Exhaust operation, Emergency 2 Diesel Generator Operation, w Component Cooling Wter.

O lurbine Irip, and Nuclear Service Water Operation) 2 1, 2, 3, 4 18

a. Manual Initiation 2 1 2 2 1, 2, 3, 4 14

b. Automatic Actuation 1 Logic and Actuation Relays 3 2 2 1, 2, 3 ISE

c. Contaisunent Pressure-High 2 3 1, 2, 3# 19M

d. Pressuriier 4 Pressure-Low

e. Steain Linie Pressure- 3/ steam linie 2/ steam linie 2/ steam line 1, 2, 3# 1 1ow in any steam 1ine

~ ~ '

_ . _ _ . . _ _ _ _ __,,a

I Alli t 3. 3-3 (Continued) .l LNGINilRf D SAll IY i~l AIURE S ACIUAll0N SYSILM INSIRUMLNTAll0N N

~

MINIMUM 101AL NO. CilANNElS CilANNEl5 APPLICABLE-c-

10 1 RIP OPERABIE MODES AC110N g IONCI10NAL UNII Of CilANNILS o

~ 3. Contaisimesit Isolation (Continued) e to c. Purge and Exhaust Isolationi Manual Initiation 2 1 2 1,2,3,4 17 1) 2 1, 2, 3, 4 17

2) Automatic Actuation 2 1 logic and Actuation Relays M See item 1. above for all Safety injection initiating functions and

3) Safety injection Y requirements.

'C

4. Steam Line Isolation I

a. Manual Initiation 1

2 1 2 1, 2, 3 22

1) System 23 Individual 1/ steam line 1/ steam line 1/ operating 1, 2, 3

2) steam line 2 2 1,2,3 21

b. Automatic Actuation 1 Iogic and Actuation Relays 4 2 3 1, 2, 3 1

c. Containment Pressure-liigiritigh

d. Steam Iine Pressure- 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# II low in any steam Iine

. _ ___ _ - - .-. - _=. .-

i TABIL 3.3-3 (Centinued) 4 n,

C INGINLIRIO SAlllY FE AIURES ACIUAll0N SYSllM INSIRlMENIAIION 2-

MINIMUM i g 101AL NO. CilAhNELS CHANNELS APPLICABLE IUNC110NAL UNIT OF CilANNELS 10 1 RIP OPERABLE MODES ACTION

]

4. Steam Line Isolation (Continued) e-N e. Steam Line Pressure - 3/ steam line 2/ steam line 2/ steam line 3H ISI I Negative Rate-High in any steam line

! S. Feedwater Isolation Automatic Actuation 2 2 1, 2 27

a. 1 m logic and Actuation

) Relays .

b. Steam Generator 4/ steam 2/ steam 3/ steam 1, 2 194 Y generator in generator in g Water Level- generator any operating each operating liigh-High (P-14) steam steam generator generator

c. 1 avg

-low (P-4 2 3 1, 2 19N Interlock) 4

d. Doghouse Water 2 1, 2 27 Level-High 2 1

e. Safety injection See item 1. above for all Safety injection initiating functions and requirements.

6. lurbine trip i

Maniual 1:iitiationi 1 1,2 25

a. 1 1

b. Automatic Actuation logic and Actuationi 1,2 27 Relays 2 1 2

- . - ~ , . . - , ._, -, ._ .-. , s,.- ,.. . _ , .

IABIE 3.3-3 (Continued)

LNGINLlRLD SAIElY FEAluRLS AC10All0N SYS1EM INSTRUMENTA110N a.

2 HiNINUH 101AL NO. CilANNELS CHANNELS APPLICABLE c ACIIGN OF CilANNELS 10 1 rip OPERABLE N00ES IUNCI10NAL UNII

- 6. Turbine Irip (Continued) e-ro c. Steam Generator Water 1,2 19N Level-liigh-liigh (P-14) 4/ steam 2/ steam 3/ steam generator generator in generator in any operating eacia operating steam steam generator generator

d. Irip of All Main 1,2# 25 feedwater Pumps 2/ pump 1/ pump 1/ pump

{

2 2 2 1,2,3 22 Y e. Reactor Irip (P-4) t$ See Item 1. above for all Safety Injection initiating functions

f. Safety injection and requirements.

