Text

Amends 129 & 4 to Licenses DPR-66 & NPF-73,respectively, Incorporating Changes to Sections 3.0 & 4.0 of Tech Specs,As Recommended in Generic Ltr 87-09
	ML20207F030
Person / Time
Site:	Beaver Valley
Issue date:	08/09/1988
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20207F035	List: ML20207F030; ML20207F086;
References
	GL-87-009, DPR-66-A-129, NPF-73-A-004 NUDOCS 8808180203
	Download: ML20207F030 (87)
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UNITED STATES NUCLEAR REGULATORY COMMISSION o

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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PEllHSYLVANIA POWER C0f!PANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. OPR-66 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Duquesne Light Company, et al.

(the licensee) dated January 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i

conducted in compliance with the Comission's regulations; O.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and j

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8808100203Og80?00J34 PDR ADOCK O pgg P

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license-1 emendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.129, are hereby incorporated in the license.

The licensee shell operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION r

/'

/,

John F. Stolz, Directoy Prgfect Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issudnce: August 9, 1988

s '

ATTACMNT TO LICENSE AMEND) TNT NO.129 FACILITY CFERATING LICENSE no. DMt-66 CC4KET No. 50-334 Replace the fo11cming pages of the Apper. dix A Technical Specifications with the enclosed pages as indicated. The revised pages are idertified by aanthent nurt>er and contain vertical lines it.dicating the arcas of change.

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 33/4 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 53/4 0 ~/

B3/4 0-8 3/4 1-20 3/4 1-20 3/4 1-20b 3/4 1-20b 1/4 3-33 3/4 3-33 3/4 3-37 3/4 3-37 3/4 3-38 3/4 3-38 3/4 3-41 3/4 3-41 3/4 3-49 3/4 3-49 3/4 3-53 3/4 3-53 3/4 3-59 3/4 3-59 3/4 4-2a 3/4 4-2a 1/4 4-28 3/4 4-28 3/4 7-22 3/4 7-22 I

3/4 11-1 3/4 11-1 l

3/4 11-6 3/4 11-6

)

3/4 11-8 3/4 11-8 3/4 11-10 3/4 11-10 3/4 11-11 3/4 11-11' 3/4 11-15 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-18 3/4 11-18 1/4 11-20 3/4 11-20 3/4 11-21 3/4 11-21 3/4 11-22 3/4 11-22 3/4 11-23 3/4 11-23 3/4 12-2 3/4 12-2 3/4 12-10 3/4 12-10 3/4 12-12 3/4 12-12

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

i 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

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

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

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 ind,1vidual 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , action shall be initiated to place the unit in a

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

BEAVER VALLEY - UNIT 1 3/4 0-1 Amendment No. % h, 129

3/4,0 APPLICABILTTY l

SURVEILLANCE REQUIREMENTS i

l 1.

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

2.

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

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

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

4.0.4 Entry into an 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 sh i be applicable as follows:

a.

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

b.

Surveillance intervals specified in Section XI of the ASME Bciler 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 1 3/4 0-2 Amendment No.9HL 129

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Specification 3.0.1 through 3.0.5 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 FR 50.36(c)(2):

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

When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shutdown the reactor or follow any remedial action permitted by i

the technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL 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 the ACTION requirements.

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

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting condition for Operation must be met.

This time limit is the allowable outage time to restore an inoperable system or ccmponent to OPERABLE status or for restoring parameters within specified limits.

If these' actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in 4 MODE or condition in which the specification no longer applies.

It is not intended _that the shutdown ACTION requirements be used as an operational convenience which pe'rmits (routine) voluntary removal of a'

system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specified time limits of the ACTION requirements are applicable i

from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a

system or component is r.emoved from service for surveillance testing or investigation of operational problems, i

Individual specifications may ir.clude 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 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 ketter-3/2/Si Amendment No.M 129

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.

j 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 the remedial measures of the ACTION requirements is not required when compliance with a

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

Specification 3.~0.3 establishes the shutdown ACTION requirements that l

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 I

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 l

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 j

safety systems under conditions *for which this specification applies.

l 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 J

failure to meet a

Limiting Condition for Operation.

Therefore, a i

shutdown may be terminated if the ACTICN 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.

i BEAVER VALLEY - UNIT 1 B 3/4 0-2 Amendment No.NM,129

3/4.0 APPLICABILITY BASES (Con't)

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

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

Therefore, if remedial measures are completed that would 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.

