Text

Proposed Tech Specs 3.0.4,4.0.3 & 4.0.4 Re Applicability
	ML20153F237
Person / Time
Site:	Hope Creek
Issue date:	04/28/1988
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20153F221	List: ML20153F216; ML20153F237;
References
	NUDOCS 8805100276
	Download: ML20153F237 (44)
	v • d • e

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l 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions 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 Operaticn is not met, except as provided j

in the associated ACTION requirements, within one hour action shall be initi-1 ated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

1.

At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

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

j 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 OPERATIONAL CONDITIONS 4 or 5.

Entry into/an l OPERATIONAL CONDITION or other specified condition shall when 3.0.4 not be made MwW4441 the conditions for the Limiting Condition for Operation are

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__ __ _ __..,_..___ _ _ _.___. - This provision shd11 not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual Specifications.

TNSERT

'A' 8805100276 880428 PDR P

ADOCK 05000354 DCD HOPE CREEK 3/4 0-1

APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance 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 i

INSERT

'B' INSERT ' C '

b.

The combined time interval for any 3 consecutive surveillance inter-vals shall not exceed 3.25 times the specified surveillance interval.

4.0.3 ailure to perform a Surveillance Requirement within the N l

interva hall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. N BffAW4P4hr%GMSt8titM2LeafMWA Surveillance requirements do not have to be N performed on inoperab'e equipment.

INSERT

'D' 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condi-tion shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.kWXXWXM INSERT

'E' 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:

a.

Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and 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) (1).

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testina activities reouired by the ASME Boiler and

^ie==mc Ve==el Cvde and epplic6ble Addenda shall be appliteMe as fo s in these Technical Specifications:

V y

ASME Boiler a ressure Vessel Required f encies MOVE THIS Code and applicab denda for rming inservice PORTION TO terminology for inserv ection and testing NEXT PAGE inspection and testing activi et activities Weekly t least once per 7 days Monthly A

st once per 31 days Quarterly or eve months At leas ce per 92 days Semiannuali every 6 months At least onc r 184 days 9 months At least once per days Yearly or annually At least once per 366 HOPE CREEK 3/4 0-2

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APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)

Pressure Vessel Code and applicable Addenda shall be applicable as 1

follows in these Technical Specifications:

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

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

d.

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

e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be con-j strued to supersede the requirements of any Technical Specification.

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INSERT FOR SPECIFICATION 3.0.4 INSERT

'A' not met and the associated ACTION requires a shutdown if they are not met within a specified time interval.

Entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the f acility for an unlimited period of time.

INSERTS FOR SPECIFICATION 4.0.3 INSERT

'B' allowed surveillance INSERT

'C'

, defined by Specification 4.0.2, INSERT

'D' 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 .

INSERT FOR SPECIFICATION 4.0.4 INSERT

'E' This provision shall not prevent passage i

through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

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3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance quirements within Section 3/4.

0.1 This specification states the applicability of each specific ion in term of defined OPERATIONAL CONDITION or other specified applicabil'ty condition nd is provided to delineate specifically when each specifi tion is applicable.

3.0.2 This ecification defines those conditions necess ry to constitute compliance with th terms of an individual Limiting Conditio for Operation i

and associated ACTIO requirement.

3.0.3 This specific ion delineates the measur to be taken for circum-l gg stances not directly provid for in the ACTION sta ments and whose occurrence would violate the intent of t specification.

F example, Specification 3.7.2

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N calls for two control room emer ncy filtration ubsystems to be OPERABLE and REP W E provides explicit ACTION requirem ts if one system is inoperable.

Under WITH the requirements of Specification 0.3, if oth of the required subsystems

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3 gg are inoperable, within one hour meas es m st be initiated to place the unit j

in at least STARTUP within the next 6 s, in at least HOT SHUTDOWN within WM the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . As P4WG a further example, Specification 3.6

.1 r quires two containment hydrogen re-combiner systems to be OPERABLE an provides explicit ACTION requirements if one recombiner system is inoperable.

nder the r uirements of Specification 3.0.3, if both of the required systems re inoperable, ithin one hour measures must be initiated to place the uni in at least START within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN wi in the following 6 ho s.

