ML20196A964

Proposed Tech Specs Clearly Defining Intent & Resolving Implementation Problems Associated/W Tech Specs 3.0.4,4.0.3 & 4.0.4

ML20196A964
Person / Time
Site:	Beaver Valley
Issue date:	01/25/1988
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20196A862	List: ML20196A857 ML20196A891 ML20196A964
References
NUDOCS 8802050219
Download: ML20196A964 (77)

Text

ATTACHMENT A-1 4

Revise the Beaver. Valley Unit No.

1 Technical Specifications as follows:

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3/'4 LIMXTING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

' 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a

specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

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

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

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.

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

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

Exceptions to these requirements are stated in the individual specifications.

3.0.5 When a

system, subsystem,

train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:

(1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),

subsystem (s),

train (s),

component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification.

Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, action shall be initiated to place the unit in a

MODE in which the applicable Limiting Condition for Operation does not apply, by placing it, as applicable, in:

BEAVER VALLEY ~ UNIT 1 3/4 0-1 PROPOSED WORDING J

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3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

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

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

This specification is not applicable in MODES 5 or 6.

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

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

a.

A maximum allowable extension not to exceed 25%

of the surveillance interval, and 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 allowed surveillance interval, defined by specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified.

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

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,

2 and 3 components shall be applicable as follows:

a.

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

b.

Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activitics required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

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

,3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY i

BASES i

Specification 3.0.1 through 3.0.5 establish the general requirements I

applicable to Limiting conditions for Operation.

These requirements j

are based on the requirements for Limiting conditions for Operation stated in the Code of Federal Regulations, 10 FR 50.36(c)(2):

1 "Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for 1

safe operation of the facility.

When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shutdown the reactor or follow any remedial action permitted by the technical specification until the condition can be mot."

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e.,

in which OPERATIONAL MODES 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.

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 I

a the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptabic level of safety for unlimited continued operation as long as the ACTION requirements continue to be mot.

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 2

for restoring parameters within specified limits.

If those actions are not completed within the allowable outage time limits, a shutdown l

is required to place the facility in a MODE or condition in which the l

specification no longer applies.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a

system (s) or component (s) from service in lieu of other alternatives that would l

not result in redundant systems or components being inoperable.

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 mot.

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 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 J

comply with ACTION requirements, the plant may have entered a MODE in which a new specification becomes applicable.

In this case, the time BEAVER VALLEY - UNIT 1 B 3/4 0-1 PROPOSED WORDING

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

,3/4.0 APPLICABILITY BASES (Con't) limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting condition for Operation are not met.

Specification 3.0.2 establishes that noncompliance with a

specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a

specification and (2) completion of tne remedial measures of the ACTION requirements is not required when compliance with a

Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

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

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

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would 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 electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on components of the primary coolant system and the potential for a

plant upset that could challenge safety systems under 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, a 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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3/4.0 APPLICABILITY

' BASES (Con't) l The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in the COLD SHUTDOWN MODE when a shutdown is required during 1

the POWER MODE of operation.

If the plant is in a lower MODE of l

operation when a

shutdown is required, the time limit for reaching l

the next lowcr MODE of operation applies.

However, if a lowcr MODE of operation is reached in less time that

allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced.

For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the i

total time to reach HOT SHUTDOWN is not reduced from the allowable l

limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would permit a

return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

i The same principle applies with regard to the allowabic outage time limits of the ACTION requirements, if compliance with the ACTION i

requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes applicable in loss time than specified, the difference may be added to the allowabic outage time limits of the second specification.

However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of specification 3.0.3 do not apply in

]

MODES 5

and 6,

because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a

+

Limiting Condition for Operation is not mot.

It precludes placing the facility in a higher MODE of operation when the requirements for a

Limiting Condition for Operation are not met and continued 1

noncompliance to these conditions would result in a shutdown to 2

comply with the ACTION requirements if a

change in MODES were permitted.

The purpose of this specification is to ensure that i

facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a

specification by restoring equipment to OPERABLE 3

status or parameters to specified limits.

Compliance with ACTION i

requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a

MODE change.

Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in i

accordance with the provisions of the ACTION requirements.

The

+

provisions of this specification should not, however, be interpreted j

as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

)

When a

shutdown is required to comply with ACTION requirements, the l

1 provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

BEAVER VALLEY - UNIT 1 B 3/4 0-3 PROPOSED WORDING l

AP'PLICABILITY

' BASES (Con't) specification 3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to

continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperabic because its normal or emergency power source is inoperable and a

system, subsystem,

train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source.

It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power

source, not the individual ACTION statements for cach system, subsystem,

train, component or device that is determined to be inoperable solely because of the inoperability of its normal or emergency power source.

For

example, Specification 3.8.1.1 requires in part that two emergency diesel generators bc OPERABLE.

The ACTION statement provides for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> out-of-service time when one emergency diesel generator is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems subsystems, trains, components and devices supplied by the inoperabic cmergency power source would also be inoperable.

This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.

In this

case, this would mean that the corresponding normal power source must be

OPERABLE, and all redundant systems, subsystems,

trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE).

If they are not satisfied, action is required in accordance with this specification.

I As a further example, Specification 3.8.1.1 requires in part that two l

physically independent circuits between the offsite transmission network cnd the onsite Class IE distribution system be OPERABLE.

The ACTION statement provides a

24-hour out-of-service time when both required offsite circuits are not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all

systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable.

This would dictate invoking the applicable i

ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied.

In this case, this would mean that for one division the emergency power source must j

be OPERABLE (as must be the components supplied by the emergency i

power source) and all redundant systems, subsystems, trains, BEAVER VALLEY - UNIT 1 B 3/4 0-4 l

PROPOSED WORDING 2

3[4.0 APPLICABILITY

' BASES (Con't)

trains, components and devices in the other division must bc

OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., be capabic of performing their design functions and have an emergency power source OPERABLE).

In other words, both cmergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.

If these conditions are not satisfied, action is required in accordance with this specification.

In MODES 5

or 6 Specification 3.0.5 is not applicabic, and thus the individual ACTION statements for cach applicable Limiting Condition for Operation in these MODES must be adhered to.

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):

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

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unicss otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a

MODE or other specified condition for which the associated Limiting conditions for Operation are applicable.

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

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the 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 allowable extension of the normal surveillance interval to facilitate surveillance scheduling and ccnsideration 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 judgement and the recognition that the most probabic j

BEAVER VALLEY - UNIT 1 B 3/4 0-5 PROPOSED WORDING

3/4.0 APPLICABILITY BASES (Con't) 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 the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under 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 inoperabic 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 allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,

specification 3.0.3, a

24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance.

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

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE 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 BEAVER VALLEY - UNIT 1 B 3/4 0-6 PROPOSED WORDING

i l

' 3/4.0 APPLTCABTLTTY l

BASES (Con't) i time limits of the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the c

Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated, i

Surveillance Requirements do not have to be performed on inoperable l

a equipment because the ACTION requirements define the remedial i

measures that apply.

However, the Surveillance Requirements have to l

be met to demonstrate that inoperable equipment has been restored to OPERABLE' status.

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE 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 MODE or condition for which these systems and components ensure safe operation of the facility.

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

T Under the provisions of this specification, the applicable j

Surveillance Requirements must-be performed within the specified surveillance interval to ensure that the Limiting Conditions for a

Operation are met during initial plant startup or following a plant j

outage.

4 When a

shutdown is required to comply with ACTION requirements, the i

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

L Specification 4.0.5 establishes the requirement that inservice i

inspection of ASME Code Class 1, 2, and 3 components and inservice l

testing of AGME Code Class 1,

2, and 3 pumps and valves shall be performed in accordance with a

periodically updated version of i

Section XI of the ASME Boiler and pressure Vcssel Code and Addenda as required by 10 CFR 50.55a.

These requirements apply except when i

relief has been provided in writing by the Commission.

1 1

This specification includes a

clarification of the frequencies for i

performing the inservice inspection and testing activities required l

by Section XI of the ASME Boiler and Pressure Vessel Code and j

applicable Addenda.

This clarification is provided to ensure l

consistency in surveillance intervals chroughout the Technical j

Specifications and to remove any ambiguities relative to the l

frequencies for performing the required inservice inspection and 1

testing activities.