7. Containment Pressure Control System 4/traisi 2/traisi 3/ train 1, 2, 3, 4 l'M

a. Start Permissive

b. Iermination 4/ train 2/ train 3/ train 1, 2, 3, 4 <

8. Auxiliary feedwater 1/traisi 1/ train 1, 2, 3 26

a. Manual Initiation 1/ train 2 1, 2, 3 21

b. Automatic Actuationilogic 2 1 azul Actuation Relays

IAHiL 3.3-3 (Continued) b i NGINIIHiD SAI LiY I EAiURES AClllAll0N SYSILM INSIRilMINIA11tsM

.M 2-MINIMlM I0IAL NO. CilANNELS CilANNELS APPLICABLE c MODES ACIION Of CilANNftS 10 1 RIP OPERABLE 3 IONCIl0NAL tlN17~

g 8. Auxiliary feedwater (Continued) e-m c. Sim. Gen. Water level-low-Low

1) Start Motor- 2/sta. gen. 3/sta. gen. 1, 2, 3 l'M l Driven Pumps 4/sta. gen.

in any opera- in each ting sta. gen. operating sim. gen.

2) Start lurbine- 4/sta. gen. 2/sta. gen. 3/sta. gen. 1, 2, 3 19N

'I Driven Pump in any two in each

@ operating operating sim. gen. sim. gen.

d. Safety injection- See Item 1. above for all Safety Injection initiating functions Start Motor-Driven Pimos and requirements.

c. Ioss-of-Offsite Power-Start Motor-Driven Pumps and Turbine-Driven Pump 6-3/ bus 2/ bus 2/ bus 1, 2, 3 1h either bus

f. Irip of All Main Icedwater Pumps-Start Motor- 1, 2# 25 2/ pump 1/ pump 1/ pump Driven Pimips

-- - -,w.. -

.-v-e ,4 .--, m - - --

r- . n - ,-

1 Allil 3.3-3 (Continued) h INGINILRID SAILIY IEAIURES ACIllAll0N SYSILM INSTRUMENIATION MINIMUM I0IAL NO. CilANNELS CilANNELS APPLICABLE e

3 IONCIl0NAL UNil 0F CHANN[LS 10 IRIP OPERABLE MODES ACTION v>

co 8. Auxiliary f eedwater (Continued)

- g. Auxiliary feedwater

" Suction Pressure-Low

1) CAPS 5220, 5221, 3/ pump 2/ pump 2/ pump 1, 2, 3 IS 5222

2) CAPS 5230, $231, 3/ pump 2/ pump 2/ pump I, 2, 3 15 5232 w 9. Containment Sump 1 Recirculation T a. Automatic Actuation 2 1 2 1,2,3,4 14 l3 Logic and Actuation Relays

b. Refueling Water Storage Iank level-Low 4 2 3 1,2,3,4 16 Coincident With Safety injection See item 1. above for all Safety Injection initiating functions and requirements.

10. loss of Power )

a. 4 kV Bus Undervoltage- 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 Id toss of Voltage

b. 4 kV Bus Undervoltage-Grid Degraded Voltage 3/ flus 2/ Bus 2/ Bus I, 2, 3, 4 IM

11. Control Hoom Area Ventilation Operation

a. Automatic Actuation logic 2 2 All 24 and Actuation Relays 1

I AlllE 3.3-3 (Continued)

" LNGINilRll) 5AILlY II AluRf 5 ACIUA110N SYSilM INSIRtMENIAll0N 4

MINIMIM 101 Al NO. CilANNELS CHANNELS APPtICABLE c MODES ACIl0N

Of CilANNLIS 10 TRIP OPil:ABLE IUNC110NAt ilNil U

g 11. Control Room Area

e. Ventilation Operatiori (Continued) ,

m v

loss-of-Offsite Power 3 2 2 1,2,3 SA b.

c. Safety injection See Item 1. above for all Safety injections initiating functions and requirements. ,

12. Containment Air Return and Ilydrogen Skimmer Operationi Manual Initiation 2 1,2,3,4 18

$ a. 2 1 w

,', b. Automatic Actuatiori logic

" and Actuation Relays 2 1 2 1,2,3,4 14

c. Containment Pressure- 1,2,3 16 2 3 liigh-liigh 4

13. Annulus Ventilation Operation 2 1,2,3,4 18

a. Manual Initiation 2 1

b. Automatic Actuation logic and Actuation Relays 2 1 2 1,2,3,4 14

c. Safety injection See item 1. above for all Safety injection initiating functions and requiremerits.

14. Nuclear Service W ter Operation 2 1,2,3,4 18

a. Manual Initiation 2 1 S. Automatic Actuation logic 1,2,3,4 21 and Actuation Relays 2 1 2

l 1ABlE 3.3-3 (Continued) 2 if LNGINilRID SAFEIY IEAIURES ACIUAIION SYSTEM INSTRUMENIA110N M.

2

' MINIMUM 10lAL NO. CllANNELS CllANNELS APPLICABLE ji Of CllANNELS TO 1 RIP OPERABLE MODES ACTION S1 EUNCIl0NAL UNil v

D" 14. Nuclear Service Water Operation

"* (Continued) ca

c. Loss-of-Of fsite Power 3 2 2 1,2,3 Id(

d. Containment Spray see item 2. above for all Containment Spray initiating functions and requirements.