The same principle applies with regard to the allowable outage tirae limits of 'the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or 1

condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

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

However, the allowable outage time limits

.of ACTION requirements for a higher MODE of operation may not be used to extend the allcwable 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 met.

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 noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a

change in MODES were permitted.

The purpose of this specification is to ensure that 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 status or parameters to specified limits.

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

MODE change.

Therefore,- in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements.

The provisi'ns of this specification should.not, however, be interpreted o

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

When a

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

BEAVER VALLEY - UNIT 1 B 3/4 0-3 Amendment No. 'M, W,129

' APPLICABILITY 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 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 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 each 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 be OPERABLE.

The ACTION statement provides for a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 inoperable emergency power source would also be inoperable.

This would dictate invoking the, applicable ACTION statements'for cach of the applicable Limi. ting 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.

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 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 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 be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, BEAVER VALLEY - UNIT 1

-B 3/4 0-4 Amendment No. % 129 l

.3/4.0 APPLICABILITY BASES (Con't)

trains, components and devices in the other division must be

OPERABLE, or likewise 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 t

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 applicable, and thus the

. individual ACTION statements for each 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):

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

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions i

for which the requirements of the Limiting conditions for Operation 1

apply unless otherwise stated in an individual Surveillance i

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 f acility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The i

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 Specificatien.

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 l

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

transient conditions or other ongoing surveillance or maintenance activities.

Item b. limits the use of the. provisions of item a.

to ensure that it is not used repeatedly to extend

the surveillance interval beyond that specified.

The limits of Specification 4.0.2 are based on engineering judgement and the recognition that the most probable.

BEAVER VALLEY - UNIT 1 B 3/4 0-5 Mendment No.129

[

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, nothi.ng in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This-specification also clarifies that the ACTION l

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 1

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 all' owed surveillance interval, defined by the provisions of Specification 4.0.2, was a

violation of the OPERABILITY l

requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance within the provisior.s of Specification 4.0.2 is a violation of a l

Technical Specification requirement and is, therefore, a reportablo event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

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

Specification 3.0.3, a

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

This provides an adequate time limit to complete Surveillance 4

1 Requirements that have not been performed.

The purpose of this allovsnce 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 i

i completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability i

of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required t

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 hendment No. 129

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i 3/4.0 APPLICABILITY BASES (Con't) time limits of the ACTION requirements are applicTble at that time.

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

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.- However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

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 those 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.

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

When a

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

Specification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code ' class 1,

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

periodically updated version of l

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

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a

clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Ves~sel Code and applicable Addenda.

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

BEAVER VALLEY - UNIT 1 B 3/4 0-7 Miendment No.129 l

i 3/4.0 APPLICABILITY BASES (Con't)

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

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL 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 1.ts specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

BEAVER VALLEY - UNIT 1 B 3/4 0-8 Amendment No.129 l

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMIT NG 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)

Automa'ic Rod Position. Deviation Monitor (2, 3), setpoints 112 l

c

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

l 1

3 (1) During the first hour fol. lowing rod motion, th.e 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 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.

BEAVER' VALLEY - UNIT 1 3/4 1-20 Amendment No 34, 129

LYMITING CONDITION FOR OPERATION (Con't) e.

If the position of a maximum of one rod cannot be 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 detect.-J I

immediately and at'least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last' determination of L

the rod's position.

l 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

?OWER to less than 50% of RATED THERMAL-power within 8 hvars.

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 per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l SURVEILLANCE REQUIREMENTS j

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 indicated positions, and b.

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

cabinet, and determining their agreemerit within 1 2 steps, at least once per 92 days.

i During startup and shutdown, overlap must be checked for all control banks at the respective bank overlap height transition points, i

i Amendment No.% 129 i

BEAVER VALLEY.- UNIT 1 3/4 1-20 b

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

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING j

LIMITING CONDITION FOR OPERATION 3.3.3.1

.The radiation monitoring instrumentation channels shown in Table 3.3.6 shall be OPERABLE with their alarm / trip setpointJ within i

the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a

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

b.

With one or more radiation monitoring channels inopercble, 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.

i BEAVER VALLEY - UNIT 1 3/4 3-33 Amendment No.129 I

~. -. - - - - - -.