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PROPOSED WORDING i

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l

' 3/4.0 APPLTCABILITY BASES (Con't)

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressurc Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a

grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

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PROPOSED WORDING

l

. REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The shutdown and control rod position indication system shall be OPERABLE as follows:

Group Demand Counter (1), 1 per group Individual analog rod position instrument channel, 1 per rod 112 steps (1) accuracy (3)

Automatic Rod Position Deviation Monitor (2, 3), setpoints 112 l

steps, or, setpoint verification by recording analog / digital rod position _at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

t I

i e

i (1) During the first hour following rod motion, the group demand counter is the primary indicator of precise rod position information, with the analog channels displaying general rod movement information.

For power levels below 50%, a 1-hour thermal soak time is allowed before the analog channels are required to perform within the specified accuracy.

]

(2) For power levels below 50%

a one hour thermal soak time is allowed.

Therefore, if a Rod Position Deviation Monitor alarm i

clears itself within this hour, the alarm is considered invalid.

(3) Malfunctions of the group demand

counters, analog RPI or Rod Deviation

Monitor, providing no actual rod misalignment existed during the malfunction, shall be reported in the monthly operating report.

i i

i BEAVER VALLEY - UNIT 1 3/4 1-20 j

PROPOSED WORDING

, LIMITING CONDITION FOR OPERATION (Con't) e.

If the position of a maximum of one rod cannot bc determined by either the direct reading of the rod position indicators or by reading primary detector voltage measurements, 1.

Determine the position of the non-indicating rod indirectly by the movable incore detectors immediately and at least once'per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position.

4 f.

If the position of more than one rod cannot be determined by either the direct reading of the rod position indicators or by reading primary detector voltage measurements, then Specification 3.0.3 is applicable.

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL power within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

d.

With the Automatic Rod Deviation Monitor inoperable, POWER OPERATION may continue provided that the deviation between the indicated positions is checked by the operator at least once por 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i' SURVEILLANCE REQUIREMENTS 4.1.3.2.1 Each of the group demand counters shall be determined to be OPERABLE by:

a.

Performing a

CHANNEL CHECK by the group demand counters within a

bank, and observing proper overlap

• of the i

indicated positions, and l

1 b.

Performing a CHANNEL CHECK by an intercomparison between the control bank benchboard indicators and the logic solid state indicators in the logic

cabinet, and determining their agreement within i 2 steps, at least once per 92 days.

t During startup and shutdown, overlap must oc checked for all control banks at the respective bank overlap height transition points, l

i 1

BEAVER VALLEY - UNIT 1 3/4 1-20 b PROPOSED WORDING

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall bc OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a

radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable, b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

1 l

BEAVER VALLEY - UNIT 1 3/4 3-33 PROPOSED WORDING

INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detector system shall bc OPERABLE with:

a.

At least 75% of the detector thimbles, b.

A minimum of 2 detector thimbles por core quadrant, and c.

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

APPLICABILITY:

When the movable incoro detection system is used for:

a.

Recalibration of the axial flux offset detection system, b.

Monitoring the QUADRANT POWER TILT RATIO, or N

c.

Measurement of FAH and F9(Z).

ACTION:

With the movabic incore detcetion system inoperable, do not use the system for the above applicabic monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicabic.

l SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore movable detection system shall be demonstrated OPERABLE by normalizing each detector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use when required for:

a.

Recalibration of the excore axial flux offset detection system, or b.

Monitoring the QUADRANT POWER TILT RATIO, or N

c.

Measuremont of FAH and Fg(Z).

BEAVER VALLEY - UNIT 1 3/4 3-37 PROPOSED WORDING l

l INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

i I

3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

i APPLICABILITY At all times l

ACTION J

a.

With the number of OPERABLE seismic monitoring instruments less than required by Table 3.3-7, restore the inoperable t

instrument (s) to OPERABLE status within 30 days.

l t

b.

With one or more seismic monitoring instruments inoperable for more than 30

days, prepare and submit a Special Report to the commission pursuant to specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for j

restoring the instrument (s) to OPERABLE status.

i c.

The provisions'of Specification 3.0.3 are not applicable.

l I

SURVEILLANCE REQUIREMENTS l

4.3.3.3.1 Each of the above seismic monitoring instruments shall be I

demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

t 4.3.3.3.2 Each of the above seismic monitoring instruments actuated

[

)

during a

seismic event greater than or equal to 0.01g shall bc l

l restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION i

performed within 30 days following the seismic event.

Data shall be j

retrieved from actuated instruments and analyzed to determine the f

magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum and l

l resultant effect upon facility features important to safety.

i 1

i l

l 4

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BEAVER VALLEY - UNIT 1 3/4 3-38

)

PROPOSED WORDING 1

i

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION l

[

3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall bc OPERABLE.

APPLICABILITY:

At all times.

[

ACTION:

a.

With the number of OPERABLE meteorological monitoring channels less than required by Table 3.3-8, suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperabic channel (s) is restored to OPERABLE status.

e b.

With one or more required meteorological monitoring channels inoperable for more than 7

days, prepare and submit a Special l

Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the l

plans for rostoring the channel (s) to OPERABLE status.

t c.

The provisions of Specification 3.0.3 are not applicable.

l

[

1 i

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies

]

shown in Table 4.3-5.

?

4 4

1 1

i

)

BEAVER VALLEY - UNIT 1 3/4 3-41 PROPOSED WORDING i

i

INSTRUMENTATION i

]

CHLORINE DETECTION SYSTEM l

LIMITING CONDITION FOR OPERATION 3.3.3.7 Three independent chlorino detection systems, with their

]

alarm / trip setpoints adjusted to actuate at a chlorino concentration of loss than or equal to 5 ppm, shall be OPERABLE.

t APPLICABILITY:

MODES 1, 2, 3 and 4.

3 1

ACTION:

l l

a.

With one chlorino detection system inoperable, operation may l

J continue provided the inoperable detector is placed in the j

tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

J

]

b.

With two chlorino detection systems inoperable, restore one of i

i the inoperable detection systems to OPERABLE status within 7 l

days, or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation-of the control room emergency ventilation system in the recirculation mode of operation.

i c.

With no chlorine detection system OPERABLE, within 1

hour i

initiate and maintain operation of the control room cmergency ventilation system in the recirculation mode of operation.

l i

i I

SURVEILLANCE REQUIREMENTS f

4.3.3.7 Each chlorino detection system shall be demonstrated

)

OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

l i

I l

i i

I l

l BEAVER VALLEY - UNIT 1 3/4 3-49 I

PROPOSED WORDING i

i i

i

, INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip sotpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm / trip sotpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM).

APPLICABILITY:

During releases through the flow path.

ACTION:

a.

With a

radioactive liquid offluent monitoring instrumentation channel alarm / trip setpoint 1 css conservative than required by the above specification, immediately suspend the release of radioactivc liquid effluents monitored by the affected channel or correct the alarm / trip setpoint.

b.

With one or more radioactive liquid effluent monitoring instrumentation channels inoperabic, take the ACTION shown in TABLE 3.3-12 or conservatively reduce the alarm sotpoint.

Exort a

best effort to return the channel to operable status within 30

days, and if unsuccessful, explain in the next Semi-Annual Effluent Re?. case Report why the inoperability was not corrected in a timely manner.

c.

The provisions of specification 3.0.3 are not applicabic.

l SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL

CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Tabic 4.3-12.

BEAVER VALLEY - UNIT 1 3/4 3-53 PROPOSED WORDING

,INSTRUMENTATXON RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radicactive gaseous offluent monitoring instrumentation channels shown in Tabic 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of 3.11.2.1 are not exceeded.

The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM).

APPLICABILITY During releases through the flow path.

ACTION a.

With a

radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a

value which will ensure that the limits of 3.11.2.1 are

met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm / trip sotpoint.

b.

With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Tabic 3.3-13 or conservatively reduce the alarm setpoint.

Excrt a

best effort to return the channel to operable status within 30

days, and if unsuccessful, explain in the next Semi-Annual Effluent Pelease Report why the inoperability was not corrected in a timely manner, c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

BEAVER VALLEY - UNIT 1 3/4 3-59 PROPOSED WORDING

• REACTOR COOLANT SYSTEM ACTION (Cont'd)

Below P-7:

K gg 1

1.0, operation below P-7 may proceed provided at a.

With e

least two reactor coolant loops and associated pumps are in operation.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.4.1.1.1 With one reactor coolant loop and associated pump not in operation, at least once per 7 days determine that:

a.