See item 3.b. above for all Phase "B" Isolation initiating functions

e. Phase "B" Isolation dnd r?quirements.

u, f. Safety injection See Item 1. above for all Safety injection initiating functions 3: and requirements.

';" g. Suction Iransfer-Low 21 Pit Level 2 1 2 1,2,3,4 tj

15. Emergency Diesel Generator Operation (Diesel Building Ventilation Operation, Nuclear Service Water Operation) 2 1,2,3,4 18

a. Manual Initiation 2 1

b. Automatic Actuation Logic and Actuation Relays 2 1 2 1,2,3,4 1-2 2 1,2,3,4 ISI

c. loss of-Offsite Power 3

d. Safety injection See item 1. above for all Safety injection initiating functions and requirements.

16. Auxiliary Building f iltered Exhaust Operation 2 1,2,3,4 18

a. Manual Initiation 2 1

b. Automatic Actuation logic 2 1,2,3,4 21 and Actuation Relays 2 1

TABLE 3.3-3 (Continued) ,

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

"Th: pr:vi:icn: Of- Sp :ific:ticr 2.0.1 cr; n:t :pplic:bl;.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inocerable channel is placed in the. tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable enannel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE recuirement, operation may continue provided the containment purge supply and exnaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE channels one less tnan the Minimum Channels OPERABLE requirement, restore the inocerable cnannel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY 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 .

ACTION 19 - With the number of OPERABLE channels one less tnan the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfiec:

a. The inoperable channel is placed in the tripped conoition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , anc D. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for sur-veillance testing of other channels per Specification 4.3.2.1.

CATAWBA - UNITS 1 & 2 3/4 3-25

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, a'djust 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 channwis for plant operations inoperable, take the ACTION shown in Table 3.3-6.

c. TheprovisionsofSpecificationf3.0.3;nd2.0.5arenotapplicable.

SURVEILLANCE REOUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations for tne MODES and at tne frequencies shown in Table 4.3-3.

CATAWBA - UNITS 1 & 2 3/4 3-51

-INSTRUMENTATION HOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a. At least 75% of the detector thimbles,

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

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

APPLICABILITY: When the Movable Incore Detection System is used for:

a. Recalibration of the Excore Neutron Flux Detection Systern, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of F g, F (Z) and F xy, 9

ACTION:

With the Movable Incore Detection System inoperable, do not use the system for the aoove applicable monitoring or calibration functions. The previsions of Specificationf 3.0.3 =d 3.0.1 are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.2 The Movable Incore Detedtion System shall be demonstrated OPERABLE st least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by irradiating each detector used and determining the acceptability of its voltage curve for:

a. Recalibration of the Excore Neutron Flux Detection system, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of F g, Fg(Z), and F,y.

CATAWBA - UNITS 1 & 2 3/4 3-55

INSTRUMENTATION SEISMIC INSTRUMENTATION :

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

APPLICABILITY: At all times.

ACTION:

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

b. The provisions of Specification / 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALI-BRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Teble 4.3-4.

4.3.3.3.2 Each of the above accessible seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g snall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. Data retrieved from the triaxial time-history accelerograpn shall include a post-event CHANNEL CALIBRATION obtained by actuation of the internal test and calibrate function immediately prior to removing data. CHANNEL CALIBRATION shall be performed immediately after insertion of the new recording media in the triaxial time-history accelero-graph recorder. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing tne magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

CATAWBA - UNITS 1 & 2 3/4 3-56

4 INSTRUMENTATION s METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring inJtrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

b. TheprovisionsofSpecification/3.0.3and3.0.5arenotapplicable.

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

CATAWBA - UNITS 1 & 2 3/4 3-59

INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.3.3.7 Two independent Chlorine Detection Systems, with their Alarm / Trip Setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 pps, shall be OPERABLE.

APPLICA8ILITY: All MODES.

ACTION:

a. With one Chlorine Detection System inoperable, restore the inoperable system 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 the Control Room Area Ventilation System with flow through'the HEPA filters and charcoal adsorbers,

b. With both Chlorine Detection Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and charcoal adsorbers.