INSTRUMENTATION MOVABLE INCORE DETECTORS

]MITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detector 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 detection system, b.

Monitoring the QUADRANT POWER TILT RATIO, or i

N c.

Measurement of FAH and Fg(Z).

ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitorin'g or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

l i

SURVEILLANCE REQUIP.EMENTS l

4.3.3.2 The incere movable detection system shall be demonstrated OPERABLE by normalizjng each detector output to be used i

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use when required for:

i a.

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

Monitoring the QUADRANT POWER TILT RATIO, or N

4 c.

Aeasurement of FAH and Fg(Z).

1 1

BEAVER VALLEY - UNIT 1 3/4 3-37 Amendment No. M,129 4

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-g--W-,,,twm yw*--,,--w----,

--e-sm-.-pwsi.*"*TtT'*'=T*'

-N^*'T

T'*

-'C-*9+v**

INSTRUMENTATION i

((ISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION s

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

APPLIC ABILITY:

At all times.

l ACTION:

a.

With the number of OPERABLE seismic monitoring instruments less than required by Table 3.3-7, restore the inoperable instrument (s) to OPERABLA 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.

c.

The provisions of ~ Specification 3.0.3 are not applicable.

i SURVEILLANCE REQUIREM.NTS 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.

i 1

4.3.3.3.2 A

seismic event greater than or equal to 0.01g shall be reported to the Commission within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Each of the above seisaLe l

monitoring instruments actuated during a seismic event greater than cr equal to 0.01g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a

CRANNEL CALIBRATION performed within 30 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnxtude 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 1 3/4 3'-38 Amendment No. 'M, W.129 l

I

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i i

e >

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

APPLICABILITY:- At all times.

ACTION:

a.

With 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 inoperable channel (s) is restored to OPERABLE status.

b.

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

days, prepa're and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

c.

The provisions of Specification 3.0.3 are not applicable.

1 SURVEILLANCE REQUIREMENTS 4.3.3.4 Eacn of the sbove meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL.ALIBRATION operations at the frequencies c

shown in Table 4.3-5.

1 i

l BEAVER VALLEY - UNIT 1 3/4 3-41 Miendment No.129 1

4

.-....--.a

INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING CORDITION FOR OPERATION i

3.3.3.7 Three. independent chlorine detection systems, with their i

alarm / 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 and 4.

ACTION:

a.

With one chlorine detection system inoperable, operation may I

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

b.

With two chlorine detection systems inoperable, rest 6re one of the inoperable detection systems to OPERABLE status within 7

days, or wit'hin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

c.

With no chlorine detection ' system OPERABLE, within 1

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

l j

SURVEILLANCE REQUIREMENTS 4.3.3.7 Each chlorine detection system shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per il days and a CHANNEL CALIBRATIONEat least once per 18 months.

l h

BEAVER VALLEY - UNIT 1 3/4 3-49 Amendment No.NHL 129

~

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 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 inocerable, 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 unsuccessful, explain in the next Semi-Annual Effluent Release 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 4.3.3.9 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 1 3/4 3-5?

Miendment No. id,129

INSTRUMENTATION RADIOACTIVE GASE005 EFFLUENT MONITORING INSTRUMENTATION I

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 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).

6 l

APPLICA3ILITY During releases through the flow path.

l

~ 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 i

met, immediately suspend the release of radioactive gaseous effluents monitored by the affected-channel or correct the i

alarm / trip sotpoint, i

b.

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

Exert a

best effort to return the channel to operable status within 30 days, *and if unsuccessful, explain in the next Semi-Annual Effluent Release Report why the inoperability was n'ot corrected in a timely manner.

~

i j

e.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4. 3. 3.1' 0 Each radioactive gaseous effluent. monitoring,

instrumentation. channel shall be demonstrated OPERABLE by performance of the CHANNEL CHCCK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

j i

i l

1 l

1 i

4 3

BEAVER VALLEY - UNIT 1 3/4 3-59 Amendment No.14,129

REACTOR COOLANT SYSTEM ACTION (Cont'd)

Below P-7:

a.

With Kg 1

1.0, operation below P-7,may proceed provided at least two reactor coolant loops and associated pumps are in operation.

b.