The applicable reactor trip system channels specified in the ACTION statements above have been placed in their tripped conditions and, b.

The P-8 interlock setpoint is within the following limits if the P-8 interlock was reset for 2 loop operation:

1.

71%

of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are closed, or 2.

66%

of RATED THERMAL POWER when the reactor coolant stop valves in the nonoperating loop are open.

4.4.1.1.2 The power to each of the reactor coolant system loop stop valves shall be verified to be removed at least once per 31 days during operation in MODES 1 or 2.

l BEAVER VALLEY - UNIT 1 3/4 4-2a PROPOSED WORDING

REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with specification 4.4.10.

APPLICABILITY:

ALL MODES ACTION:

a.

With the structural integrity of any ASME Code Class 1

component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.

b.

With the structural integrity of any ASME Code Class 2

component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.

c.

With the structural integrity of any ASME Code Class 3

component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

I SURVEILLANCE REQUIREMENTS 4.4.10 Each ASME Code Class 1,

2, and 3

component shall be demonstrated OPERABLE in accordance with Specification 4.0.5.

1 i

i i

BEAVER VALLEY - UNIT 1 3/4 4-28 PROPOSED WORDING

PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each scaled source containing radioactive material either in excess of those quantitics of by-product material listed in 10 CFR 30.71 or 1

0.1 microcuries of any other material, including alpha

emitters, shall be free of 1

0.005 microcuries of removable contamination.

APPLICABILITY At all timos ACTION a.

Each scaled source with removable contamination in excess of the above limit shall be immediately withdrawn from uso and:

1.

Either decontaminated and repaired, or 2.

Disposed of in accordance with Commission Regulations.

b.

The provisions of Specification 3.0.3 are not applicabic.

l SURVETLLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each scaled 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.

l 4.7.9.1.2 Test Frequencies - Each category of scaled sources shall be tested at the frequency described below.

i BEAVER VALLEY - UNIT 1 3/4 7-22 PROPOSED WORDING j

l

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS l

CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at any time from the sito (Soc Figure 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Tahte II, Column 2

for radionuclides other than dissolved or cetrained nobic gases.

For dissolved or entrained nobic gases, th4 concentration shall bc limited to 2 x 10~" pC1/ml total activity.

APPLICABILITY:

At all times.

ACTION f

a.

With the concentration of radioactive materici released from the site to unrestricted areas excceding the above limits; immediately restore the concentration withia the abovo limits, and b.

Submit a

Special Report to the Commission within 30 days in accordance with Specification 6.9.2.

c.

The previsions of Specification 3.0.3 are not appAlcabic.

I SURVEILLANCE REQUIREMENTS

_ =. ~.

4.11.1.1.1 Radioactive liquid wastes shall be sampled and analycod according to the sampling and analysis program of Table 4,11-1$.

4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of the ODCM to assure that the concentration at the point of release are maintained within the limits of specifications 3.11.1.1, i

Radioactive liquid.

discharges are normally via batch modes.

Turbino Building trains shall be monitored as specified in Section 4.11.1.1.3.

1 BEAVER VALLEY - UNIT 1 3/4 11-1 PROPOSED WORDING

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to MEMBER (S) OF THE PUBLIC from radioactive materials in liquid offluents released from the site (see Figure 5.1-2) shall be limited:

a.

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

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

APPLICABILITY At all times.

ACTION a.

With the calculated dose from the rolcase of radioactive materials in liquid offluents exceeding any of the above limits, preparc and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a

Special Report which identifics the causc(s) for exceeding the limit (s) and defines the correctivo actions to be taken to reduce the releases, and the proposed i

corrective actions to be taken to assure the subsequent releases will be within the above limits.

(This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act).*

b.

The provisions of Specification 3.0.3 are not applicable.

l l

t 1

i i

Applicable only if drinking water supply is tskon from the rocciving water body, i

1 1

B2 AVER VALLEY - UNIT 1 3/4 11-6 PROPOSED WORDING 1

, RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in cach liquid waste batch prior to its discharge when the projected doses due to liquid offluent releases from the site (Soc Figure 5.1-2) whan averaged over 31 days I

would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY:

At all times ACTION a.

With liquid waste being discharged without treatment and exceeding the limits specified, preparc and submit to the e>mmission within 30 days pursuant to specification 6.9.2 a Special Report which includes the following information:

1.

Identification of the inoperabic equipment or subsystems and the reason for inoperability, j

2.

Action (s) taken to restore the inoperable equipment to i

operational status, and 3.

Summary description of action (s) taken to prevent a

recurrence, b.

The provisions of Specification 3.0.3 are not applicable.

l l

l BEAVER VALLEY - UNIT 1 3/4 11-8 PROPOSED WORDING

RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to 10 caries, excluding tritium and dissolved or entrained noble gases.

a.

BR-TK-6A (Primary Water Storage Tank) b.

BR-TK-6B (Primary Water Storage Tank) c.

LW-TK-7A (Steam Generator Drain Tank) d.

LW-TK-7B (Steam Generator Drain Tank) e.

Miscellaneous temporary outside radioactive liquid storage tanks.

APPLICABILITY:

At all times A,CTION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and b.

Submit a Special Report to the commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

c.

The provisions of Specification 3.0.3 are not applicable.

l

)

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed 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.

BEAVER VALLEY - UNIT 1 3/4 11-10 PROPOSED WORDING i

=.

RADIO OTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a.

The dose rate limit for noble gases shall be 1 500 mrem /yr to the total body and 1 3000 mrem /yr to the skin, and b.

The dose rate limit, inhalation pathway only, for I-131 tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than 8

days shall be 1 1500 mrem /yr to any organ.

APPLICABILITY:

At all times ACTION:

a.

With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s), and b.

Submit a Special Report to the Commission within 30 days pursuant to specification 6.9.2.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLAMCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.

BEAVER VALLEY - UNIT 1 3/4 11-11 PROPOSED WORDING

RADIOACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (See Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the following:

a.

During any calendar quarter, to i 5 mrad for gamma radiation and

$ 10 mrad for beta radiation.

b.

During any calendar

year, to 1 10 mrad for gamma radiation and 1 20 mrad for beta radiation.

APPLICABILITY At all times.

ACTION a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30

days, pursuant to Specification 6.9.2, a

Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS i

4.11.2.2 Dose calculations.

Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

BEAVER VALLEY - UNIT 1 3/4 11-15 PROPOSED WORDING

RADIOACTIVE EFFLUENTS

DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (S) OF THE PUBLIC from radiciodines and radioactive materials in particulate form (excluding C-14),

and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following:

a.

During any calendar quarter to 1 7.5 mrem to any organ, and b.

During any calendar year to 1 15 mrom to any organ.

APPLICABILITY At all times.

ACTION a.

With the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and i

radionuclides (other than noble gases) 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, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.

Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

1 BEAVER VALLEY - UNIT 1 3/4 11-16 (next page is 3/4 11-18)

PROPOSED WORDING

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (See Figure 5.1-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (See Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY:

At all times.

ACTION a.

With gaseous waste being discharged without treatment 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 which includes the following information:

1.

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

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

Summary description of action (s) taken to prevent a

recurrence.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENT 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCM.

BEAVER VALLEY - UNIT 1 3/4 11-18 (next page is 3/4 11-20)

PROPOSED WORDING

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.5 The quantity of radioactivity contained in each gas storage tank shall be limited to < 52,000 curies noble gases (considered as Xe-133).

APPLICABILITY:

At all times.

ACTION a.

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

Submit a Special Report to the Commission.within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

c.

The provisions of Specification 3.0.3 are not applicable.

l l

i SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in each j

gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank when the Waste Gas Decay Tank Monitor (RM-GW-101) is not operable.

4.11.2.5.2 The Waste Gas Decay Tank Monitor (RM-GW-101) operability shall be determined in accordance with Tabic 4.3-13 unless sampling pursuant to 4.11.2.5.1 is being conducted.

BEAVER VALLEY - UNIT 1 3/4 11-20 PROPOSED WORDING

,. _. --.a

4 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to 1

2%

by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY At all times ACTION a.

With the concentration of oxygen in the waste gas holdup system

>2%

by volume, immediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to i 4% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 2%

by

volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 2% by volume within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10 or monitoring in conjunction with its associated action statement.

i l

BEAVER VALLEY - UNIT 1 3/4 11-21 PROPOSED WORDING

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RALIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be used, as applicable, to solidify and package radioactive wastes, and to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71.

