Text

Proposed Changes to Tech Spec Sections 3.0.4,4.0.3 & 4.0.4 Re Applicability of Limiting Conditions for Operation & Surveillance Requirements
	ML20234E754
Person / Time
Site:	Perry
Issue date:	09/17/1987
From:	; CLEVELAND ELECTRIC ILLUMINATING CO.
To:	;
Shared Package
ML20234E694	List: ML20234E754; PY-CEI-NRR-0720, Application for Amend to License NPF-58,changing Tech Specs 3.0.4,4.0.3 & 4.0.4 & Bases for Tech Specs 3.0 & 4.0,per Guidance Provided by Generic Ltr 87-09.Fee Paid;
References
	NUDOCS 8709220505
	Download: ML20234E754 (40)
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3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in hI tucceeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the a

Limiting Conditions for Operation, the associated ACTION requirements shall be me t.

3. 0. 2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTI0t, 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, completinn of the Action requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does

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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 SHUTOOWN 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 .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accorcance 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.

3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are-not met within a specified time interval.

Entry into an OPERATIONAL CONDITION or othar specified condition may be made in accordance with the ACTION requirements l

vhen conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through r o

to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual Specifications.

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APPLICABILITY I.

SURVEILLANCE REQUIREMENTS

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i t-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 maximum allowable extension not to exceed 25% of the surveillance a.

interval, but b.

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

4.0.3 Failure to perform a Surveillance Requirement within the alloved surveillance interval, defined by Specification 4.0.2. shall constitute i

noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicabl..

at the time it is identified that a Surveillance Requirement has nnr b-cu 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 allovable cutage t.ime limits of the ACTION requirements are less than 24 houts.

Sur"eillanca Requirements do not have to be performed on inoperable equipment.

l 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applienbla condition shall not be made unless the Surveillance Requirement (s)) assne lared with the Limiting Condition for Operation have been performed wi thin tha applicable surveillance interval or as otherwise specified.

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

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

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Inservice inspection of ASME Code Class 1, 2, and 3 components and a

inservice testing of ASME Code Class 1, 2, and 3 pumps and valves r

shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and appifcable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has i

been granted by the Commission pursuant to 10'CFR 50, Section 50.55a(g)

(6) (1).

b.

Surveillance intervals specified in Section XI of t'he ASME Boiler and Pressure Vnssel 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 Technical Specifications:

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APPLICABILITY j

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SURVEILLANCE RE0VIREMENTS (Continued)

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice i

terminology for inservice insoection and testing activities inspection and testing 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

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Semiannually or every 6 months At least once per 184 days Every 9 months Yearly or annually At least once per 276 days At least once per 366 da,ys l

The provisions of Specification 4.0.2 are applicable to the above c.

1 required frequencies for performing inservice inspection and testing activities.

d.

shall be in addition to other specified Surveillance Re Nothing in the ASME Boiler and Pressure Vessel Code shall be construed e.

to supersede the requirements of any Technical Specification j

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES' Specifications 3.0.1 through 3.0.4 establish the general requirements applicable l

to Limiting Condition for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):

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

i Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or'other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The 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 j

lieu of other alternatives that would not result in redundant systems or components being inoperable.

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

In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation rust be met.

This time limit is the allovable outage time to restore an inoperable system or component to OPERABLE status or for restoring I

parameters within specified limits. If these actions are not completed within j

the allowable outage time limits, a shutdown is required to place the facility

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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

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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 or operational problems.

Individual specifications may include

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a specified time limit for the completion of a Surveillance Requirement when 4

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i 3/4.0 APPLICABILITY BASES (Con't) equipment is removed from service.

In this case, the allowable outage time j

limits of the ACTION requirements are applicable when this limit expires if 1

the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL s

CONDITION in which a new specification becomes applicable.

In this case, the time limits of the ACTION requirements vould apply from the point in time that the new specification becomes applicable if the requirements of the Lir: sing Condition for Operation are not met.

Specification 3.0.2 establishes that noncompliance with a specification exits vhen 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. Tne purpose of this specification is to clarify that (1) implementation of the ACTION requirement within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance vith a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdovn 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 i

purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that vould not result in redundant systems or components 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 coordinate the reduction in j

electrical generation with the load dispatcher to ensure the stability and j

l availability of the electrical grid. The time limits specified to reach lover l

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 i

challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdovn 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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3/4.0 APPLICABILITY 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 SHUTD0VN when a shutdown is required during POVER operation.

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

However, if a lover CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOVN, or other OPERATIONAL CONDITION, is not l

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

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reach HOT SHUTD0VN 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 SHUTD0VN is not reduced from the allovable 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 vould permit a return to POWER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

Thesameprine[pleapplieswithregardtotheallovableoutagetimelimitsof the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL CONDITION or condition of operation for another specification in which the requireme. ts of the Limiting Condition for Operation are not met.

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

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

d Specification 3.0.4 establishes limitations on a change in OPERATIONAL j

CONDITIONS when a Limiting Conditior for Operation is not met.

In precludes j

placing the facility in a higher CONDITION of operation when the requirements q

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 vere permitted. The purpose of this 3

specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered vben corrective action is being taken to obtain compliance with a specification by restoring equipment to l

OPERABLE status or parameters to specified limits. Compliance with ACTION l

requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL l

CONDITION or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification l

should not, however, be interpreted as endorsing the failure to exercise good f

practice in restoring systems or components to OPERABLE status before plant startup.

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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 lover CONDITION of operation.