. '5: pr:;i:!: : cf 5;;;i't :ti r 3.0." :r: n t :pplic:ble, ,

SURVEILLANCE REQUIREMENTS 4.3.3.7 Each Chlorine Detection System shall be demonstrated OPERABLE by cerformance of a CHANNEL CHECX at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

P

{

i CATAWBA - UNITS 1 & 2 3/4 3-70

INSTRUMENTATION f FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire o detection zone shown in Table 3.3-11 shall be OPERABLE. , l APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

a. With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in Table 3.3-11 inoperable, :

restore the inoperable instrument (s) to OPERABLE status within 14 days or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establisn 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 that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in ,

Speci fication 4. 6.1. 5.

b. With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Function B fire detection instruments shown in Table 3.3-11 inoperaole, '

or with any two or more adjacent fire detection instruments shown in '

J Table 3.3-11 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the contain-ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

c. The provisions of Specification / 3.0.3 :n: 2.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each of the above rectiired smoke detection or flame detection instru-ments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST. Detectors which are not accessible during plant operation shall be demon- i strated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUT 00WN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months. ;

4.3.3.8.2 Each of the above required heat detection instruments shall be cemon-strated OPERABLE as follows: ,

a. For nonrestorable spot-type detectors, at least two detectors out of i i

every hundred, or fraction thereof, shall be removed every 5 years and functionally tested. For each failure that occurs on the detectors

! removed, two aaditional detectors shall be removed and tested; and I

CATAWBA - UNITS 1 & 2 3/4 3-71 ,

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.9 The Loose-Part Detection System shall be OPERABLE.

APPLICA8ILITY:

MODES 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 pursuant to Specification 6.3.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b. The provisions of Specificationp 3.0.3 n.d 3.0.t are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each channel of the Loose-Part Detection Systems 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. An ANALOG CHANNEL OPERATIONAL TEST except for verification of Setpoint at least once per 31 days, and

c. A CHANNEL CALIBRATION at least once per 18 months.* f "ThissurveillanceneednotbeperformeduntilpriortoenteringSTARTUPfollowingf[

(This applies to Unit 1 only.)

the Unit 1 first refueling.

CATAWBA - UNITS 1 & 2 3/4 3-79 AmendmentNo./((Unit AmendmentNo./ Unit 2) 1) uwg

INSTRUMENTATION RADIOACTIVE LIQUIO EFFLUENT MONITORING _ INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm /

Trip Setpoints of these channels shall be determined and adjustqd in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip ietpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.7 why this inoperability was not corrected within the time specified,

c. TheprovisionsofSpecification/3.0.34 .r4 3.0.4. are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECX, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequen,cies shown in Table 4.3-8.

I CATAWBA - UNITS 1 & 2 3/4 3-80

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3,3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the 00CM.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above -

specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

. b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected within the time specified.

c. TheprovisionsofSpecification/3.0.3and3.0.tarenotapplicable.

SURVEILLANCE REOUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-9.

4

)

d l

i l

CATAWBA - UNITS 1 & 2 3/4 3-CS

INSTRUMENTATION 3/4.3.3.12 BORON DILUTION MITIGATION SYSTEM ;

4 LIMITING CONDITION FOR OPERATION

\ t 3.3.3.12 As a minimum, two trains of the Boron Oilution Mitigation System shall be OPERABLE and operat h.g with Shutdown Margin Alarm ratics set at less /

than or equal to 4 times ths-steady-state count rate.

APPLICABILITY: MODES 3, 4, AND 5 (UNIT 1 ONLY)

ACTION:

(a) With one train of the Boron Dilution Mitigation System inoperable or not operating, restore the inoperable train '.o OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or (1) suspend all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with -

Alarm Setpoints less than or equal to one-half decade above the steady-state count rate and verify that the combined flowrate from both Reactor Makeup Water Pumps is less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) within the next hour. \

(b) With both trains of the Boron Dilution Mitigation System inoperable or not operating, restore the inoperable trains to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or (1) suspenu all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade above the steady-state count rate and verify that the combined flow rate from both Reactor Makeup Water Pumps is less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) within the next hour.

(c) T" pr:vici n; cf Specification 3.0.4 are nat applicella.

SURVEILLANCE REQUIREMENTS 4.3.3.12.1 Each train of the Boron Dilution Mitigation System shall be demon- '

strated 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 , CATAWBA - UNITS 1 & 2 3/4 3-92a Amendment No. (Unit 1)

Amendment No.

(Unit 2) [

1 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 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.

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.

i

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200'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.

d. Th; pr;visi;n:; cf Sp;;ificati:n 3.0.4 are n;; applic212.

SURVEILLANCE REOUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per tne recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

CATAWBA - UNITS 1 & 2 3/4 4-39

3 PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie ,

of removable contamination. l APPLICABILITY: At all times.

ACTION:

a. With a sealed source having remevablo contamination in excess of the above limits, immediately 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.

b. TheprovisionsofSpecification/3.0.3:r.d3.0.5arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.9.1 Test Requirements - Each sealed source shall be tested for leakage l and/or contamination by:

l

a. The licensee, or

b. Other persons specifically authori:ed by the Commission or an Agreement State.