Methods utilized to meet these requirements shall be described in facility procedures and in the Process Control Program (PCP).

APPLICABILITY At all times.

ACTION:

a.

With the applicable requirements of 10 CFR Part 20 and 10 CFR Part 71 not satisfied, suspend affected shipments of solid radioactive wastes from the site.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.3.1.1 Prior to shipment, solidification shall be verified in accordance with Station Operating Procedures.

4.11.3.1.2 Reports.

The semi-annual Radioactive Effluent Release Report in Specification 6.9.1.12 shall include the following information for each type of solid waste shipped offsite during the report period:

a.

container volume; b.

total curie quantity (determined by measurement or estimate);

c.

principal radionuclides (determined by measurement or estimate);

d.

type of waste (e.g.,

spent

resin, compacted dry waste evaporator bottoms);

e.

type of container (e.g.,

LSA, Type A,

Type B,

Large Quantity), and f.

solidification agent (e.g., cement, urea formaldehyde).

I BEAVER VALLEY - UNIT 1 3/4 11-22 PROPOSED WORDING

e RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4.1 The dose or commitment to MEMBER (S) OF THE PUBLIC from all facility releases is limited to 125 mrem to the total body or any organ (except the

thyroid, which is limited to 175 mrem) for a calendar year.

APPLICABILITY At all times.

ACTION a.

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, prepare and submit a

Special Report to the Commission within 30 days pursuant to Specification 6.9.2 defining the corrective action and limit the subsequent releases such that the dose or dose commitment to MEMBER (S)

OF THE PUBLIC is limited to 1 25 mrem to the total body or any organ (except thyroid, which is limited to 1 75 mrem) for a

calendar year.

This special report shall describe the steps to be taken or modifications necessary to prevent a recurrence.

Otherwise, obtain a

variance from the Commission to permit releases which exceed the 40 CFR 190 Standard.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.4.1 Dose Calculations.

Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, and 3.11.2.3.b, and in accordance with the ODCM.

BEAVER VALLEY - UNIT 1 3/4 11-23 PROPOSED WORDING

3/4.12 RADIOLOGICAL ENVIRONNENTAL MONITORING 3/4.12.1 MONITORING PROGRAM (Continued)

LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continuedl:

c.

With milk or fresh leafy vegetable samples unavailable from the required number of locations selected in accordance with Specification 3.12.2 and listed in the ODCM, obtain replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1 and the ODCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.

d.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations given in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1.

BEAVER VALLEY - UNIT 1 3/4 12-2 PROPOSED WORDING

l RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A

land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a

distance of five miles.

(For elevated releases as defined-in Regulatory Guide 1.111, (Rev. 1) July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.)

APPLICABILITY:

At all times.

ACTION a.

With a

land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, prepare and submit to the Commission within 30

days, pursuant to l

Specification 6.9.2, a

Special Report, which identifies the new l

location (s).

I b.

With a

land use census identifying a milch animal location (s) which yicids 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, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report, which identifies the new location.

The new location shall be added to the radiological environmental monitoring program within 30 days, if possible.

The milk sampling program shall include samples from the three active milch animal locations, having the highest calculated dose or dose commitment.

Any replaced location may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted, c.

The provisions of Specification 3.0.3 are not applicable.

l 1

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

1

)

l BEAVER VALLEY - UNIT 1 3/4 12-10 PROPOSED WORDING

1 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

APPLICABILITY:

At all times ACTION a.

With analyses not being performed as required above, report the

^

corrective actions taken to prevent a

recurrence to the Commission in the Annual Radiological Environmental Report, b.

The provisions of Specification 3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.12.3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report.

BEAVER VALLEY - UNIT 1 3/4 12-12 PROPOSED WORDING

ATTACHMENT A-2 Revise the Beaver Valley Unit No.

2 Technical Specifications as follows:

Remove Pages Insert Pages 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 B3/4 0-1 B3/4 0-1 B3/4 0-2 B3/4 0-2 B3/4 0-3 B3/4 0-3 B3/4 0-4 B3/4 0-4 B3/4 0-5 B3/4 0-6 B3/4 0-7 3/4 3-39 3/4 3-39 3/4 3-45 3/4 3-45 3/4 3-46 3/4 3-46 3/4 3-49 3/4 3-49 3/4 3-56 3/4 3-56 3/4 3-60 3/4 3-60 3/4 3-65 3/4 3-65 3/4 4-38 3/4 4-38 3/4 7-20 3/4 7-20 3/4 11-1 3/4 11-1 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-7 3/4 11-8 3/4 11-8 3/4 11-9 3/4 11-9 3/4 11-13 3/4 11-13 3/4 11-14 3/4 11-14 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-18 3/4 11-19 3/4 11-19 3/4 12-1 3/4 12-1 3/4 12-9 3/4 12-9 3/4 12-10 3/4 12-10

,3/4 LfMfTfNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY i

LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements.shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the: Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,.

2.-

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

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

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.

3.0.4 Entry litto an OPE 11ATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION reoutres a shutdown if they are not ret withWa specified tire interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIMKL HODES as~ required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

ke o

3.0.5 When a system, subsystem, train, component or device is determined to be because its normal power source is inoperable, it may be c 6g,sQ.

for the purpose of satisfying the requirements of its applicable limiting Con-dition for-0peration, provided:

source is OPERABLE; and (2) all of its redundant system (s), subsyst train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification.

Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply, by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

.At least HOT SHUTOOWN within the following'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

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

This specification is not applicable in MODES 5 or 6.

BEAVER VALLEY - UNIT 2 3/4 0-1 fropain/

NerS

• APPLICABILITY SURVEILLANCE RE0VIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless othe Nise stated in an individual Surveillance Requirement.

4.0.2, Each Surveillance Requirement shall be performed within the specified

,time interval with:

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

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

i.0.3 Failure to perfom a Surveillance Requirement within the allowed x

surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITT requirements for a limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a surveillance Requirement has not been perfor1ned.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the ccepletion of the surveillance when the allowable outage time f limits of the ACTION recuirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.. Surveillance f Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIOMAL PODE or other specified condition shall not g

/

be made un s the Surveillance Requirement (s) associated with a Limiting

\\

I Cond31 4 Operation has been perforwed within the stated s nce 1 ntervar r as otherwise specified. This provision shall no

-passage

\\through or to OPERATIONAL PODES as required to comply with ACTION requirements.

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

di e.

a.

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

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, Sec-tion 50.55a(g)(6)(i).

b.

. Surveillance intervals specified in Secti.on.XI of the _ ASME Boiler.

and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

BEAVER VALLEY - UNIT 2 3/4 0-2 Tropoisl NO ]

'3/4 LIMITING COWITIONS FOR OPERATION AND SURVEILLANCE REQ 3/4.0 APPLICA5ILITT BASES eld.f Specification 3.0.1 through-3.0It establish the general requirements applicable to Limiting Conditions for operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):

or performance levels of equipment required for safe operatio facility.

met, the licensee shall shut down the reactor or follow any re i

I 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 Conditions for Operation is required for safe operatio 1

j i

ACTION requirements establish those remedial measures that must be taken The within specified tim limits when the requiremnts of a Limiting Condition for Operation are not met.

j There are two basic types of ACTION requiremnts. The first specifies the further restricted by the tim limits of the ACTION requirem safety for unlimited continued operation as long as the A In this continue to be met.

limit in which conformance to the conditions of the Limiting Co Operation must be met.

This time limit is the allowable outage time to parameters within specified limits. restore an inoperable system or com i

If these actions are not coepleted within i

the alloweble outage time limits, a shutdown is required to place the in a MODE or condition in which the specification no longer applies not intended that the shutdown ACTION requirements be used as an o.

It is convenience which permits (routine) voluntary removal of a systen(perational component (s) frte service in lieu of other alternatives that would not result s) or in redundant systans or components being inoperable.

The specified time limits of the ACTION requirements are applicable from point in time it is identified that a Limiting Condition for Operation is not met.