3.0.4 This specif~ cation provides that entry into n OPERATIONAL CONDITION must be made with (a) he full complement of required sys ms, equipment or components OPERABLE nd (b) all other parameters as specif in the Lidting Conditions for Op ation being met without regard for allowab e deviations and out of ser,vice ov'isions contained in the ACTION statements.

The int t of this provision is to ensure that unit operation s not initiated th either required equipment or systems inoperable or ot r limits being ex eded.

xceptions to this provision have been provided for a limited number f spe fications when startup with inoperable equipment would not affect plan s ety.

These exceptions are stated in the ACTION statements of the appropri te pecifications.

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l APPLICABILITY BASES 4.0.1 This specification provides that surveillance activities necessary ensure the Limiting Conditions for Operation are met and will be performe dur-the OPERATIONAL CONDITIONS or other conditions for which the Limiti Condi ns for Operation are applicable.

Provisions for additional sur 11ance activit es to be performed without regard to the applicable OPERATIO CONDI-TIONS or olher conditions are provided in the individual Surveilla e Require-mants.

Surve lance Requirements for Special Test Exceptions ne only be performed when e Special 7est Exception is being utilized a an exception to an individual spec ication, g

4.0.2 The provision of this specification pr de allowable tolerances for performing surveillance tivities beyond tho specified in the nominal AND surveillance interval.

These lerances are n ssary to provide operational E

flexibility because of schedulin nd perfor nce considerations.

The phrase M

'at least" associated with a survei ance equency does not negate this

/l TACHED allowable tolerance; instead, it perm 1 he more frequent performance of sur-T fwirgp veillance activities.

The tolerance values, taken ither indiv ually or consecutively over 3 test intervals, are sufficien '

restrictive to sure that the reliability associated with the surveil nce activity is not s nificantly degraded beyond that obtained from the n nal specified interval.

4.0.3 The p visions of this specification set forth t criteria for determination compliance with the OPERABILITY requirements o the Limiting Conditions f Operation.

Under this criteria, equipment, system or components are assum to be OPERABLE if the associated surveillance activities ave been satisfa orily performed within the specified time interval.

Nothing n this provi on is to be construed as defining equipment, systems or components OP BLE, when such items are found or known to be inoperable although stil eting the Surveillance Requirements.

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APPLICABILITY BASES

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N th a limiting Concitions for Operation have been performed within the specifi d 4.0.4 This specification ensures that surveillance activitie.s associated ti interval prior to entry into an applicable OPERATIONAL CONDITION or othe spec ied applicability condition.

The intent of this provision is to ensu e that s veillance activities have been satisfactorily demonstrated on a c rent basis as equired to meet the OPERABILITY requirements of the Limiting ndition for Operat n.

Under the erms of this specification, for example, during i tial plant startup or folio ng extended plant outage, the applicable surv llance activ-ities must be per ed within the stated surveillance interv prior to placing or returning the sys m or equipment into OPERABLE status.

4.0.5 This specifica ion ensures that inservice nspection o.f ASME Code Class 1, 2 and 3 components d inservice testing o ASME Code Class 1, 2 and 3 pumps and valves will be per rmed in accordanc with a periodically updated version of Section XI of the AS Boiler and Pr-sure Vessel Code and Addenda q

as required by 10 CFR 50, Section

.55a.

Re ef from any of the above require-g ments has been provided in writing b the C ission and is not a part of these AND Technical Specifications.

RWyb WE5 This specification includes a cl if ation of the frequencies of perform-ing the inservice inspecti'on and te ing ac 'vities required by Section XI of the ASME Boiler and Pressure Vess Code and licable Addenda.

This clarifi-cation is provided to ensure co istency in sur illance intervals throughoutl l

these Technical Specification and to remove any biguities relative to the '

frequencies for performing e required inservice i ection and testing actiy-ities.

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Under the terms this specification, the more rest etive requirementsl of the Technical Sp ifications take precedence over the AS Boiler and Pressure Vessel Code and licable Addenda.

For example, the require nts of Specifi-cation 4.0.4 to erform surveillance activities prior to entry to an OPERATIONAL CONDITION or her specified applicability condition takes preced ce over the ASME Boiler nd Pressure Vessel Code provision which allows p' imps t be tested up to one eek after return to normal operation.