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

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

Specification 4.0.1 establishes the requirement that surveillance must be performed during the OPERATIONAL CONDITIONS or other conditions for which the l

requirements of the Limiting Conditions for Operation apply unless othervise i

stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillance are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safety operation of the facility when the plant is in j

an OPERATIONAL CONDITION or other specified condition for which the individual 1

l Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated..miting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allovable 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. permits an allovable extension of tra normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These 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 that the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, is a condition that constitutes a failure to meet the PERRY - UNIT 1 B 3/4 0-4

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3/4.0 APPLICABILITY BASES (Con't)

OPERABILITY requirements for a Limiting Condition for Operation.

Under the i

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 performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allovable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2.,

constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation and any reports required by 10 CFR 50.73 shall be determined based on the length of time the surveillance interval has been exceeded, and the corresponding Limiting Conditions for Operation ACTION time requirements, as discussed in NUREG 1022, Supplement 1.

I If the allovable outage time limits of the ACTION requirements are less than 24 I

hours or a shutdown is required a comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures vould be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that becomes 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 allovance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

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

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

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i 3/4.0 APPLICABILITY BASES (Con't)

Specification 4.0.4 establishes the requirement that all applicable surveillance must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a.n OPERATIONAL l

CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable surveillance Requirements must be performed within the specified surve11Llance 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 i

of Specification 4.0.4 do not apply because this vould delay placing the facility in a lover 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

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periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided ir. vriting by the Commission.

This specification includes a clarification of the frequencies for performing

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

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

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i l TABLE 3.3.2-1 (Continued)'

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ISOLATION ACTUATION INSTRUMENTATION i

ACTION.

ACTION 20 '-

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

ACTION 21' -

Close the~ affected system isolation valve (s) within one hour or:

In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT a.

SHUTDOWN within.the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24. hours.

b.

In Operational Condition.", suspend CORE ALTERATIONS, handling of irradiated fuel in the' primary containment and operations with a potentia 1'for draining the reactor vessel.

i ACTION 22 Restore the manual initiation function to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or:

In OPERATIONAL' CONDITION 1, 2, or 3, be in at least HOT a.

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN

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i within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l b.

In OPERATIONAL CONDITION *, suspend CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling of irradiated fuel in the primary containment.

ACTION 23 Be in at least STARTUP with the associated isolation valves-

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closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT SHUTDOWN within I

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

ACTION 24 Be in at least STARTUP within 6 haurs.

ACTION 25 Verify SECONDARY CONTAINMENT INTEGRITY with the annulus exhaust gas treatment system operating within one hour.<NL j

ACTION 26 '-

Restore the manual initiation. function to OPERABLE status 1

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system 1, solation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and declare the affected system inoperable. #.

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j ACTION 27 Close the affected system isolation valves within one hour and declare the affected system inoperable. M l

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ACTION 28 Within one hour lock the affected system isolation valves closed, or verify, by remote indication, that the valve (s)'is closed and electrically disarmed, or isolate the penetration (s) and declare the affected system inoperable.

NOTES When handling irradiated fuel in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When any turbine.stop valve is greater than 90% open and/or the key locked Condenser Low Vacuum Bypass Switch is in the normal position.

During CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The e;..ht.. ef Op;;tfinth;; 2.0.1 ; ; ::t ;;1fid10.

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L TABLE 3.3.3-l'(Continued)

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EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION f

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_ inoperable channel in the tripped condition within one hourd or declare the l'i associated system inoperable.

b.

With more than one channel inoperable, declare the associated l

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 A05 trip system or ECCS inoperable.

' ACTION 32 -

With-the number of OPERABLE. channels less'than the Minimum OPERABLE 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 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months or declare tne associated ADS valve or ECCS inoperable.

ACTION.34.-'

With the number of OPERAELE channels less than recuired cy.the Minimum OPERABLE Channels per Trip Function requirement:

'For one trip system, place.that trip system in the tripced a.

conditionwithinonehour/ordeclaretheHPCSsystemincoeracle.l'-

E b.

For both ttfp' systems, declare the HPCS 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 hour, or altgn the HPCS system to'take suction from the l'

d suppression pool 7, or declare the HPCS system inoperable.

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ACTION 36 With the number of OPERABLE channels 1 css than required by the Minimum OPERABLE Channels per Trip Function requirement, place' at least one inoperable channel in the tripped condition within-one hour / or declare the HPCS system inoperable.

ACTION 37 -

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

ACTION 38 -

With the number of OPERABLE channels less than the Total Number

'tionwithin1 hour /;heinoperablechannelinthetrippedcondi-of Channels, place t operation may then continue until perform-ance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 39 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

Restore the inoperable channel to OPERABLE. status within 7 days i

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TAB E 3.3.5-1 (continued) ppy REACTOR CORE ISOLATION COOLING SYSTEM l'

e4 ACTUATION IN5TRUMENTATION ACTION 50 --

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

1 a..

For one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within one hou /

or declare the RCIC system inoperable.

b. ' For both trip systems, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement, declare the RCIC system inoperable.

ACTION 52 -

With the number of OPERABLE channels less than required by the

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Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within one boun#, or aliAn the RCIC system to take suction from the suppression poo'F, or declare the RCIC system inoperacle.

ACTION 53 --

Witn the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System 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 RCIC system inoceracle.

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INSTRUMENTATION g.

SEISfGC MONITORING INSTRUMENTATION l

LIMIT!NG CON:I~:CN FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERAELE.

APPLICABILITY:

At all times.

ACTION:

5 a.

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

is b.