The time Itmits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or Investigation of operational problems.

j equipment is removed from service.a specified time limit for the In this case, the allow:ble outage time f 2/lVfA' VAlM Y -M/ T A B 3/4 0-1 N0005E-D N&biA/G'

i l

3/4.0 APPLICA81LITY l

BASES (Con't) the surveillance has not been completed. limits of the ACTION When a shutdown is required to j

comply with ACTION reoutrements, the plant may have entered a MODE in i

new specification becomes applicable.

i ACTION requirements would apply from the point in time that the newIn for Operation are not met.specificatior, becomes applicable if the requireme j

_ Specification 3.0.2 establishes that noncompliance with.a specification when the reouf rements of the Limiting Condition for Operation are not met a the associated ACTION requirements have not been implemented within the specified time interval.

i (1) implementation of the ACTION requirements within the specifie remedial measures of the ACTION requirements is 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 implemented when a Limiting Condition for Operation is not met and the i

condition is not specificaLly addressed by the associated ACTION requirem The purpose of this specification is to delineate the time limits for pla the unit in a safe shutdown MODE when plant owration cannot be maintain within the limits for safe operation defined ay 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 reduj systems or components from service in lieu of other alternatives that wou result in redundant systans or components being inoperable.

allowed to One hour is operation. prepare for an orderly shutdown before initiating a change in plant This time permits the operator to coor111nate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

MODES of operation permit the shutdown to proceed in a cont manner that is well withis the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minime required equipment is OPERAK L This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could c safety systems under conditions for which this specification applies.

under the provisions of the ACTION requirteents are may be terminated.

from the point in time there was a failure to meet a Limiting C Operation.

~Therefore, the shutdown may be terminated if the ACTION not expired, thus providing an allowance for the com actions.

/$E&E4 VANEV-/WJ7' ?

8 3l4 0 2 P2dfdsFD WMPtAkr

' ' - ~

~ ~ '

~ ~ ~

+ -

i 3/4.0 APPLICABILITY l

{

BASES (Con't) 1 The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in _

1 i

the COLD SWTOOWN MODE when a shutdown is required during the POWER MOD l

operation.

If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation ap-plies.

However, if a lower MODE of operation is reached in less time than MODE, is not reduced. allowed, the total allowable time to reach COLD SHUTD For example, if HOT STAMDBY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> b to reach HOT SHUTDOWN is not reduced from the allowable limit o Therefore, if remedial measures are corplated that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE o operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if cos911ance with the ACTION requirements for on specification results in entry into a MODE or condition of operation for Operation are not met.another specification in which the requirements of the Lim 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 allowble outage time limits of ACTION requirements for a higher MODE of operation may not be used to the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

6, because the ACTION requirements of individual sp remedial measures to be taken.

Condition for Operation is not met. Specification 3.0.4 estabitshes lim It precludes placing the facility in a Operation are not met and continued noncogitance t result in a shutdown to comply with the ACTION requirements if a change MODES were permitted.

The purpose of this specification is to ensure that 1

facility operation is not initiated or that higher MODES of operation are n entered when corrective action is being taken to obtain coegliance with a o

specification b.y restoring equipment to OPERABLE status or parameters to specified limits.

Coupliance with ACTION rtquirements that permit continued able level of safety for continued operation without re the plant before or after a MODE change.

with the provisions of the ACTION requirements.an OPERAT 1

The provisions of this exercise good practice in restoring systems or ccep 1

before plant startup.

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

AMt/E4 t/k W-u.t ir.a B 3/4 0-3

$C(dND biGDI'W

,' 3/4eo APPLICASILITY i.

BASES (Con't)

M c & cs G 3.0.5 This specification delineates what additional conditions must be satistled to permit operation to continue, consistent with the ACTION state-ments for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or tievices to be con -

sistent with the ACTION statements of the associated electrical power source.

It allows operation to be governed by the time-limits of the ACTION statement associated with the limiting. Condition for 0peration for the normal or emergency-power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoperabl of the inoperability of its normal or emergency power source.e solely because For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE.

The ACTION statement provides for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> out of service time when one emergency diesel generator is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specifica-tion 3.0.5, all system subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable.

This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Specifica-tion 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.

In this case, this would mean that the corresponding normal power source must be OPERABLE, and all re-dundant systems, subs >

ems, trains, components, and devices must be OPERABLE, or otherwise satisfy :. Tification 3.0.5 (i.e, be capable of performing their design function and have at least one normal or one emergency power source OPERABLE).

If tney are not satisfied, action is required in accordance with this specification.

As a further example, Specification 3.8.1.1 requires in part that two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE.

The ACTION statement pro-vides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification.3.0.5, all. systems, subsystems,. trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable.

This would dictate invoking the applicable ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied division the emergency power source. In this case, this would mean that for one supplied by the emergency power source)t be OPERABLE (as must be the components mus and all redundant systems, subs trains, components and devices in the other division must be OPERABLE, ystems, or like-wise satisfy Specification.3.0.5 (i.e., be capable of. performing their design functions and have an emergency power source OPERABLE). In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.

If these conditions are not satisfied, action is required in accordance with this speci f icat i or.,

BEAVER VALLEY - UNIT 2 8 3/4 0-4 PRoksEb iMDa)(r

.g,0 APPLICABILITY B.ASE S (C o n N In MODES S or 6 Specification 3.0.5 is not applicable, and thus the indi-vidual ACTION statements for each applicable Limiting Condition for Operation in these MODES must be adhered to.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the SurveillanceRef3):utrements stated in the Code of Federal Reptletions, 10 CFR 50.36(c)

I, "Surveillance requirements are requirements relating to test calibra-i tion, 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 comfitions of operation will be met."

i Specification 4.0.1 establishes the requirement that surveillances must be i

performed during the OPERATIONAL MODES or other conditions for which the I

requirements of the Limiting Conditions for Operation apply unless othemise j

stated in an individual Surveillance Requirement. The purpose of this spect-fication is to ensure that surveillances art perfomed to verify the opera-j tional status of systems and components and that parameters are within spect-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIOML MODE for which the requirements of the associated Limiting Condition for Operatio(do not apply unless otherw specified. The Surveillance Requirements associated with a Special Test i

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

l Specification 4.0.2 establishes the conditions under which the specified time Interval for Survefilance Requirements way be extended.

Item a. pernits an allowable extension of the nomal surveillance interval to facilitate surveillance scheduling and consideration of plant operatin may not be suitable for conducting the surveillance; e.g., g conditions that transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the l

use of the provisions of ites a. to ensure that it is not used repeatedly-to extend the surveillance interval beyond that specified. The limits of l

l Specification 4.0.2 are based on engineering,iudgment and the recognition that the most probable result of any particular surveillance being performed is the verification of confomance 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.

j Specification 4.0.3 establishes the failure to perfom a Surveillance Requirement within~the allowed surveillance interval, defined by th of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERMILITY requirements for a Limiting Condition for Operation.

Under the R 3/4 0-i MC/Wfb VIO[D W o

3/4.0 APPt ICABIt.ITY BASES (Con't) provisions of this specification, systems and companents are assmed to be ORERABLE 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 OPERA 8LE 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 allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERA 8ILITY 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 reguirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is providtd to permit a delay in implementing the ACTION requirements. This provides an adequate time Ifmit to complete Surveillance Requirements that have not been performed.

of this allowance is to permit the completion of a surveillance before aThe purpose shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of j

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 i

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 remedfal measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status B 3/4 0- 6 (Xh M h) WCED/5

3/4.0 APPLICABILITY PASES (Con't) must be met before entry into an OPERATIONAL M

ance, operation specified in the Applicability statement.

The pormse of this or parameter limits are met before entry into a MODE these systems and components ensure safe operation of the facility.

associated with plant shutdown as mell as startup. provision This Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval plant startup or following a plant outage.to ensure that the Limit of Specification 4.0.4 do not apply because this woul facility in a lower MODE of operation.

Specification 4.0.5 establishes the requirement that inservice inspection of MME Code class I, 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 upoated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as reqaired by 10 CFR 50.55a. These requirem except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for perfoming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

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

Under the terms of this specification, the more restric Vessel Code and applicable Addenda.

to perform surveillance activities before entry into an OPERATIONAL M other specified condition takes precedence over the ASME Soiler and Pressure Yessel Code provision ehich allows pumps and valves to be tested up to o

)

week after return to normal operation.

capable of performing its specified functionof OPERABLE d precedence over the ASME Boiler and Pressure,Yessel Code provision whic allows a valve to be incapable of performing its specified function for up 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

B 3/4 0-7 000(CSED VhsDMCr-l s

INSTRUMENTATION

~

3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING I

LIM

• TING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 i

shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

TheprovisionsofSpecificatiop3.0.3:,d3.0.4arenotapplicable.