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

4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startuo 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 6 months for all sealed sources containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogon 3),

and ,

2) In any form other than gas.

CATAWBA - UNITS 1 & 2 3/4 7-25

PLANT SYSTEMS 3/4.7.10 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10.1 The Fire Suppression Water System shall be OPERABLE with:

a. At least two fire suppression pumps, each with a capacity of 2500 gpm, with their disenarge aligned to the fire suppression header, and

b. An OPERABLE flow path capable of taking suction from Lake Wylie and transferring the water through distribution piping with OPERABLE sectionalizing control valves and isolation valves for each sprinkler, hose standpipe, or Spray System riser recuired t0 be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.

APPLICABILITY: At all times.

ACTION:

a. With one of the above required pumps and/or one Water Supply /Distri-bution System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pumo or supply. TheprovisionsofSpecification)3.0.3an: ';.0.5 are not applicable.

b. With the Fire Suppression Water System otherwise inoperable establish a backup Fire Suppression Water System within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l CATAWBA - UNITS 1 & 2 3/4 7-27

f PpNTSYSTEMS ;

CO21Y, STEMS LIMITING CONDITION FOR OPERATION 3.7.10.3 The following High Pressure and Low Pressure CO2 Systems shall be OPERABLE:

a. Low Pressure C0: System - Diesel generator rooms, and

b. High PGissure CO2 System - Auxiliary feedwater pump rooms.

APPLICABILITY: Whenever equipment protected by the CO2 Systems is required to De OPERABLE.

ACTION:

a. With one or more of the above required CO2 Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol,

b. The provisions of Specification ( 3.0.3 n d 2.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.3.5 Each of the above required CO2 Systems shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.

4.7.10.3.2 Each of the above required Low Pressure C0: Systems chil] be demonstrated OPERABLE:

a. At least once per 7 days by verifying the CO: storage tank level to be greater than 44% of full capacity, and i

b. At least once per 18 months by verifying:

Each system actuates manually and automatically, upon receipt f.

1) of a simulated actuation signal, i

i

2) Damper closure devices receive an actuation signal upon system aperation, and l

! 3) By a visual inspection of discharge no::les te assure no blockage.

1 i CATAWBA - UNITS 1 & 2 3/4 7-31

2 PLANT SYSTEMS FIRE HOSE STATICNS .

LIMITING CONDITION FOR OPERATION 3.7.10.4 The fire hose stations given in Table 3.7-3 shall be OPERABLE.

~

APPLICABILITY: Whenever e'quipment in.the. areas prof.ected by the fire hose

~

stations is required't'o be 0PERABLE. .

ACTION: -

a. With one or more of the fire hose stations given in Table 3.7-3 inoperable, provide gated wye (s) on the nearest OPERABLE hose station (s). One~ outlet of the wye shall be connected to the standard length of hose provided for/the hose station. The second outlet of the wye shall b'e connected to a length of hose sufficient to provide coverage for the area left. unprotected by the inoperable hose station. Where it can be demonstrated that the physical reuting'of the fire hose would result in a recognizable hazard to station personnel, plant equipment, or the hose itself, the fire hose shall- be stored in a roll at the outlet of the OPERABLE hose station. Signs snall be mounted above the gated wye (s) to identify the proper hose to use. The above ACTION requirement shall be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire nose is the primary means of fire suppression; otherwise route the aoditional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. The provisions of Specification) 3.0.3 and .0.1 are not applicable.

SURVEILLANCE RE0VIREMEN15 4.7.10.* Each of the fire hose stations given in Table 3.7-3 shall be demonstrated OPERABLE:

a. At least once per 31 days, by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station,

b. At least once per 18 months, by:

1) Visual inspection of the stations not accessible duri , plant l operations to assure all required equipment is at the tation, l

l 2) Removing the hose for inspection ar> reracking, and

3) Inspecting all gaskets and replacing any degraded gaskets in l the couplings.

l

c. At least once per 3 years, by:

1) Partially opening each hose station valve to verify valve OPERABILITV and no flow blockage, and

2) Conducting a hose hydrostatic test at a pressure of 200 psig or l

at least 50 psig above maximum fire main operating pressure, whichever is greater l

l CATAWBA - UNITS 1 & 2 3/4 7-33 t

a PLANT SYSTEMS 3/4.7.11 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.11 A11~ fire barrier penetrations (walls, floor / ceilings, cable tray enclosures.and.other fire barriers) separating safety-related fire areas or -

separating portions of redundant systems important to safe shutdown within a fire area and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable, piping, and ventilation duct pene-tration seals) shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire barrier penetrations and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a continuous fire watch on at least one side of the affected pene-trat. ion, or verify the OPERASILITY of fire detectors on at least one side of the inoperable penetration and establish an hourly fire watch patrol,

b. The provisions of Specification / 3.0.3 =c 3.0.5 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.1 At least once per 18 months the above required fire barrier penetrations and sealing devices shall be verified OPERABLE by performing a visual inspection of:

a. The exposed surfaces of each fire rated assembly; ,

i

b. At least 10% of all fire dampers. If apparent changes in appearance

( or abnormal degradation are found, a visual insoection of an additional 10% of the dampers shall be made. This inspection l