Tne crovisions of Specificatiory'3.0.3 :n: :. -:

not applicaole.

SURVEILLANCE RECUI EVENTS

.('

4.3.7.2.1 Eacn of tne above required seismic monitoring instruments shall be demonstrated OPERASLE 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 sctuated during a seismic event greater than or equal to 0.05g 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 30 days following the seismic event.

Data snall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground i

motion.

A Special Report shall be prepared and submitted to the Commission a

pursuant to Specification 6.9.2 within 10 days describing the magnitude, fre -

quency spectrum and resultant effect upon unit features important to safety.

b.e PERRY - UNIT 1 3/4 3-67

p.:l p

.J l

INSTRUME NTAT

0.'. -

W.p

' METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CON 0!TICH FOR'0PERATION L

.3.3.7.3'.The meteorological monitoring instrumentation shown in Table 3.3.7.3-1 shall be OPERAELE.'

L APPLICABILITY: At all times.

s I'

ACTION:

' With one or more of.the above recuired_ meteorological monitoring

- a.

instruments inocerable 'for more than 7 days, prepare and suomit 'a

Special Report to the Commission pursuant to Specification 6.9.2

.witnin the next 10 days outlining the'cause of the malfunction and the plans for restoring.tne instrumentation to CPERAELE status.

is Tne p' ovisions of Specification /'3.0.3 :-i 2. :

b.

r

:: not acclicaole.

(:

' SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of.the above required meteorological monitoring instruments 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.

t 5

5 (50 l

. PERRY - UNIT 1 3/4 3-70

!f L8 Table'3.3.7.5 *

(Continuec)

~

ACCIDENT MONITORING INSTRUMENTATIONS ACTION STATEMENTS i

l ACTION 80 -

With the number of OPERABLE accident monitoring instrumentation a.

channels less than the Required Numcer of Channels shown in Table 3.3.7.5-1, restore the inoperacle channel (s) to OPERABLE status within 7' days or be in at least HOT SHUT 00WN within tne next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ar.d in COLD SHUTDCWN within the following.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

j.

b.

i With the number of OPERABLE accident monitoring instrumentation j.

channels less than the Minimum Channels OPERABLE re Table 3.3.7.5-1, restore'the inoperable channel (s) quirements of to OPERAELE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTOCWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN witn the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The provisiens of Specification 3.0.4 are not acclicsole.

c.

ACTICN 31 -

Vitn the numcer of CPERAELE Channels less taan required by tne Minimum Channels CFERAELE re uirement, eitner restore One inc;eracle Channel (s) to C75RA3LE s atus wi nin 72 nours, or:

Initiata ne pre?lannec al ernate cetnoc of monitoring the a.

appropriate parameter (s), anc b.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining tne action taken, the cause of the inoperability and the plans and senedule for restoring the system to OPERABLE status.

~'

r:xt:i:n: :f :;::f'fe: f:r 2.0. ' :r: net 1;;'dcebte ACTION 82 -

1 With the number of OPERABLE accident monitoring instrumentation a.

channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, verify the valve (s) position by use of alter-nate indication methods; restore the inoperable channel (s) to OPERABLE status at the next time the valve is required to be demonstrated OPERA 8LE pursuant to Specification 4.0.5.

+;

'5: ;r:.ici:n: ;f Sp :ifi;;ti:n 2.0. P:rr ::t :;; f::b':_s, i

e 9

PERRY - UNIT 1 3/4 3-79 e

m i4 i

1, t

j

.i L.

INSTRUMEN ATIS

I

. TRAVERSING IN-CORE PROBE SYSTEM-1 i

LIMITING CON 0! TION FOR OPERATICN 3.3.7.7.

The'_ traversing in core probe system shall.be OPERA 8LE with:

a.

Five movable detectors,. drives and readout equipment to map'the core,

.and b.

Indexing equipment to allow all five detectors.to be calibrated in f

a common location.

I APPLICABILITY:

When the traversing in-core probe is used for:

a.

-Recalibration of the LPRM detectors, and b."

Monitering the APLHGR, LHGR, MCPR, or MFLPD.

ACTICN:

'With the traversing in-core pre:e system inoceracle, do not use the system for tne a: eve acplica:1e monitoring or calibration functions. Tne provisions of i

E :e:ification/ 3.0.3

1,'

.. not applicaole.

j

.\\

ts SURVEILLANCE REQUIREMENTS

.i 4

4.3.7,7 The traversing-in-core probe system shall be demonstrated OPERABLE by normalizing each of the above reouired detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use when required for the LPRM calibration function.

)

i "Uniy tne cetector(s) in the location (s) of interest are required to be OPERABLE.

- (M,

\\

u.~

l PERRY - UNIT 1 3/4 3-82

d 4

l INSTRUv! nth!ON LOOSE-PART DETECTION SYSTEM

.]

a

~

5 LIMITING ~ CON 0! TION FOR 00ERATION 3.3.7.8 The. loose part detection system shall'be OPERABLE.

' APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

l ACTION:

i a.

With one or more loose-part detection system channels. inoperable for.

more than 30; days,' prepare and submit a Special Report to the Com-i mission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring 1

One enannel(s) to OPERABLE status.

l is b.

Tne crovisions of Specification / 3.0.3 a.; :.: ':: not applicaele.