I c.

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

BEAVER VALLEY - UNIT 2 3/4 3-39 fyoyov) Worlag

INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

A minimum of 2 detector thimbles per core quadrant', and c.

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

APPLICABILITY:

When the movable incore detection system is used for:

A.

Recalibration of the axial flux offset de'tection system, B.

Monitoring the QUADRANT POWER TILT RATIO, or C.

Measurement of F and Fq (Z).

ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions..The provisions of Specification /3.0.3and4r074arenotapplicable.

l 30RVEILLANCE REQUIREMENTS 4.3.3.2 The incore movable detection system shall be demonstrated OPERABLE eby normalizing each det.ector output to be used within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use when required for:

Recalibration of the excore axial flux offset detection system, or a.

b.

Monitoring the QUADRANT POWER TILT RATIO, or c.

Measurement of F and Fq (Z).

l 1

BEAVER VALLEY - UNIT 2 3/4 3-45 Qvuposed N0'Y"y

INSTRUMENTAT10N SEISMIC INSTRUMENTATION LIMITING CONDITION'FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

a.

With the number of OPERABLE seismic monitoring instruments a s than required by Table 3.3-7, restore the inoperable instrument (s) to OPERABLE status within 30 days.

b.

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

The provisions of Specification / 3.0.3 and 0-4 are not applicable.

l c.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 A seismic event greater than or equal to 0.01g shall be reported to the Commission within I hour.

Each of the above 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 30 days following the seismic event.

Data shall be retrieved from 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 30 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

BEAVER VALLEY - UNIT 2 3/4 3-46

(%pos ul Wo<J q

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

APPLICABILITY:

At all times.

ACTION:

With the number of OPERABLE meteorological monitoring channels less a.

than required by Table 3.3-8, suspend all release of gaseous radio-active material from the radwaste gas decay tanks until the inoperable channel (s) is restored to OPERABLE status.

b. - With one or more required meteorological monitoring channels inoper-able for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 0.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to 0FERABLE status.

The provisions of Specification / 3.0.3 rd 3.0.4 are not applicable.

l c.

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

BEAVER VALLEY - UNIT 2 3/4 3-49 08/18/87 frof 05ed (N0fd

INSTRUMENTATION CHLORINE DETECTION SYSTEMS LIMITING CONDITION FG;' OPERATION 3.3.3.7 Three independent chlorine detection systems, with their alare/ trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, 4, 5 and 6.

ACTION:

With one chlorine detection system inoperable, operation may continue a.

provided the inoperable detector is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

b.

With two chlorine detection systems inoperable, restore one of the inoperable detection systems to OPERABLE status within 7 days, or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, isolate outside air inlet to the control room.

With no chlorine detection system OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> isolate c.

outside air inlet to the control room.

I d.

The-provisions-of-Specif-icatiert-3r0-4-ere-r,ct ;pplic;ble.

l 4

SURVEILLANCE REQUIREMENTS i

4.3.3.7 Each chlorine detection system shall be demonstrated OPERABLE by per-formance of a CHANNEL FUNCTION TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

h J

r b

4 BE\\VER VALLEY - UNIT 2 3/4 3-56

[ro po s ec]

Wordi

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID, EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at anytime from the site (See Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 pCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore concen-tration within the above limits, and b.

Submit a Special Report to the Commission within 30 days in accordance with Specification 6.9.2.

TheprovisionsofSpecification/3.0.3end3.0.'arenotapplicable.

c.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive '.iquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1*.

4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

"Radioactive liquid discharges are normally via batch modes.

Turbine Building i

Orains shall be monitored as specified in Section 4.11.1.1.3.

Recirculation j

drain pump discharge shall be Qonitored as specified in Section 4.11.1.1.4.

BEAVER VALLEY - UNIT 2 3/4 11-1

~ ~J ~

ProrowJ W"h"j

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.3.2 The dose or dose commitment to MEMBER (S) 0F THE PUBLIC from radio-actis materials in liquid effluents released from the reactor unit (see Figurt 5.1-1) shall be limited:

a.

Durug any calendar quarter to less than or equal to 1.5 mrem to the total body a.'d to less than or equal to 5 mram to any organ, and b.

During any calendar year to less than or equal to 3 arem to the total body and to less than or equal to 10 mrem to any ora n.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases, and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.

(This Special Report shall also include (1) the i

results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements cf 40 CFR 141, Safe Drinking Water Act).*

b.

The provisions of Specification / 3.0.3 :nd 3.0.1 are not applicable l

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations.

Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

• Applicable only if drinking water supply is taken from the receiving water body.

BEAVER VALLEY - UNIT 2 3/4 11-6 fragend

\\Morlig

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FC' OPERATION 3.11.1.3 The Liquid Radwaste Treatment Systes shall be used to reduce the raaioactive materials in each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases frcm the reactor unit (See Figure 5.1-2) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY:

At all times.

1 ACTION:

With liquid waste being discharged without treatment and exceeding the a.

limits specified, prepare and submit to the Commission within 30 days pursuant to Specification 649.2 a Special Report which includes the follow-ing information:

1.

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

Action (s) taken to restore the inoperable equipment to opera-tional status, and 3.

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

TheprovisionsofSpecification/3.0.3:nd3.0.tarenotapplicable.

l SURVEILLAhCE REOUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the 00CM.

l l

BEAVER VALLEY - UNIT 2 3/4 11-7

~ ', ' '

fro po sed Wo rd th e

.I

l e

i RADI0 ACTIVE EFFLUENTS LIQUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each miscellaneous temporary outside radioactive liquid storage tank shall be limited to 1 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

I ACTION:

With the quantity of radioactive material in any of the inbove tanks ex-a.

ceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and b.

Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities I

planned and/or taken to reduce the contents to within the specified limits.

The provisions of Specification / 3.0.3 =d 3.0.4 are not applicable.

l c.

SURVEILLANCE REQUIREMENTS 4,11.1.4 The quantity of radicactive material contained in each of the above listed 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.

8 BEAVER VALLEY - UNIT 2 3/4 11-8 Propo s ej Worfm

RADIO.1?TIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a.

The dose rate limit for noble gases shall be < 500 mrea/yr to the total body and 1 3000 mrem /yr to the skin *, and b.

The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater.

than 8 days shall be 1 1500 mrem /yr to any organ.

_ APPLICABILITY:

At all times.

ACTION:

a.

With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limit (s), and b.

Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2.

The provisions of Specification / 3.0.3 =d 3.0.4 are not applicable.

l c.

SURVEILLAhCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM.

4.11.2.1.2 The dose rate, inhalation pathway only, for 1-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than 8 days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the 00CM by obtaining represen-tative samples and performing analyses in accordance with the sampling and anal-ysis program specified in Table 4.11-2.

• Durinbontainmentpurgethedoseratemaybeaveragedover960 minutes.

BEAVER VALLEY - UNIT 2 3/4 11-9 f to f ose.tl LAofdi G

RADIOACTIVE EFFLUENTS DOSE-NOBLE GASES LIMITING CONDITION FO-OPERATION 3.11.2.2 The air dose from the reactor unit in unrestricted areas (See Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the following:

During any calendar quarter, to i 5 mrad for gamma radiation and i 10 mrad a.

for beta radiation.

b.

During any calendar year, to i 10 mrad for gamma radiation and i 20 mrad for beta radiation.

APPLICABILITY:

At all times.

ACTION:

With the calculated air dose from radioactive noble gases in gaseous a.

effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and de-fines the corrective actions taken to reduce the releases and the-proposed corrective actions to be taken to assure the subsequent releases will be within the above limits, b.

TheprovisionsofSpecification/3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations.

Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

l BEAVER VALLEY - UNIT 2 3/4 11-13

/

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yapose)

\\0MN

RADIOACTIVE EFFLUENTS

~

DOSE-RADIOI0 DINES, RADI0 ACTIVE KATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASE5 LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (S) 0F THE PUBLIC from radioiodines and radioactive materials in particulate form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous affluents released from the reactor unit (see Figure 5.1-1) shall be limited to the following:

a.

During any calendar quarter to 5 7.5 mrem to any organ, and b.

During any calendar year to 515 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) 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, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits.

b.

The provisions of Specification / 3.0.3 cnd 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations.

Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

BEAVER VALLEY - UNIT 2 3/4 11-14 f(oposed Word

_ RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see Figure 5.1-1), when aver-aged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the reactor unit (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With gaseous waste being discharged without treatment 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 which includes the following information.