And for example, th Technical Specifi ation definition of OPERABLE does not grant a grace period befo a

devic that is not capable of performing its specified function is declar ino erable*and takes precedence over the ASME Boiler and Pressure Vessel pr i-n which allows a valve to be incapable of performing its specified functio or up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

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3/4.0 APPLICABILITY BASES Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based cn the requirements for Limiting (Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36 c)(2):

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

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified conditions) conforvence to the Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION requirements. The first specifies the remedial measures that >ermit continued operation of the facility which is not further restricted by tie time limits of the ACTION requirements.

In this

ase, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits.

If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in an OPERATIONAL CONDITION or other specified condition in which the specification no longer applies.

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

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when HOPE CREEK B 3/4 0-1

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3/4.0 ApplICARILITY BASES K on't) equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable.

In this case, the time limits of the ACTION recuirements'would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

S)ecification 3.0.2 establishes that noncompliance with a specification exists w1en 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 purpore of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required den compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time Ifmits for placing the unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which pennits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or componts being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinete the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial m2asures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be tiaminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

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BASES (Con't)

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation.

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

However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would pennit a return to POWER operation, a penalty is rot incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

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

specification results in entry into an OPrAATIONAL CONDITION or condition of operation for another specification in which the recuirements of the Limiting Condition for Operation are not met.

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

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

Specification 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change.in CONDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPEP.ATIONAL C0hDITIONS.

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

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e 3/4.0 APPLICABILITY BASES (Con't)

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

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

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

Specification 4.0.1 establishes the requirement that surveillances must be perfomed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are perfomed to ve.-ify the J

operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be perfomed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Recuirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

Item a. pemits an 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., transient conditions or other ongoing surveillance or maintenance activities.

Item b.

limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being perfomed is the verification of conformance with the Surveillance Requirements.

These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perfom a Surveillance Requirement within the allowed surveillance interval, defined by ';he provisions of Specification 4.0.2, as a condition that constitutes a failure HOPE CREEK B 3/4 0-4

3/4.0 APPLICABILITY BASES (Con't) to meet the OPERABILITY reovirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been perfonned and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have perfonned the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a limiting Condition for Operation that is subject to enforcement 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 requirements 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 requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to 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 pemit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perfom the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is teminated.

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

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

HOPE CREEK B 3/4 0- 5

3/4.0 APPLICABILITY BASES (Con't)

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component 0PERABIL!TY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systers and components ensure safe operation of the facility.

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

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

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

Specification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Roiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by.the Commission.

This specification includes a clarif t ati?n of the frequencies for performing the inservice inspection and testiak actisities required by Section XI of the ASME Boiler and Pressure Vessel Code and applisc51e Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Ilnder the term: of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to i

one week after return to normal' operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which e

is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Yessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable, ROPE CREEK B 3/4 0-6 4

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j REACTIVITY CONTROL SYSTEMS 3/4.1.4 CONTROL ROD PROGRAM CONTROLS R0D WORTH MINIMIZER LIMITING CONDITION FOR OPERATION 3.1.4.1 The rod worth minimizer (RWM) shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*#, when THERMAL POWER is less than or equal to 20% of RATED THERHAL POWER, the minimum allowable low power setpoint.

ACTION:

a.

With the RWM inoperable, verify control rod movement and compliance with the prescribed control rod pattern by a second licensed operator or other technicclly qualified member of the unit technical staff who is present at the reactor control console.

Otherwise, control rod movement may be only by actuating the manual scram or placing the reactor mode switch in the Shutdown position.

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SURVEILLANCE REQUIREMENTS 4.1.4.1 The RWM shall be demonstrated OPERABLE:

a.

In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods for the purpose of making the reactor critical, and in OPERATIONAL CONDITION 1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to RWM automatic initia-tion when reducing THERMAL POWER, by verifying proper indication of the selection error of at least one out-of-sequence control rod.

b.

In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods for the purpose of making the reactor critical, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod, c.

In OPERATIONAL CO.NDITION 1 within one hour after RWM automatic initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

d.

By verifying that the control rod patterns and sequence input to the RWH computer are correctly loaded following any loading of the program into the computer.

Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

See Special Test Exception 3.10.2.

HOPE CREEK 3/4 1-16

o TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

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

a.

With one channel inoperable, place the i operable channel in the tripped condition within one hou or declare the associated system inoperable.

b.