SURVEILLANCE REQUIREMENTS 1

k i

4.3.7.5 Each channel of the loose part detection system shall be demonstrated 0FERAELE 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

~

CHANNEL CALIBRATION at least once'per 18 months.

c.

i I

lh

. PERRY - UNIT 1 3/4 3-83 1

1+

(c

~

n 3

INSTRUMENTATION e hjiF RADIOACTIVE:LIOUID EFFLUENT MONITORING INSTRUMENTATION

. LIMITING CONDITION FOR OPERATION 3.3;7.9 L The radioactive liquid effluent monitoring instrumentation channels y

shown in Table 3.3.7.9-1 shal1 be OPERABLE with their alarm / trip setpoints 1

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 OFFSITE DOSE CALCULATION MANUAL (00CM).

' APPLICABILITY:

At all times.

i 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 ' radioactive liquid 4

effluents monitored by the affected enannel or declare the channel inoperable, or'cnanga the setpoint so it' is acceptacly conservative, b.

With less than the minimum number of : radioactive liquid effluent.

monitoring instrumentation channels OPERABLE, take the ACTION shown.

in Table 3.3.7.9-1.

Restore the inoperable. instrumentation to

-(.

.0PERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Semiannual Radioactive Effluent Release Report.

The provisions of Specification / 3.0.3 x 2 b.:r: not applicable.

c.'

SURVEILLANCE RE0VIREMENTS-i 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE 3

CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.

k i

I $

PERRY - UNIT 1 3/4 3-84

I E

i J@

1 INSTRUMENTATION x-RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.10 The radioactive gaseous ~ effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the-limit of Specification 3.11.2.1* are not exceeded.

r.

alarm / trip setpoints.of applicable channels shall be detarmined and adjusted in The accordance with the methodology and parametars in the 00CM.

APPLICABILITY: As shown in Table 3.3.7.10-1 F

ACTION:

With a radioactive gaseous affluent monitoring ir.strumentation channel a.

alarm / trip setpoint less conservative than required by the above specification, ceclare the channel inoperable, or. change the'setpoint -

so it is. acceptably conservative.

b.

With less than the minimum number of radioac*ive gaseous effluent monitoring instrumentation channels '0PERABLE, take the ACTION shown in Table.3.3.7.10-1.

Restore the inoperacle instrumentation to j

.(.

OPERABLE status within 30 days 'and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Semiannual Radioactive Effluent Release Report.

l is The provisions of Specification / 3.0.3 r.d 2. 0. 0 m. not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive gaseous affluent monitorin shall be demonstrated OPERABLE by performance of the 'g instrumentation channel

')

CHANNEL CHECX, SOURCE L

CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.

l a

k i

I F-

h. !b i

See Specification 3.11.2.6 for the Main Condenser Offgas Hydrogen Monitor j

(1N64-N012A/B) limit..

I PERRY - UNIT 1 3/4 3 89 i

j INSTRUMENTATION, 1

1

'3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9 The plant' systems actuation instrumentation channels shown in Table I

-3.3.9-1 shall.be OPERABLE with their trip setpoints set consistent with the values shown in the, Trip Setpoint column of Table 3.3.9-2.

f APPLICABILITY: As shown in Table 3.3.9-1.

ACTION:

r.

f

'a. ' With a plant system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9-2, declare the channel-inoperable and either place the 1

l inoperable channel in the tripped condition until the channel is l

restored to OPERABLE status with its trip setpoint adjusted

.{

consistent with the Trip Setpoint value, or declare the associated i

system inocerable.

A b.

For the ' containment spray system:

1.

With the number of OPERABLE channels less than required by the Minimum CPERABLE Channels per Trip System requirement for one

(

trip system, plact at least one inoperable channel in the tripped condition within one hour *or ' declare the associated.

]

system inoperable.

I k

2.

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

Minimum OPERABLE Channels per Trip System requirement for both trip systems, declare the associated system inoperable, j

For the feedwater system / main turbine trip system:

c.

1.

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

the Minimum OPERABLE Channels requirement, restore the 6

inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels requirement, restore at least one I

of the inoperable channels to 0PERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l:

"T.%, =.;.... ef Sec'.ficatier r ^.t r ; = t :;;1!: d 12._

p,.;i.%

PERRY - UNIT 1 3/4 3-98

{

i t

l l

INSTRUMENTATION LIMITING CONDITION.FOR OPERATION (Continued)

ACTION (Continued)

I d.

For the suppression pool makeup system:

1.

For the Drywell Pressure-High and the Reactor Vessel Water Level-Low, Level 1-

-)

i 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 inoperable channel in the tripped condition within one hourA or declare the.

i associated system (s) inoperable.

b)

With more than one channel inoperable, declare the asso-ciated system (s) inoperable.

2.

For the Suppression Pool Water Level-Low, Suppression Pool Makeup Timer an:: the SPMU Manual Initiation:

With the numoe of OPERABLE channels less than required cy the Minimum OPERABLE Channels per Trip System requirement, restore the inoperaole channels to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; i

_p otherwise, declare the associated suppression pool makeuo system l

' inoperable and take the action required by Specification 3.6.3.4.

d SURVEILLANCE REQUIREMENTS 1

4.3.9.1' Each plant system actuation instrumentation channel shall be demon-strated OPERABLE by the ' performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITICNS and at the frequencies shown in Table 4.3.9.1-1.

i 4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all l

channels shall be performed at least once per 18 months.

L gg

=

l (jf. yh PERRY - UNIT 1 3/4 3-99 i

i

i REACTOR COOLANT SYSTEM

(

3/4.4.4 CHEMISTRY k

LIMITING CONDITION FOR OPERATION v

3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY:

At all times.

ACTION:

a.

In OPERATIONAL CONDITION 1:

1.