1.

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

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

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

b.

TheprovisionsofSpecification/3.0.3and3.0.4arenotapplicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the ODCH.

BEAVER VALLEY - UNIT 2 3/4 11-15 p[osad Wod mg

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 The solid radwaste system shall be used, as applicable, to solidify and package radioactive wastes, and to ensure meeting the requirements of 10 CFR Part 20, 10 CFR Part 61 and of 10 CFR Part 71.

Methods utilized to meet these requirements shall be described in facility procedures and in the Process Control Program (PCP).

APPLICABILITY:

At all times.

ACTION:

a.

With the applicable requirements of 10 CFR Part 20, 10 CFR Part 61 and 10 CFR Part 71 not satisfied, suspend affected shipments of solid radio-active wastes from the site.

b.

TheprovisionsofSpecification/3.0.3ed3.0.'arenotapplicable.

l SURVEILLANCE RE0UIREMENTS 4.11.3.1.1 Prior to shipment, solidification shall be verified in accordance with Station Operating Procedures.

4.11.3.1.2 Reports.

The semi-annual Radioactive Effluent Release Report in Specification 6.9.1.12 shall include the following information for each type of solid waste shipped offsite during the report period:

a, container volume; i

b.

total curie quantity (determined by measurement or estimate);

principal radionuclides (detemined by measurement or estimate);

c.

d.

type of waste (e.g., spent resin, compacted dry waste evaporator bottoms);

e.

type of container (e.g., LSA, Type A, Type B, Large Quantity);

f.

solidification agent (e.g., cement); and g.

classification and other requirements specified by 10 CFR Part 61.

BEAVER VALLEY - UNIT 2 3/4 11-18 i

h(o p e Stel N o fcllN Q

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOL OPERATION 3.11.4.1 The dose or dose commitment to MEMBER (S) 0F THE PUBLIC from all facility releases is limited to < 25 arem to the total body or any organ (except the thyroid, which is limited to i 75 arem) for a calendar year.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tions 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a or 3.11.2.3.b, prepare and submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 defining the corrective action and limit the subsequent releases such that the dose or dose commitment to MEMBER (S) 0F THE PUBLIC is limited to < 25 arem to the total body or any organ (except thyroid, which is limite3 to 175 arem) for a calendar year.

This special report shall describe the steps to be taken or modifications necessary to prevent a recurrence.

Otherwise, obtain a variance from the Commission to permit releases which exceed the 40 CFR 190 Standard.

b.

The provisions of Specification 3.0.3 :nd 3.0.' are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Dose Calculations.

Cuculative dose contributions from liquid and f

gaseous effluents shall be determined in accordance with Specifica-tions 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, 3.11.2.3.a. and 3.11.2.3.b and in accordance with the ODCM.

\\

1 BEAVER VALLEY - UNIT 2 3/4 11-19

~ ~ 1 ~~

Pro posed Wod q

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM l

l LIMITING CONDITION FOR OPERATION 4

3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a re-currence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal un-availability, or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to i

the end of the next sampling period.

b.

With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to Specification 6.9.2 which includes an evalua-tion of any release conditions, environmental factors or other aspects which caused the limits of Table 3.12-2 to be exceeded This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

1 Concentration (1)

Concentration (2)

+

+

.... > 1.0 Limit Level (1)

Limit Level (2) l

~

With milk or fresh leafy vegetable samples unavailable from the required c.

number of locations selected in accordance with Specification 3.12.2 and

)

listed in the ODCM, obtain replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12-1 and the ODCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.

d.

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

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1 BEAVER VALLEY - UNIT 2 3/4 12-1 Qcoyosed lA0fdE i

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall indentify the location of the nearest milk animal, the nearest residence, and the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

For elevated releases as defined in Regulatory Guide 1.111, (Rev.1) July 1977, thr. land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteo-rological sectors within a distance of three miles.

APPLICABILITY:

At all times.

ACTION:

With a land use census identifying a location (s) which yields a calculated a.

dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report, which identifies the new location (s),

b.

With a land use census identifying a milk animal location (s) which 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 ;,repare and submit to the Commission withi., 30 days, pursuant to Specification 6.9.2, a Special Report, which identifies the new location.

The new location shall be added to the radio-logical environmental monitoring program within 30 days, if possible.

The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment.

Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

The provisions of Specification 3.0.3 and-3rer4 are not applicable.

l c.

SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey **, aerial survey, or by consulting local agriculture authorities.

• Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

• • Confirmation by telephone is equivalent to door-to-door.

BEAVER VALLEY - UNIT 2 3/4 12-9 fopesel hid I}

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

APPLICABILITY:

At all times.

ACTION:

With analyses not being performed as required above, report the corrective a.

actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.

b.

TheprovisionsofSpecific& tion /3.0.3and2.0.1arenotapplicable.

l SURVEILLANCE REOUIREMENTS 4.12.3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report.

t 4

BEAVER VALLEY - UNIT 2 3/4 12-10 frayased 00 (d '

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The alarm /

trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM).

APPLICABILITY:

During releases through the flow path.

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 effluents monitored by the affected channel or correct the alam/ trip setpoint.

b.

With one or more radioactive liquid effluent monitoring instrumenta-tion channels inoperable, take the ACTION shown in Table 3.3-12 or conservatively reduce the alarm setpoint.. Exert a best effort to return the channel to operable status within 30 days, and if unsuc-

cessful, explain in the next Semi-Annual Effluent Release Report why the inoperability was not corrected in a timely manner, TheprovisionsofSpecification/3.0.3rd3.0.4arenotapplicable.

l c.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in' Table 4.3-12.

BEAVER VALLEY - UNIT 2 3/4 3-60

($opo:.cd LAbE

I,NSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of 3.11.2.1 are not exceeded.

The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with the Offsite Dose Calculation Manual (00CM).

APPLICABILITY:

During releases through the flow path.

ACTION:

a.

With a radioactive gaseous process or effluent monitoring instrumenta-tion channel alarm / trip setpoint less conservative than a value which.

will ensure that the limits of 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm / trip setpoint.

b.

With one or more radioactive gaseous effluent monitoring instrumenta-tion channels inoperable, take the ACTION shown in Table 3.3-13 or conservatively reduce the alare setpoint.

Exert a best effort to return the channel to operable status within 30 days, and if unsuc-cessful, explain in the next Semi-Annual Effluent Release Report why the inoperability was not corrected in a timely manner, The provisions of Specification;l 3.0.3 rd 3.0.1 are not applicable.

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c.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operatinns at the frequencies shown in Table 4.3-13.

BEAVER VALLEY - UNIT 2 3/4 3-65 froposed WO

"[j

' REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY

~

ASME CODE CLASS 1, 2, AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.10.

APPLICABILITY:

All MODES.

ACTION:

With the structural integrity of any ASME Code Class 1 component (s) a.

not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum tempera-ture 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.

With the structural integrity of any ASME Code Class 3 component (s) c.

not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service, d.

, The-provisions-of-Spec 4f4 cat 4on 3.0.4 are not appMc4M+.

l SURVEILLANCE REOUIREMENTS 4.4.10 'Each ASME Code Class 1, 2, and 3 component shall be demonstrated OPERABLE in accordance with Specification 4.0.5.

BEAVER VALLEY - UNIT 2 3/4 4-38 1% gsed @ @

PLANT SYSTEMS 3/4.7.9 SEALE0 SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of those quantities of byproduct material listed in 10 CFR 30.71 or > 0.1 micro-curies of any other material, including alpha emitters, shal.1 be free of

> 0.005 microcuries of removable contamination.

APPLICABILITY:

AT ALL TIMES.

ACTION:

a.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

1.

Either decontaminated and repaired, or 2.

Disposed of in accordance with Commission Regulations.

b.

TheprovisionsofSpecification/3.0.3ed3.0.'arenot l

applicable.

i SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage i

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, 4.7.9.1.2 Test Frequencies - Each category of sealed sources shall be tested at the frequency described below, j

a.

Sources in use (excluding startup sources previously sub.iected to core flux) - At least once per six months for all sealed sources containing radioactive materials.

1.

With a half-life greater than 30 days (excluding Hydrogen 3) and 2.

In any form other than gas.