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

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ECCS inoperable.

ACTION 32 -

With the number of OPERABLE channels less than required by the

.t nimum 9PERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 33 -

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

ACTION 34 -

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

a.

For one channel inoperable, place the inoperable channel in the tripped condition within 1 houf:9or declare the HPCI system inoperable.

y b.

With more than one channel inoperable, declare the HPCI system inoperable.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hou or declare the HPCI system inoperable.

ACTION 36 -

With the number of OPERABLE channels one less than the Total NumberofChannels,placg'theinoperablechannelinthetripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , operation may then continue until performance of the nex required CHANNEL FUNCTIONAL TEST.

ACITON 37 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function requirement, open the minimum flow bypass valve within one hour.

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

^The-provhions-of:Specifi c ation=3dL-4-Are:mt-apellc ablea HOPE CREEK 3/4 3-35

1 TABLE 3.3.6-1 (Continued) i CONTROL ROD BLOCK INSTRUMENTATION ACTION Declare the RBM inoperable and take the ACTION required by ACTION 60 Specification 3.1.4.3.

With the number of OPERABLE Channels:

ACTION 61 f

a.

One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable l

channel to OPERABLE status within 7 days or place the i

inoperable channel in the tripped condition within the next hour.

b.

Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within i

one hour.

l

-Tha

._lm I.....

.,f 0.,_

l f i.. :

...O

^2 _._... i

2..r.1

c;h l With the number of OPERABLE channels less than required by the ACTION 62 Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

=T4prov i siund--vi-5pec4f4caC-h0-4 m M 6S.41- --

l l

With the number of OPERABLE channels less than required by the i

ACTION 63 Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

NOTES 1

With THERMAL POWER > 30% of RATED THERMAL POWER.

~

(

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

a.

The RBM shall be automatically bypassed when a peripheral control rod is selected.

l b.

This function shall be automatically bypassed if detector count rate is

> 100 cps or the IRM channels are on range 3 or higher.

c.

This' function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.

d.

This function shall be automatically bypassed when the IRH channels are on range 3 or higher.

e.

This function shall be automatically bypassed when the IRM channels are on range 1.

l HOPE CREEK 3/4 3-58

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

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 OPERABLE status.

b.

The provisions of Specificatio if 3.0.3 nd 3.:

are not applicable.

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

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved frou actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety, i

HOPE CREEK 3/4 3-68

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICADILITY:

At all times.

ACTION:

a.

With one or more of the required meteorological monitoring instrumen-tation channels inoperable for more than 7 days, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status.

b.

The provisions of Specificatio

3. 0. 3 -=::-j 3; 0.4:are not applicable.

i SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation l

channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

HOPE CREEK 3/4 3-71

m..-...

...p

..x-

. w.r:

c-m -

-- -- ' ' " ' - " ~

l t

1 Table 3.3. 7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 --

t i

With the number of OPERA 3LE accident monitoring instrumentation a.

i channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least NOT SHUTDOWN within the next l

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

t b.

With the number of OPERA 8LE accident monitoring instrumentation i

channels less than the Minimum Channels OPERA 8LE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE i

status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT $HUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SMUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

i ACTION 81 -

With the number of OPERA 8LE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

Initiate the preplanned alternate method of monitoring the a.

appropriate parameter (s), and l

b.

Prepare and submit a Special Report to the Commission pursuant to j

Specification 6.9.2 within 14 days following the event outlining the action taken, the cause er the inoperability and the plans and schedule for restoring the system to OPERA 8LE status.

=T he9tovisions=of=$pecif4 set ten =3#4r4=ere- = ; c;; Heat),w ACTION 82 -

With the number of OPERA 8LE accident monitoring instrumentation a.

channels less than the Required Number of Channels shown in Table 3.3.7.5-1, verify the valve (s) position by use of alternate indica-tion methods; restore the inoperable channel (s) to 0PERA8LE status within 30 days or.be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With the number of OPERA 8LE accident monitoring instrumentation channels less than the Minimum Channels OPERA 8LE requirements of

. Table 3.3.7.5-1, verify the valve (s) position by use of alternate I

indication methods; restore the inoperable chan9el(s) to OPERABLE i

status within 7 days or be in at least NOT SHUYDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 l

HOPE CREEK 3/4 3 86

INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7.