With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concen-tration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity less than 10 pmho/cm at 25 C and with the chloride concentration less than 0.5 ppm, this need not be reported to the Commission and-t*+

- e f ;. i 'i c a t i e r :. C. * :.r; r,; t ;;;' f :r 's rw.

2.

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

3.

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

b.

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

At all other times:

1.

With the:

1 a)

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

Chloride concentration exceeding the limit specified in Table 3.4.4-1, restore the chloride concentration to within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system.

Determine that the structural integrity of the reactor coolant system remains acceptable for continued oper tion z

prior to proceeding to OPERATIONAL CONDITION 3.

j I

2.

The provisions of Specification 3.0.3 are not applicable.

l PERRY - UNIT 1 3/4 4-13

{

1

REACTOR COOLANT SYSTEM

3/4.4.8 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

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

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

ACTION:

a.

With'the structural integrity of any ASME Code Class I component (s) not conforming'to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant l

System temperature greater than 50*F above the minimum temperature l

required by NDT considerations.

b.

With the structwel 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 to greater than 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 1

the affected component (s) from service.-

J i

/':': : c' S; '" rit# - 11' : : :t :;;'ir d':_

SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5.

/

i PERRY.- UNIT 1 3/4 4-25

.I

i l

g REACTOR COOLANT SYSTEM COLD SHUTOOWN I

LIMITING CONDITION FOR OPERATION l

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 at least:

a.

One OPERABLE RHR pump, and b.

Two OPERABLE RHR heat exchangers.

APPLICABILITY: OPERATIONAL CONDITION 4 when heat losses to the ambient are not sufficient"" to maintain OPERATIONAL CONDITION 4.

ACTION:

a.

With less than the a:ove recuired RHR snutdown cooling moce loo:s CPERAELE, within one hour anc at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereaf ter, demonstrate the.o:eracility of at least one alternate metnoc ca:a:le of cecay heat removal for eacn ino: era le RHR'shutcown cooling moce loo:.

.k-b.

Wita no RHR shutcown cooling mode loc: or recirculation pum: in coeration, within one hour establisn reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

_~.1. ;._ -4 ;i;r.: cf S;;;i finti;r :. 0. " ;r: Je_t_;;;ii:2%

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 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 snutoown cooling made 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.

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

hydrostatic testing.

L

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

[

Der 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERABLE.

t V

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

PERRY - UNIT 1 3/4 4-27

t f

..f 3..:..:

m.n..,,,v :: :-

u

.;i CONTAINMENT VACUUM BREAKERS LIMITING CONDITION FOR OPERATION 3.6.5.1 All containment vacuum breakers shall be OPERABLE and the vacuum breakers shall be closed.

APPLICABILITY: Whenever PRIMARY CONTAINMENT INTEGRITY is required per Specifications 3.6.1.1.1 and 3.5.1.1.2.

ACTION:

a.

With one containment vacuum breaker inoperable for opening but known to be closec, c:aration may continue ard-t'e p-t'>i:icn: Of I;c:i'i::t':.- 2.0.'

;. ;.;1.

i--..'. c.

b.

Witn :.c containment vacuum breakers inoperable and/or with one or two containmen vacuum brea<ers c:en, witnin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months close tne me:cr aceratec isolation valve (s). Restore at least 3 vacuum creakers to OPERASLE anc closed status within 72 neurs or ce in at leas HCT SHUTOCWN -itnin tne next 12 neurs anc in COLD SHUTOCWN within the follcwing 24 neurs.

c.

Wits more than tw: containment vacuum breakers inoceracle anc/cr 0;en, be

('

in at leas: HOT SEUT00hN witnin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOCWN witnin the nex: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , ane:

1.

Maintain an unobstructed opening (s) in the containment that equals or exceeds the flow area provided by two open vacuum breakers, or 2.

Deactivate the containment spray by closing at least one valve in eacn containment spray supply header and deenergizing the power supply to its motor operator.

d.

With the position indicator of any containment vacuum breaker inoperable, restore the inoperable position indicator to OPERABLE status within 14 days or verify the vacuum breaker to be closed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by local indication.

Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Q:

PERRY-UNIT 1 3/4 6-40

i h ga'j,

'3/4.7.S' SEALED SOURCE ~ CONTAMINATION

~PLAC SYSTEMS 2

I

.(IMITINGCONDITIONFOROPERATION 3.7.5 Each sealed source containing radioactive material either in excess of i

100 microcuries of beta and/or gamma emitting material or 10 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 micro-curies of removable contamination.

[

APPLICABILITY: At'all times.

I ACTION:

a.

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

1.

Decontaminate and recair the sealed source, or 2.

Ofsocse of the sealed source in accordance with C:mmission Regulations.

is b.

TheprovisionsofSoecificationk3.0.32-dL1':=notapplicaele.

SURVEILLANCE REQUIREMENTS 4.7.5.1 Test Recuirernentq - Each sealed source shall be tested for leakage l

and/or contamination cy:

a.

The licensee, or a

b.

Other persons specifically authorized by the Commission or an f

Agreement State.

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

r

'4.7.5.2 Test Frequencies Each category of sealed sources, excluding startup sources and fission oetectors 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 half-life greater than 30 days, excluding Hydrogen 3, and X.

2.

In any form other than gas.

PdRRY - UNIT 1 3/4 7-14

i I

g i

REFUELING ODERATION5 Oh5 S '

LOW WATER LEVEL 1'i LIMITING-CONDITION FOR OPERATION 1

3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) j

. system.shall.be OPERABLE and at.least one loop shall be in operation,* with each loop consisting of at least:

.]