! process shall continue until a 10% sample with no apparent changes in appearance or abncrmal degradation is fouM. Samples snall be I

selected such that each fire damper will be inspected every 15 years; and

c. At least 10% of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made.

This inspection process shall continue until a 10% sample with no apparent enanges in appearance or abnormal degradation is found.

Samples shall be selected such that each penetration seal will be inspected every 15 years.

CATAWBA UNITS 1 & 2 3/4 7-36

REFUELING OPERATIONS 3/4.9.7 -CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 3000 pounds

shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With fuel assemblies in the storage pool.

ACTION:

a. With the requirements of the above specification not satisfied, place the crane load in a safe condition.

b. The provisions of Specificationg 3.0.3 :nd 3.0.5 are not applicacle.

SURVEILLANCE REOUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly and control rod, shall be verified to be less than or equal to 3000 pounds prior to moving it

+ over fuel assemolies."

I 2

I "Weir gates of the spent fuel pool may be moved by crane over the stored fuel provided the scent fuel has decayed for at least 17.5 days since last being part of a core at power.

CATA'nBA.- UNITS 1 & 2 3/4 9-9

L

-REFUELING OPERATIONS 3/4.9.10 WATER LEVEL-STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of irradiated fuel assemolies seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

a. With the requirements of the above specific'ation not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

b. The provisions of Specification / 3.0.3 rd 2.0.' are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level in the storage pool shall be determined to be at least its minimum required depth at least once per 7 days wnen irradiated fuel assemblies are in the fuel storage pool.

CATAWBA - UNITS 1 & 2 3/4 9-13

REFUELING OPERATIONS 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.9.11 At least one train of the Fuel Handling Ventilation Exnaust System shall be OPERA 8LE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With both trains of the Fuel Handling Ventilation Exhaust System inoperable, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until the Fuel Handling Ventilation Exhaust System is restorea to OPERA 8LE status,

b. The provisions of Specification / 3.0.3 cnd 3.P.2 are not applicaole.

SURVEILLANCE REQUIREMENTS 4.9.11.1 One train of the Fuel Handling Ventilation Exhaust System shall be cetermined to be operating and discharging through the HEPA filter and carcon adsorbers at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever irradiated fuel is being moved in the storage pool and during crane operation with loads over the storage pool.

4.9.11.2 Both trains of the Fuel Handling Ventilation Exhaust System snali ce '

demonstrated OPERABLE:

a. At least once per 31 days by initiating, from the control room, flow tnrough the HEPA filters and carbon adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating;

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

1) Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses tne test procedure guidance in Regulatory Positions C.5.a. C.S.c, and C.5.d* of Regulatory Guide 1.52, Revision 2, March 1973, and tne system flow rate is 16,565 cfm 10%;

"Tne requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and ocerating.

CATAWBA - UNITS 1 & 2 3/4 9-14

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION

.3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from racioactive materials in liquid effluents released, from each unit, to UNRESTRICTED rREA5 (see Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole 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 whole body and to less than or equal to 10 mrems to any organ.

APDLICABILITY: 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 comDliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies witn regard to the requirements of 40 CFR Part'141, Safe Orinking Water Act."

b. TheprovisionsofSpecificationf3.0.3crd2.0.'arenotapolicacle.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be ceterminea in accorcance with the metnodology and parameters in the 00CM at least once per 31 days.

"ine requirements of ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles downstream of the plant discharge.

l l CATA'n8; - UNITS 1 & 2 3/4 11-5

+~*-g-, . - - , - , . , - ~ ~ , - ,,

RADI0 ACTIVE EFFLUENTS LIOUID RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and sopropriate portions of tne system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole boay or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: 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 Soecification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid 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 Specification / 3.0.3 xd 3.0.1 are not applicacle.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methocology and parameters in the 00CM when Liquid Radwaste Treatment Systems are not l being fully utili;:ed.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be consicered OPERABLE by meeting Speci fications 3.11.1.1 and 3.11.1.2.

l

\

l l

l CATA'aBA - UNITS 1 & 2 3/4 11-6

1 i

l 1

I RADI0 ACTIVE EFFLUENTS LIOUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately 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, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Speci fication 6.9.1. 7.

b. The provisions of Specificationt 3.0.3 and 2.0.2 are not applicable.