The traversing in-core probe system shall be OPERABLE with:

Five movable detectors, drives and readout aquipment to map the core, a.

&nd b.

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

APPLICABILITY:

When the traversing in-core probe is used for:

a.

Recalibration of the LPRM detectors, and b.*

Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

ACTION:

With the traversing in-core probe system inoperable, suspend use of the system for the above applicable monitoring or calibration functions. The provisions of Specificatio 3.0.3

..J 3.^.^:are not applicable.

SURVE7U 'wCE REQtyREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use for the LPRM calibration function.

l

'l "Only the detector (s) in the required measurement location (s) are required to be OPERABLE.

HOPE CREEK 3/4 3-89

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.9 The loose part detection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission 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. ass =3seus:.are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a:

a.

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

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

CHANNEL CALIBRATION at least once per 18 months.

l HOPE CREEK 3/4 3-90

\\

1

~

t INSTRUMENTATION l

l RA010 ACTIVE L10V!0 EFFLUENT MONITORING INSTRUMENTATION i

LlHITING CON 0! TION FOR OPERATION l

i

\\

3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure tnat 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).

APPLICABillTY: At all times.

ACTION:

i With a radioactive liquid effluent monitoring instrumentation channel a.

Alarm / Trip Setpoint 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, or change the setpoint so it is acceptably conservative.

)

b.

With less than the minimum. number of' radioactive liquid effluent l

monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3.7.10-1.

Exert best efforts to return the i'nstruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Spec-ification 6.9.1.7 why this inoperability was not corrected in a timely i

i manner.

The provisions of Specification ()3.0.3 =-j 1 c.

a are not applicable.

l Y

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.10-1.

l i

l HOPE CREEK 3/4 3-91 4

i

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous ef fluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERA 6LE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.6 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 00CH.

APPLICABILITY:

As shown in Table 3.3.7.11-1.

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, or change the setpoint so it is acceptably.

conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE,.take the ACTION shown in Table 3.3.7.11-1.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant i

to Specification 6.9.1.7 why this inoperability was not corrected rn a timely manner.

TheprovisionsofSpecification$3.0.31.

2.^.? are not applicable.

l c.

t i

SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.11-1.

l HOPE CREEK 3/4 3-96

1 INSTRUMENTATION 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM I

LIMITING CONDITION FOR OPERATION 3.3.8 At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With one turbine control valve, or one main stop valve per high pressure turbine steam lead inoperable and/or with one combined intermediate valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or close at least one valve in the affected steam lead (s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the above required turbine overspeed protection system otherwise i

inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

c.

The prisions=o'-5eificedon=M-h e x t-:;; H r m.

SURy}ILLANCEREQUIREMENTS 4.3.8.1 The provisions of Specification 4.0.4 are not applicable.

4.3.8.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Cycling each of the following valves through at least one complete cycle from the running position:

a)

For the overspeed protection control system; 1)

Six low pressure combined intermediate valves b)

For the electrical overspeed trip system and the mechanical overspeed trip system; 1)

Four high pressure main stop valves, and 2)

Six low pressure combined intermediate valves.

HOPE CREEK 3/4 3-103 i

I REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY:

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

ACTION:

a.

With the structural integ?ity 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 4,

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.

24.

T he=provi sions=ofdpecif4 cat 4ca-Sid7rs=notmappMcabk---

SURVEILLANCE REQUIREMENTS

-f 4.4.8 No requirements ot.her than Specification 4.0.5.

1 4

HOPE CREEK 3/4 4-27

REACTOR COOLANT SYSTEM COLO SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'##

with each loop consisting of:

a.

One OPERABLE RHR pump, and b.

One OPERABLE RHR heat exchanger.

l APPLICABILITY:

OPERATIONAL C0hDITION 4 and heat losses to ambient ** are not I

sufficient to maintain OPERATIONAL CONDITION 4.

ACTION:

l With less than the above required RHR shutdown cooling mode loops OPERABLE, a.

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

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

The= provisions =ofdM fication=hb4-we est 5ppMceWo;==-

=G SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system, recirculation pump or alternate method shall be determined to be in i

operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation or at least one recirculation pump is in operation.

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

(

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

hydrostatic testing.

l I

- Ambient losses must be such that no increase in reactor vessel water temper-ature will occur (even though COLD SHUTDOWN conditions are being maintained).