1 a.

One OPERABLE RHR pump, and b.-

Two OPERA 8LE RHR heat exchangers.

l

' APPLICABILITY:

OPERATIONAL CONDITION 5, when irradiated fuel.is in the reactor I

vessel anc.tne. water level is less than 22 feet 10 inches above the top of the i

reactor pressure vessel flange:and heat losses to the amcient are not suffi-l cient" to maintain OPERATIONAL CONDITION 5.

.)

ACTICN:

a.

With less tnan the acove required shutcown cooling mece loc:s of the RHR system OPEi!A5LE, 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, I

demonstrate'.tne c:eracility of at least one alternate methoc capable of 7

decay heat removal for eacn inocerable RHR shutcown cooling moce loop.

b.

.With no RHR shutdown cooling mode loop in operation, within one hour l

' establish reactor coolant circulation by an alternate method and monitor j

reactor coolant. temperature at least once per hour.

l c.

Th pr:vi;f;n ;f !;;;f 'f::ti:r, 2. 0. ' : : ets;;

b':.

. 1 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 snutcown 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 cuch that no increase in reactor vessel water temperature will occur ('even though REFUELING conditions are being maintained).

(..ly PENRY-UNIT.1 3/4 9-17 L

__j

i i

L I

1 W

RADI0 ACTIVE E: FLUENT 5

, N.Ilh

.00SE t.

Ln LIMITING CONDITION FOR OPERATION 3.11;1.2' The dose or' dose commitment to a MEMBER OF THE PUBLIC from radioactive

' materials in liquid effluents released, from each. reactor unit, to UNRESTRICTED' 1

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 j

. total bocy and to less than or equal to 5 mrems to any organ,'and l:(

b.

During any calendar year to less than or equal to 3 mrems to the

. tetal body and.to less than or equal to 10 mrems. to any organ.

APPLICABILITY At'all-times.

' ACTION:

~

a-With tne ca1culatec dose from the release of radioactive materials in licuid effluents exceecing any of.the acove limits, prepare and submit' to' tne Commission within 30: days, pursuant to Soecifica-tien S.9.2, a S:ecial Report whien. identifies the cause(s) for exceecing the limit (s) and cefines the corrective actions that have been taken to reduce the. releases anc the -corrective actions to be 4

'U taken to ensure that future releases will be in compliance with tne above limits.

iS b.

The provisions of Specification \\ 3.0.3 e 10

m not applicable.

SURVEILLANCE REQUIREMENTS w...

4.11.1.2 : Dose Calculations.

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

PERRY - UNIT 1 3/4 11-5

.1 i

RADI0 ACTIVE EFFLUENTS L

LIOUID RA0 WASTE TREATMENT SYSTEM t

[ M.y' LIMITING CONDITION'FOR OPERATION 13411.1.3 The LIQUIO.RA0 WASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the~ system shall be used to reduce the release of radioactivity when' the projected doses due to the liquid effluent from each reactor unit to

. UNRESTRICTED AREAS (see Figure 5.1.1-1) would exceed 0.06' mrem to the total.

j body.or 0.2 mrem to any. organ, in a 31-day period.

APPLICABILITY:

At all times.

I h

ACTION:

f

'a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the' Commission, within 30 days pursuant to Specification 6.9.2,.a Special Recort 'ahich incluces the fo11 ewing information:

1.

Explanation of why liquid radwaste was being discharged without; treatment, identification of any inoperaole equipment or suo-systems, anc the reason for the inoceracility, and 2.

Action (s) taken to restore the ineperacle equipment to OPERAELE

-(

sta:us,-and 3.

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

is b.

The provisions of Specification \\ 3.0.3 xd 2.0. * :r: not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED p-AREAS shall-be projected at least once per 31 days, in accordance with method-

},

ology 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.

i l-h

~

1 L

PERRY - UNIT 1 3/4 11-6

+

sy RADIOACTIVE EFFLUENTS

/ffN LIQUID'HOLOUP TANKS LIMITING CONDITION FOR OPERATION 1

i i

3.11.1.4.' The._ quantity.of radioactive material contained in any outside tempo-rary tank, not including liners for_ shipping radwaste, shall be limited to less.than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At'all times.'

m ACTION-l a.

' With the quantity of radioactive material.in. any of the above j

specified tanks exceeding the above limit, immediately suspend all

. additions of radioactive material to the tanks.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 ~ '

1 events. leading to'the condition in the next Semiannual Radioactive

Ef fluent Release Report pursuant'to Specification' 6.9.1.8.

is b.

The provisions of' Specification 3.0.3 c-d 2. 0. ' : :

not acclicaele.

(j{

~* SURVEILLANCE REQUIREMENTS 4.11.1.4 _ The quantity.of radioactive material contained. in each of the above specified tanks shall-be determined to be within the above limit by analyzing

'a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

)

E l

t gP c..

]

PERRY - UNIT 1 3/4 11-7 1

k f,0I0 ACTIVE ~ EFFLUENTS gg DOSE - NOBLE GASES r

' LIMITING COND! TION FOR OPERATION

3.11.2.2 :The: air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site 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 5 mrads for gamma L

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 the radioactive noble gases in gaseous effluents exceeding any of the above limits, preoare and submit to the Commission within 30 days, pursuant to Specifica-tion 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 ensure that future releases will be in compliance with Specification 3.11.2.2.

58 The provisions of Specification \\ 3.0.3 :-d % o d b.

r: not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.2.2 Dosa' Calculations.