BEAVER VALLEY - UNIT 2 3/4 7-20 hopsed WorJ %

4 RADI0 ACTIVE EFFLUENTS GASEOUS WASTE STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.5 The quantity of radioactivity contained in any connected group of gaseous waste storage tanks shall be limited to < 19,000 curies noble gases (considered as Xe-133).

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any connected group of gaseous waste storage tanks exceeding the above limit, ismediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> re -

duce the tanks contents to within the limit, and b.

Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

TheprovisionsofSpecification/3.0.3=d3.0.4arenotapplicable.

l c.

SURVEILLANCE REOUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in any connected group of gaseous waste storage tanks shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tanks.

i 1

BEAVER VALLEY - UNIT 2 3/4 11-16 Qco go sed

'80(dt I

RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to 1 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY:

At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas holdup system > 2% by volume, immediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to 14% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

With the concentration of oxygen in the waste gas holdup system grteter than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 2% by volume within twelve hours, TheprovisionsofSpecification,/3.0.3:nd3.0.1arenotapplicable.

l c.

SURVEILLANCE REOUIREMENTS 4.'11.2.6 The concentrations of oxygen in the waste gas holdup system shall be determinid to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10 or monitoring in conjunction with its associated action statement.

BEAVER VALLEY - UNIT 2 3/4 11-17 fra f a seel N0fd W

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ATTACHMENT B

Safety Analysis Beaver Valley Power Station proposed Technical Specification Change Unit 1 Change No. 145 Unit 2 Change No. 1 Description of amendment request:

The proposed amendment would incorporate the changes to Section 3.0 and 4.0 and applicable bases of the Beaver Valley Unit 1

and Unit 2 Technical Specifications recommended in accordance with Generic Letter 87-09.

The NRC has determined that specifications 3.0.4, 4.0.3 and 4.0.4 may be modified to clarify the intent and resolve the following three problems associated with those requirenients :

1) unnecessary restrictions on mode changes provided by specification 3.0.4; 2) unnecessary shutdowns caused by specification 4.0.3 when surveillance intervals are inadvertently exceeded; and 3) conflicts between specifications 4.0.3 and 4.0.4.

Generic Letter 87-09 provides an in-depth discussion of the identified problems and the solutions recommended by the NRC.

The Unit 1

and Unit 2 Technical Specifications were reviewed in accordance with the recommendations provided in Generic Lotter 87-09.

To reficct those recommendations exceptions to specification 3.0.4 will be deleted in the following locations since the revision to specification 3.0.4 permits continued plant operation.

Beaver Valley Unit 1 Page Section Page Section 3/4 1-20 3.1.3.2 3/4 11-8 Action b 3/4 1-20b Action d 3/4 11-10 Action c 3/4 3-33 Action c 3/4 11-11 Action c 3/4 3-37 Action 3/4 11-15 Action b I

3/4 3-38 Action c 3/4 11-16 Action b 3/4 3-41 Action c 3/4 11-18 Action b 3/4 3-49 Action d 3/4 11-20 Action c

)

3/4 3-53 Action c 3/4 11-21 Action c 3/4 3-59 Action c 3/4 11-22 Action b i

3/4 4-2a Action b 3/4 11-23 Action b 3/4 4-28 Action d 3/4 12-2 Action d 3/4 7-22 Action b 3/4 12-10 Action c i

I r

-.. ~. -

A'rTACHMENT B Page 2 Page Section Page Section i

3/4 11-1 Action c 3/4 12-12 Action b 3/4/11-6 Action b l

i Page 3/4 3-33, Action a and b reference the actions applicable to 4

Table 3.3-6, one of

these, Action 20 requires compliance with the i

action requirements of specification 3.4.6.1.

Action a and b of specification 3.4.6.1 require a

plant shutdown within a specified j

time interval.

Therefore, an exception to specification 3.0.4 is l

required to allow mode enanges in accordance with the action requirements.

Action e

of specification 3.4.6.1 is the only 1

j specification referenced containing an exception to specification 3.0.4, therefore, the exception to specification 3.0.4 in Action c of speciffbation 3.3.3.1 will be deleted.

1 Beaver Valley Unit 2 Page Section Page Section l

3/4 3-39*

Action c 3/4 11-8 Action c j

3/4 3-45 Action 3/4 11-9 Action c 3/4 3-46 Action c 3/4 11-13 Action b l

l l

3/4 3-49 Action c 3/4 11-14 Action b l

3/4 3-56 Action d 3/4 11-15 Action b i

l 3/4 3-60 Action c 3/4 11-16 Action c 3/4 3-65 Action c 3/4 11-17 Action c 1

3/4 4-38 Action d 3/4 11-18 Action b 3/4 7-20 Action b 3/4 11-19 Action b 3/4 11-1 Action c 3/4 12-1 Action d 3/4 11-6 Action b 3/4 12-9 Action c 3/4 11-7 Action b 3/4 12-10 Action b l

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• See BV-1 discussion of action statements applicable to cpecification 3.3.3.1.

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Ah ACHMENT B Page 3 o

The Unit 1

and Unit 2

specifications listed below would not satisfy the provisions under which mode changes are permitted by the revision to specification 3.0.4 since the action statements require a plant shutdown within a

specified time interval.

Therefore, these pages are listed for information only and the exception to specification 3.0.4 will not be deleted.

Beaver Valley Unit 1 Page Section Page Section 3/4 3-50 Action c 3/4 4-32 Action a 3/4 4-11 Action c 3/4 6-5 Action a.4 3/4 4-27a Action c 3/4 7-1 Action c Beaver Valley Unit 2 Page Section Page Section 3/4 1-8 Footnote 3/4 4-35 Action d 3/4 1-11 Footnote 3/4 4-39 Action e 3/4 3-57 Action c 3/4 4-40 Action a 3/4 3-74 Action c 3/4 6-4 Action a.4 3/4 4-17 Action c 3/4 7-1 Action b l

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)

ATTACHMENT C

No Significant Hazards Evaluation Beaver Valley power Station proposed Technical Specification Change Unit 1 Change No. 147 Unit 2 Change No. 2 Basis fer proposcd no significant hazards consideration determination:

The Commission has provided standards for determining whether a

significant hazards consideration exists (10 CFR 50.92(c).

A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

The proposed changes do not involve a

significant hazards consideration because:

(1) This is an administrative change being proposed to provide clarification of the action to be applied to the RTB (Table 3.3-1 item 21).

Both Action 1 and Action 40 are the actions specified for this item and Action 1

is being revised by adding except for one of the diverse trip features (undervoltage or shunt trip attachment) inoperable apply Action 40".

This is being done to more clearly define when Action 40 is to be applied.

This is consistent with the intent of Generic Letter 85-09 which provides the basis for incorporating the RTB diverse features into the technical specifications.

Therefore, clarification is provided for applicability of these actions and is consistent with the commissions recommendations in Generic Letter 85-09 and will not affect the UFSAR or the probability of occurrence or the consequences of an accident previously evaluated.

(2) These changes are administrative in nature since only clarification is provided and no change to equipment or components or the FSAR accident analysis is required.

Thus, no adverse safety considerations are introduced by the proposed changes.

Therefore, the probability for an accident or a malfunction of a different type than previously evaluated would not be created.

(3) The proposed change provides clarification for applying Action 40 to cicarly reflect the intent of Generic Letter 85-09 and resolve potential problems associated with unnecessary restrictions on plant operability.

This change makes it very cicar that Action 40 is to be applied in lieu of Action 1 if one of the diverse trip features (undervoltage or shunt trip attachment) is inoperable.

Action 40 provides up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in which to restore the breaker to operable status and the breaker may be bypassed for that time required for performing maintenance to restore the breaker to operable status.

Therefore, clarification is provided and the proposed change does not affect any safety analysis or design basis which would involve a significant reduction in the margin of safety.

S

~ *APTACHMENT C

(

Page 2 The Commission has provided guidance concerning the application of the standards for determining whether a

significant hazards consideration exists by providing certain examples (54 FR 7751) of i

amendments that are considered not likely to involve significant hazards consideration.

Example (i) relates to "A

purely administrative change to technical specifications:

for example, a change to achieve consistency throughout the technical specifications, correction of an

error, or a

change in l

nomenclature".

The proposed change relates to this example in that the proposed changes are requested to achieve consistency throughout the technical specifications and reduce confusion concerning implementation of the requirements in accordance with the recommendations provided in Generic Letter 87-09.

Therefore, based on the above considerations, it is proposed to characterize the changes as involving no significant hazards consideration.

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