The provisions of Specification 3.0.3 are not applicable.

l d

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 thats 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.

I 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.

)

BEAVER VALLEY - UNIT 1 3/4 4-2a Amendment No.1HL,129 1

J

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,--,-r- -. - - -,,,., - -., -

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 sarvice.

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.

BEAVER VALLEY - UNIT 1 3/4 4-28 Amenchent No.14,129 1

r r

PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OFF. RATION 3.7.9.1 Each sealed source containing radioactive material either in excess of those quentities of by-product material listed in 10 CFR 30.71 or 'l 0.1 microcuries of any other material, including alpha

emitters, shall be free of 1

0.005 microcuries of removable contamination.

APPLICABILITY At all times ACTION a.

Each sealed source with removable contamination in excess of the above l'imit shall be immediately withdrawn from vse 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 applirtble.

l SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

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

The test method shall have a detec' tion 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.

i l

BEAVER VALLEY - UNIT l-3/4 7-22 knendment No. 129 i

4

_.._,..-3....

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released at any time from the site (See Figure 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, 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-* 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 the concentration within the above limits, and b.

Submit a

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

c.

The provisions of' Specification 3.0.3 are not applicable.

[

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed i

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.

1 l

l i

Radioactive liquid discharges are normally via batch modes.

Turbine Building Drains shall be monitored as specified in Section 4.11.1.1.3.

BEAVER VALLEY - UNIT 1 3/4 11-1 Amendment No h4,129 a

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION OF OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases from the reactor unit (See Figure 5.1-1) when averaged over 31 days would exceed 0.06 mram 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, prepare and submit to the commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following informatient 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 j

3.

Summary description of action (s) taken to prevent a

recurrence, b.

The provisions of Specifications 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Dosas due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.

BEAVER VALLEY - UNIT 1 3/4 11-8 Amendment No. % Wl,129 j

(Nextpageis 3/41110) j 4

RADIOACTIVE EFTLVEt11 l

LIQUID HOLDUP TANKS i

l LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to 3 10 curies, excluding tritium and dissolved or entrained noble' cases.

I 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 ACTION:

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 4.11.1.4.1 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

/cendment No.M.M. l?.9 e

6 b

RADIOACTIVE 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 yalues:

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

SURVEILLANCE 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.

During containment purge the dose rate may be averaged over 960 minutes.

I BEAVER VALLEY - UNIT 1 3/4 11-11 AmendmentNo,M,bl.129

l RADIOACTIVE EFFtUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR 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:

a.

During any calendar quarter to i 5 mrad for gama radtation and i 10 mrad for beta radiation.

b.

During any calendar year, to 110 mrad for gama radiation and 1 20 mrad for beta radiat. ion.

APPLICABILITY:

At all times

)

ACTION:

a.

With the calculated air dose trem radioactive noble gases in gaseous effluents exceeding any si the above limits, prepara 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) at.d 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 Specifications 3.0.3 are not applicable.

l SURVEILLANCE REOUIRE24ENTS 4.11.2.2.1 Dose Calculations.

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

BEAVER VALLEY - UNIT 1 3/4 11-15 Mendment No. )(, JM,129

RADIOACTIVE EFF2,UENTS

DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND ftADIONUCLIDES OTHER TMAN NOBLS GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (s) OE THE PUBLIC from radiciodines and radioactive mater!.als 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 reactor unit (See Figure 5.1-1) shall be limited to the following:

During any calende.r quarter to 1 7.5 mram to any organ, and a.

b.

During any calendar year to i 15 mrem 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 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 Specifications 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.3.1 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 11-16 Amendment No. M, hC, M (Next page is 3/4 11-18) 129 1

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREAT >G2Pr

.t 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 affluent air doses due to gaseous ef fluent 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 erad 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 drys, 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.

Sumary description of action (s) taken to prevent a

recurrence.

b.

The provisions of Specifications 3.0.3 are not applicable.

SURVEILI.ANCE REQUIRTMENTS I

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

1 I

BEAVER VALLEY - UNIT 1 3/4 11-18 Amendment No. '1K, '1%, 't$b l

(Nextpageis 3/411-20) 129 1

1

____,1

RAD 20 ACTIVE 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 152,000 curies noble gases (considered as Xe-133).