Cumulative dose contributions for noble gases 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 days.

i

['

PERRY - UNIT 1 3/4 11-12

1 RADIOACTIVE EFFLUENTS 1

f~ LQ{i[8 -

DOSE - 100INE-131, 100INE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM

]

i J

LIMITING-CONDITION F00 OPERATION

'3.'11.2.3 The-dose to a MEMBER OF THE PUBLIC from Todine-131, iodine-133, l

L tritium.and radionuclides:in particulate form with half-lives greater than J

8 days in gaseous effluents released, from'each reactor unit, from the site to 3

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.

APPLICABILITY:

At all times.

l ACTION:

a.

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

tritium and racianuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare anc suomit 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 that have-been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Specification 3.11.2.3.

18 b.

.The provisions of Specificatiodh 3.0.3...d 3.0.? ;r; not applicable.

A SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days 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 days.

sam

,h PERRY - UNIT 1 3/4 11-13 a_-_-__-__

RADI0 ACTIVE EFFLUENTS gg GASEOUS RA0 WASTE (OFFGAS) TREATMENT

%(

LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RA0 WASTE' TREATMENT (OFFGAS) SYSTEM shall be in operation.

The Charcoal bypass mode shall not be used unless the offgas post-treatment radiation monitor is OPERABLE as specified:in Table 3.3.7.1-1.

APPLICA8ILITY:

Whenever the main condenser air ejector evacuation system is in operation.

ACTION:

a.

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

1.

Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems-which resulted in gaseous radwaste being discharged without treatment, and the reason for 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, is TheprovisionsofSpecificationk3.0.3e.,43.0.0mnot b.

applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of relevant instrumentation shall be checked at least once per 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 gaseous radwaste treatment system is functioning.

f kb 3/4 11-14 PERRY - UNIT l' a

i I

. RADIOACTIVE EFFLUENTS

)

VENTILATION EXHAUST TREATMENT SYSTEMS

.gle LIMITING CONDITION FOR OPERATION I

3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radio-activity when the projected dose due to gaseous effluent releases from each I

reactor unit to areas at and beyond the SITE SOUNDARY (see Figure 5.1.1-1) in a 31 day period would exceed 0.3 mrem to any organ of a MEMBER OF-THE PUBLIC.

APPLICABILITY:

At all times.

I ACTION:

a.

With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.9.2, a Special Report l

which includes the following information:

1.

Explanation of wny gaseous racwaste was teing cisenargec without treatment, identification of any inocera:le ecui: ment or suosystems which resultec in gaseous racwaste bei.9g dischargac without treatmen, anc :ne reason for.ne inoperacility, i

2.

Action (s) taken to restore tne inoperacle ecuipment to OPERABLE status, and 3.

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

iS The-provisions of Specification \\ 3.0.3 rd hs.* c c not b.

applicable, f

SURVEILLANCE REQUIREMENTS

. 4.11.2.5.1 Doses due to gaseous releases from each reactor 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 00CM.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATHENT SYSTEMS shall be demonstrated OPERA 8LE by meeting Specifications 3.11.2.1 and 3.11.2.3.

hi PERR - UNIT 1 3/4 11-15

~

w_______m_.m______.---__m_--

6,

' RADIOACTIVE E*FLUENTS EXPLOSIVE GA5 MIXTURE

...g N MITIflG C0t4DITION COR OPERATION

.1 3.11.2.6 The concentration of hydrogen in the offgas treatment system'shall be limited. to _less than or equal to ~4% by volume.

APPLICABILITY: Whenever the offgas treatment system is in operation.

. ACTI0ft:'

- With. the concentration of hydrogen in the offgas treatment system a.

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 the continuous monitor inoperable, utilize grab sampling

.procecures.

is The provisions of Specification / 3.0.3 :n. :. 0. * : :. net applicable.

.c.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of nycrogen inL the offgas treatment system shall.

be determined to be within the above limits by continuously monitoring the r<

waste gas in the offgas treatment system.whenever the main condenser evacuation system is in operation with the hydrogen. monitor OPERASLE as required by Table 3.3.7.10-1 of Specification 3.3.7.10.

1 J

)

W PERRY - UNIT 1 3/4 11-16 i

[

RADIOACTIVE EFFLUENTS l

i i

3/4.11.3 SOLID RA0 WASTE TREATMENT

' kg:.

l 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

-l 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 l

recurrence.

{

'b.

With.the SOLIDIFICATION or dewatering not performed in accordance with tne PRCCESS CONTROL PROGRAM, (1) test the improperly processed waste in eacn container to ensure that it meets burial grounc and shipping recuiremencs and (2) take appropriate administrative action to prevent recurrence.

is.

(

c.

The provisions of Specification 3.0.3 :nd 2.0.' :r: not acplicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 If the SOLIDIFICATION method is used, the PROCESS CONTROL PROGRAM i

shall be used to-verify the SOLIDIFICATION of at least one representative-test i

specimen.from at least every tenth batch of each type of wet radioactive warte-

. e.g., filter sludges, spent resins, evaporator bottoms, and sodium sulfate

(

solutions).

j l

a.

If any test specimen fails to verify SOLIDIFICATION, the 50LIDIFICA-TION of the batch under test shall be suspenddd until such time as additonal test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

SOLIDIFICATION of the Latch may then be resumed using the alternative SOL *DIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

l N.o

.l PERRY - UNIT 1 3/4 11-18

)

f i

l RADIOACTIVE EFFLUENTS i

3/4.11.4 TOTAL 00SE 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 radiation, from uranium fuel cycle sources snall 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.

i n

APPLICABILITY:

At all times.