HOPE CREEK 3/4 4-29

PLANT SYSTEMS 3/4.7.6 SEALE0SOURCECONTAMINAT!g LIMITING C0hDITION FOR OPERATION 3.7.6 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 microcuries of removable contamination.

APPLICABILITY:

At all times.

ACTION:

a.

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

1.

Decontaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

b.

The provisions of Specificatio 3.0.3 ;;:e 3.0.t are not applicable.

e SURVEILLANCE REQUIREMEN_TS 4.7.6.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

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

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

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

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

1.

With a balf-life greater than 30 days, excluding Hydrogen 3, and 2.

In any form other than gas.

HOPE CREEK 3/4 7-19

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with each loop consisting of:

a.

One OPERABLE RHR pump, and b.

One OPiRABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less than 22 feet 2 inches above the top of the reactor pressure vessel flange and heat losses to ambient ** are not sufficient to maintain OPERATIONAL CONDITION 5.

ACTION:

a.

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

b.

With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour, u- -The=previsions=of= Specification =k0Ar,-

b.,4Aicabter=-

SURVEILLANCE REQUIREMENTS 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period.

- Ambient losses must be such that no increase in reactor vessel water temper-ature will occur (even though REFUELING conditions are being maintained).

HOPE CREEK 3/4 9-18

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1-1) shall be limited:

a.

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

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

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeoing any of the above limits, prepare and j

submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defiries 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.

The provisions of Specificatio

.0.3 -and=S-Or* 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 ODCM at least once per 31 days.

4 l

l HOPE CREEK 3/4 11-5

j i

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION I

1 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce the radioactive materials in

)

liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see i

Figure 5.1.1-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day period.

APPLICABILITY:

At all times.

ACTION:

a.

With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the 4

following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-systems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

The provisions of Specificatio 3.0.3-a.d-Ler4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

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HOPE CREEK 3/4 11-6

RADIOACTIVE EFFLUENTS LIQUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside traporary tank shall be limited to less than or equal to 10 curies, excluding taitium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

4 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 Specification 6.9.1.7.

b.

The provisions of Specificatio 3.0.3 ees-are,4 rare 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-l active materials are being added to the tank.

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l HOPE CREEK 3/4 11-7

RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION

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3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure E.1.1-1) 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 noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report 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.

The provisions of Specificatio % 3.0.3.ee 3,^.4:are not applicable.

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

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l HOPE CREEK 3/4 11-12

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RADIOACTIVE EFFLUENTS DOSE - 100lNF-131, IODINE-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEM8ER 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 reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ and, b.

During any calendar year:

Less than or equal to 15 mrems to any organ.

APPLICA8ILITY:

At all times.

ACTION:

With the calculated dose from the release of iodine-131, iodine-133, a.

tritium, and radionuclides in particulate form with half lives greater than 8 days, 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 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.

The provisions of Specificatio 3.0.3 and=hb4 are not applicable.

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

HOPE CREEK 3/4 11-13

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O RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

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

ACTION:

a.

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

1.

Identification of the inoperable equipment or subsystems and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

b.

The provisions of Specificatio > 3.0.31wed aree4 = are not applicable.

SURVEILLANCE REQUIREMENTS l

4.11.2.4 The readings of the relevant instruments shall be checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the main condenser air ejector is in use to ensure that the 1

gaseous radwaste treatment system is functioning.

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HOPE CREEK 3/4 11-14

o RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM for the Reactor Building and the Service and Radwaste Building shall be OPERABLE and appropriate por-tions of this system shall be used to reduce release of radioactivity when the projected doses in 31 days due to gaseous effluent releases from each unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) 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 MEMBER OF THE PUBLIC APPLICABILITY:

At all times.

ACTION:

a.

With radioactive ventilation exhaust being discharged without treat-ment and in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

1.

Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

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

The provisions of Specificatio 3.0.3 :nd-0.^-4 are not applicable.

SURVEILLANCE REQUIREMENTS.

t 4.11.2.5.1 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 the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.

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

HOPE CREEK 3/4 11-15

RADIOACTIVE' EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABILITY:

At all times.

ACTION:

a.