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

CATAWBA - UNITS 1 & 2 3/4 11-7

RADIOACTIVE EFFLUENTS CHEMICAL TREATMENT PON05 LIMITING CONDITION FOR OPERATION

3.11.1.5 The quantity of radioactive material contained in each cnemical treatment pond :,nall be limited by the following expression:

A 264 -

< 1. 0 J

excluding tritium and dissolved or entrained noble gases, Where:

A. = pond inventory limit for single radionuclide "j", in Curies; J

C. = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for J single radionuclide "j", microcuries/ml; V = design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microcuries/ Curie per milliliter / gallon.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed ponds exceeding the above limit, immediately suspend all additions of radioactive material to the pond and initiate corrective action to reduce the contents to within the limit,

b. TheprovisionsofSpecification/3.0.3c.nd2.C.?arenotaoplicable.

SURVEILLANCE REOUIREMENTS 4.11.1.5 The quantity of radioactive material contained in each oaten of resin / water slurry to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative samDie of the baten to be transferred to the chemical treatment ponos snali ce limited by the expression:

C d < 0.006 j C)

Where:

c. = radioactive resin / water slurry concentration for radionuclide "j" 3 entering the UNRESTRICTED AR.EA chemical treatment ponds, in microCuries/ milliliter; and C B,' Table II, Column 2, concentration for y = 10 CFR Part 20, Appendix single radionuclide "j", in microcuries/ milliliter.

CATAWSA - UNITS 1 & 2 3/4 11-8

+

RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION

'3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-4) shall be limited to the following:

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

APPLICABILITY: At all times.

ACTION

a. With the calculated air dose from radioactive noDie 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 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.

b. TheprovisionsofSpecificationl3.0.3;nd2..1arenotacplicable.

SURVEILLANCE REOUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance witn the methodology and parameters in the 00CM at least once per 31 days.

CATA'WBA - UNIT 51 & 2 3/4 11-13

RADI0 ACTIVE EFFLUENTS DOSE - IODINE-131.-100lNE-133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 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 greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BCUNDARY (see Figure 5.1-4) snall 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.

APDLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with nalf-lives greater than 8 days, in gaseous effluents exceeding any of tne acove limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies tne cause(s) for exceeding the limit and defines the corrective actions that have been taken to re1uce the releases and the proposed corrective actions to be taken to issure that suosequent releases will be in compliance with the above limits.

D. The provisic.is of Specification / 3.0.3 ;r.d 2.0.1 are not acolicaole.

SURVEILLANCE RE0U1REMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iooine-133, tritium and radionuclices in carticulate form with half-lives greater tnan 8 days snall Oe determined in accorcance with the metnodology and parameters in tne 00CM at least once per 31 days.

I i

l CATAWBA - UNITS 1 & 2 3/4 11-14

RADIOACTIVE EFFLUENTS GASEOUS RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION ,

3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLOUP SYSTEM shall be OPERABLE and appropriate portions of these s'ystems snali ce used to reduce releases of radioactivity when the projected coses in 31 days due to gaseous effluent releases, from eacn unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-4) would exceed either:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

At all t,mes.

APPLICABILITY:

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to tne Commission within 30 days, pursuant to Specification 6.9.2, a Soecial 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 equipi;nt to OPERABLE status, and

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

b. The provisions of Specification) 3.0.3 ad 2.0.' are not apolicaole.

SURVEILLANCE REOUIREMENTS 2.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY snall be projected at least once per 31 days in accordance with the metnodology and parameters in the 00CM wnen Gaseous Racwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Specification 3.11.2.1 ano 3.11.2.2 or 3.11.2.3.

CATAWBA - UNITS 1 & 2 3/4 11-15

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall ce limited to lass tnan or equal to 2% by volume wnenever the hydrogen concentration exceeds 4% by ' volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With t' concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce tne concentration of oxygen to less than or equal to 4% by volume; then take ACTION a. above.

C. TheprovisionsofSpecification/3.0.3and:.0.5arenotapplicable. .

SURVEILLANCE REOUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the WASTE GAS HOLOUP SYSTEM shall be cetermined to be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hyarogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.

i CATAhBA - UNITS 1 & 2 3/4 11-16

e

RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank snall be limited to less than or equal to 97,000 Curies of noble gases (con-sidered as Xe-133 equivalent). l APDLICABILITY: At all times.

ACTION:

a. Witn the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.

b. TheprovisionsofSpecification/3.0.3and3.C.!arenotapplicaole.

SURVEILLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank snall be determined te be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

1 l

l CATA'nBA - UNITS 1 & 2 3/4 11-17

RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTES LIMITING CONDITION FOR OPERATION

-3.11.3 Radioactive wastes shall be solidified.or dewatered in accorcance with the PROCESS CONTROL PROGRAM to meet shipping and transportation reouirements 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 processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the Solid Radwaste System as necessary to pre-vent recurrence.

b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed naste in each container to ensure that it meets buria' ground and snioping requirements and take appropriate administrative action to prevent recurrence.

c. The provisions of Specification / 3.0.3 ar.d .0.d'are not acolicaole.

SURVEILLANCE REOUIREMENTS 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 CCNTRCL PROGRAM:

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIF: CATION of the baten under test snall be suspended until sucn time as acciticrai test specimens can be obtained, alternative SOLIDIFICATION carameters can be determined in accordance with the PROCESS CONTROL PRCGRAM.

and a suosequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PRCGRAM: '

o. If the initial test soecimen from a batch of waste faiIs to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM snall provide for the collection and testing of representative test specimens from eacn consecutive batch of the same type of wet waste until at least tnree consecutive initial test specimens demonstrate SOLICIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as recuired, as proviced in Specification 6.13, to assure SOLIDIFICATION of suosecuent Datches of waste; and

c. With the installed ecuicment incapable of meeting Soecification 3.11.3 or declared inoperable, restore the ecuioment to CPERABLE status or provice for contract cacability to process wastes as necessary to satisfy all apolicaole transportation and disposal recuirements.

C TaaEA - UNITS 1 & 2 3/4 11-13

1 f

i RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commit: rent to any MEf8ER 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 mrems to the wnole body or any organ, exceot the thyroid, which shall be limited to less than or equal to 75 mrems.

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 Specifi-cation 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a.,

or 3.11.2.3b., calculations shall be made including direct raciation contributions from the units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commiss. ion within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent

! releases to prevent recurrence of exceeding the above limits ano includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, snail

/

include an analysis that estimates the radiation exposure (dose) to L

a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including L

all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It snall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the 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 recuest for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance

! is granted until staff action on the request is complete. L r

j b. The provisions of Specification / 3.0.3 ud 3.0.1 are not acolicarle.

! SURVEILLANCE REQUIREMENTS

)

} 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents j shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and g

4.11.2.3, and in accordance with the methodology and parameters in the 00CM.

I 4.11.4.2 Cumulative dose contributions from direct radiation from the units

anc from radwaste storage tanks shall be determined in accordance with the j methodology and parameters in the 00CM. This requirement is acclicaole only i uncer conditions set forth in ACTION a. of Specification 3.11.4.

)f I

CATAWBA - UNITS 1 & 2 3/4 11-19 L - - - _ _ _ _ _ _ _ - - _

RADIOLOGICAL ENVIRONMENTAL MCNITORING LIMITING CONDITION FOR OPERAT!0N ACTION (Continued)

c. With milk or fresh leafy vegetable samples unavailable from one or.

more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add tnem within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table for the 00CM reflecting the new loca-tion (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

d. The provisions of Specification / 3.0.3 :nd 2.0.! are not applicable.

SURVEILLANCE RE0VIREMENTS a.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from tne specific locations given in tne taole and "

figure (s) in the 00CM, and shall be analyzed pursuant to the requirements cf Table 3.12-1 and the detection capaoilities required by Table 4.12*1.

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t CATAWBA - UNITS 1 & 2 3/4 12-2 L l

RADIOLCGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR 0,PERATION 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 One nearest milk animal, the nearest residence, and the neare:t garden

cf greater than 50 m (500 ft 2) 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 calculated in Specification 4.11.2.3, identify the new loca-tion (s) in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 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 excosure pathway) 20P. greater than at a location from which^samoles are currently ceing obtained in accordance with Specification 3.12.1, acc the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the 00CM. Th.e sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exoosure pathway, may be deleted from this monitoring program after October 31 of the year in whicn this Land Use Census was concucted. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table (s) for the OCCM reflecting the aew location (s), with information supoorting the cnange in the sr.mpling locations.

c. TheprovisionsofSpecificationl3.0.3and3.0.1 are not acclicaole.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the nighest pred'cted 0/Qs in lieu of the garden census. Speci-fications for broad leaf vegetation sampling in Table 3.12-1.4.c. shall be followed, including analysis of control samples.

CATA%BA - UNITS 1 & 2 3/4 12-13

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 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 approved oy 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 Specificationf 3.0.3 and 2.0.! are not applicable.

SURVEILLANCE RE0VIREMENTS 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 Interlacoratory Comparison Program shall be included in the Annual Radiological Environmental Ocerating Report pursuant to Specification 6.9.1.6.

CATAWBA - UNITS 1 & 2 3/4 12-15

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