ACTION:

I With the calculated doses from th'e release of radioactive materials a.

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 radiation contributions from the reactor units and from outside storage tanks to-determine whether the aoove limits of Specifiestion 3.11.4 have been exceeded.

If sucn is the case, prepare and submit to the Com-mission within 30 oays, pursuant to Specification 6.9.2, a Special Reoort nat cefines the corrective action to ce taken to reduce'sub-secuent releases to prevent recurrence of exceeding the above. limits and incluces the senedule for acnieving conformance with the above limits.

This;Soecial 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 in-cludes the release (s) covered by this report.

It shall also describe levels of radiation and concentrations of radioactive material in-volved, 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 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.

.is i

b.

The provisions of Specification / 3.0.3 M ?.^. ' r; not applicable.

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 00CM.

4.11.4.2 If the cumulative dose contributions exceed the limits defined in 3.11.4, ACTION a, cumulative dose contributions from direct radiation from unit operation including outside storage tanks shall be determined in accordance with the methodology and parameters in the 00CM.

kmN PERRY - UNIT 1 3/4 11-20

\\

o J

3/4.12 RADIOLOGICAL ENVIRONMENTAL MM ITORING 1/,4.12.1"MONITORINGPROGRAM q{

LIMITING CONDITION FOR OPERATION

- 3.12.1 The radiological environmental monitoring program shall be conducted-as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being con-ducted as specified in Table 3.12.1-1, prepare and submit to the Com-mission,.in the Annual: Radiological Environmental Operating Report per Specification 6.9.1.6, a description of the reasons for not conducting the program as required and the plans fcr preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in

[

an environmental sampling. medium at a specified location exceeding the reporting levels.of LTable 3.12.1-2 when averaged over any calendar.

quarter, 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 to be taken to recuce radioactive effluents so that the potential annual 1

dose to a MEMBER OF THE PUSLIC is less than the calendar year limits

'I of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

When more than one of the radionuclides in Table 3.12.1-2 are detected in tne sampling medium, this recort shall be submitted if:

concentration (21 concentration (11 reporting level (1) reportinglevel(2)y..11.0 When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted

.if the potential annual dose

to a MEMBER OF THE-PUBLIC is equal to or' greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an eventi the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.6.

c.

With milk or broad leaf vegetation samples unavailable from one or more of the sample locations ree;uired by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the 00CM. The specific locations from which samples were i

unavailable may then be deleted from the monitoring program.~ Pursuant to Specification 6.14, submit in the next Semiannual Radioactive i

Effluent Release Report documentation for a change in the 00CM includ-ing a revised figure (s).and table for the 00CM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

b q

d.

The provisions of Specification / 3.0.3 = l 3.0.i n not applicable.

j (M

The methodology and parameters used to estimate the potential annual dose to a J

.M MEMBER OF THE PUBLIC shall be indicated in this report.

PERRY - UNIT 1 3/4 12-1

I;'

Ll RADIOLOG! CAL ENVIRONMENTAL' MONITORUG

.g.

3/4.12.2 LAND USE CENSUS p

e

~ LIMITING CONDITION FOR OPERATION 3.12^2 A land use census shall be conducted and shall identify within a. dis-tance of 8 km (5 miles) the location in each of the 16 meteorological sectors.of "J

the nearest milk animal, the nearest residence and the nearest garden

of greater

'{

2 E

than 50 m2 (500 ft ) producing broad leaf vegetation.

i

~

APPLICA8ILITY:

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, identify the new j

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) wnich yielos a calculated dose or dose commitment (via the same exposure patnway) 20 percent greater than'at a location from which milk anc/or broad leaf vegetation samples are currently being obtained in accorcance-with Specification 3.12.1, acc the new. location (s) to the radiological environmental monitoring program within 30 days.

If no milk and/or broad leaf vegetation samples are identified..in the new sector with the highest 0/Q value, tnen the next sector with the hignest 0/Q

(.

value will be considered and so on until a sampling location-can be established.

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 af ter October 31 of the year in which this land use census was conducted,* Identify the new location (s) in the next Semiannual i

Radioactive Effluent Release' Report and also include in the report a revised. figure (s) and table (s) for the 00CM reflecting the new location (s),

g The provisions of Specification / 3.0.3 ?"-?-^ ^ & not applicable.

c.

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, 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 sec-tors with~ the highest predicted 0/Qs in lieu of the garden census.

Specifica-tions for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.

PERRY - UNIT 1 3/4 12-13

RNOIOLOGICAL' ENVIRONMENTAL MONITORING l

3/4.12.3 INTERLA80RATORY COMPARISON PROGRAM (p' f :-

LIMITING' CONDITION FOR OPERATION 1

3.12.3 Analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1.

These materials-are supplied as part of an Interlaboratory Comparison Program which has been-approved.by 'the Commission.

APPLICABILITY:

At all times.

ACTION:-

i l

1 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.

Theprovisionsof. Specification 3.0.3;.;b'2.1.!

b.

r; not applicable.

SURVEILLANCE REQUIREMENTS

(

4.12.3 A summary of the results obtained as part-of the above requ' ired Interlaboratory Comparison Program shall be included in the Annual Radiological l

Environmental Operating Report pursuant to. Specification 6.9.1.6.

l l-l l

E Ab PERRY - UNIT.1 3/4 12-14 i

_ _ - - _ - - - - - _ -. - _ _ _ - - _ - - - _ - -

ML20234E754

Text

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