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

With continuous monitors inoperable, operation of the main condenser offgas treatment system may continue for up to Su days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , The provisions of SpecificatiorQ 3.0.3 ud 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously moni-toring the waste gases in the main condenser offgas treatment system whenever the main condenser evacuation system is in operation with the hydrogen monitors required OPERABLE by Table 3.3.7.11-1 of Specification 3.3.7.11.

HOPE CREEK 3/4 11-16

n RADIOACTIVE EFFLUENTS VENTING OR PURGING LIMITING CONDITION FOR OPERATION 4

3.11.2.8 VENTING or PURGING of the Mark I containment drywell shall be through either the reactor building ventilation system or the filtration, recirculation and ventilation system.

APPLICABILITY: Whenever the containment is vented or purged.

ACTION:

i a.

With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.

b.

The provisions of Specifications 3.0.3 = = 3.G.2 are not applicable.

b I

SURVEILLANCE REQUIREMENTS l

4.11.2.8 The containment shall be determined to be aligned for VENTING or PURGING through either the reactor building ventilation system or the filtration, recirculation and ventilation system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at-least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the drywell.

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l HOPE CREEK 3/4 11-18

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

APPLICABILITY:

At all times.

ACTION:

a.

With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately 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 accorciance with the PROCESS CONTROL PROGRAM, (1) demonstrate by test or analysis that the improperly processed waste in each container meets the requirements for transportation to the disposal site and for receipt at the disposal site and (2) take appropriate administrative action to prevent recurrence.

c.

The provisions of Specificatio 3.0.3 m a,& are not applicable, l

SURVEILLANCE REQUIREMENTS 4.11.3.1 The PROCESS CONTROL PROGRAM shall be followed to verify that the pro-perties of the packaged waste meet the minimum stability requirements of 10 CFR i

Part 61 and other requirements for transportation to the disposal site and re-ceipt at the disposal site.

4.11.3.2 The PROCESS CONTROL PROGRAM shall include sufficient quality control and assurance methods to assure the solidified waste product from any process (either in-house or contracted vnndor) meets the requirements for transporta-tion and receipt at the di'sposal site.

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I HOPE CREEK 3/4 11-19

,o RADI0 ACTIVE EFFLUENTS 3/4.1T 4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except 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 should be made including direct radiation contributions from the units including outside storage tanks, etc.

to determine whether the above limits of Specification 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Com-mission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce sub-sequent releases to prevent recurrence of exceeding the above limits ar.d includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 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 de-scribe 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 request for a vari-1 ance 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.

The provisions of Specificatio 5 3.0.3 inns-i.srs-are not applicable.

1 b.

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SURVEILLANCE REQUIREMENTS l

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

4.11.4.2 Cumulative dose contributions from direct radiation from the units including outside storage tanks, etc. shall be determined in accordance with the methodology and parameters in the ODCM.

This requirement is applicable only under conditions set forth in Specification 3.11.4, ACTION a.

j HOPE CREEK 3/4 11-20

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RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued)

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specifica-tion 6.9.1.8, 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 pursuant to Speci-fication 6.9.1.8 and also include in the report a revised figure (s) and table for the CDCM reflecting the new location (s).

1 d.

The provisions of Specifications 3.0.3:st;d 5.0.i=are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

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HOPE CREEK 3/4 12-2

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LANO 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 meteoroTogical sectors of the nearest milk animal, the nearest residence and the nearest 2

2 garden

of greater than 50 m (500 ft ) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) that yields a calcu-lated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, 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) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

Pursuant to Specification 6.9.1.8, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s).

c.

The provisions of Specification) 3.0.3 W =6re,4-are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.

The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

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 0/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12.1-1, Part 4.c., shall be followed, including analysis of control samples.

HOPE CREEK 3/4 12-13

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supp' lied as part of an Interlaboratory Comparison Program that has been approved by the l

Commission.

l APPLICABILITY:

At.all times.

ACTION:

l a.

With analyses not being performed as required above, report the l

corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report purcuant I

I to Specification 6.9.1.6.

l b.

The provisions of Specificatio 3.0.3 and=&eSr4=are not applicable.

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SURVEILLANCE REQUIREMENTS 4

l 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 Inter t

laboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specifi:ation 6.9.1.6.

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HOPE CREEK 3/4 12-14 l

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ML20153F237

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