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, 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 Specifications 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in each gas storge tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

Performance of this surveillance is required when the gross concentration of the primary coolant is > 100 vC1/ml.

l j

BEAVER VALLEY - UNIT 1 3/4 11-20 Amendment No.W. M 129 i

RADI0 ACTIVE ETTZUENTS EXPLOSIVE GAS MIXTVR4 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 i

concentration exceeds 4% by volume.

MPLICABILITY:

At all times.

i ACTION:

a.

With the concentration'of oxygen in the waste gas holdup system >

2%

by volume but 1 4%

by

volume, imediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to 1 2% by volume within 48 i

hours.

I i

b.

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

by volume, imediately suspend all additions of waste I

gases to the affacted tank and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a, above.

j c.

The provisions of Specifications 3.0.3 are not applicable.

l j R G;,ILLANCE REQUIREMENTS 4.11.1.6.1 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

)

I BEAVER VALLEY - UNIT 1 3/4 11-21 knenchent No.% W.129 l 1

1

o.

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID 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 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.

I 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 bot! toms);

e.

type of container (e.g.,

LSA, Type A,

Type B,

Large Quantity), and f.

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

1 BEAVER VALLEY - UNIT 1 3/4 11-22 Amendment No. % 129 4

'l

_ _ _. _ -. _ ~

o.

RADIOACTIVE EFFLUENTS l

3/4.11.4 TOTAL DO5E LIMITING CONDITION FOR OPERATION l

3.11.4.1 The dose or commitment to MEMBER (S) OF THE PUBLIC from all i

facility releases is limited to

<25 mrom to the total body or any organ (except the

thyroid, which ~is limited to 175 mrem) for a j

calendar year.

APPLICABILITY At all times.

l l

ACTION a.

With the calculated dose from the release of radioactive

~

materials in liquid or. gaseous effluents exceeding twice the l

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 < 25 mrem to the total body or any organ (except thyroid, which is limited to i 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 l

SURVEILLANCE REQUIREMENTS 4.11.4.1.1 Dese 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.

I i

l i

i j

BEAVER VALLEY - UNIT 1 3/4 11-23 Anendment No.h hi,129

)

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

LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued):

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 Tabla 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.

d BEAVER VALLEY - UNIT 1 3/4 12-2 Amendment No, h,129 4

, ~ _ -

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12,2 LAND USE CENSUS I

l LIMITING CONDITION FOR OPERATION j

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 fres'h 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 4

2 and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within 3

a distance of three miles.)

APPLICABILITY:

At all times.

ACTION a.

With a

land use census identifying a location (s) which yields a 3

calculated dose or dose commitment greater than the values l

currently being calculated in Specification 4.11.2.3, prepare and j

submit to the commission within 30

days, pursuant to y

specification 6.9.2/

a Special Report, which identifies the new location (s).

b.

With a

land use census identifying a milch animal l' cation (s) o 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, prepare and submit to the commission within 2

30 days, pursuant to Specification 6.9.2, a Special Report, which identifies the new location.

The new location shall be added to i

the radiological environmental monitoring program within 30 days, j'

from the three active milch animal locations, having the highest if possible.

The milk sampling program shall include samples I

calculated, dose or dose commitment.

Any replaced location may be deleted from this monitoring program after (October 31) of the j

year in which this land use census was conducted.

c.

The provisions of Specification 3.0.3 are not applicable.

l I

a j

Broad leaf vegetation sampling may be performed at the site l

boundary in the direction sector with the highest D/Q in lieu of j

the garden census.

I a

BEAVER VALLEY - UNIT 1 3/4 12-10 Amendment No. h 129 k

4

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,.,.,-n.-v-

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RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM i

LIMITING CONDITION FOR OPERATION I

3.12.3 Analyses shall be performed on radioactive materials supplied as part of.an Interlaboratory comparison Program.

l AEPldCAE_LITY:

At all times t

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.

l 1

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 1

Annual Radiological Environmental Report.

a

]

1 1

I BEAVER VALLEY - UNIT 1 3/4 12-12 Amendment No. M. 129 1

a 9

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r_-_,,

,-,-----,-y

,---_-w

,,y v-,,

---,-,----.--=w.-

-r RADIOACTIVE EFFLUENTS

]

1 i

29.Ela LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose.or dose commitment to MEMBER (S) OF THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see:

Figure 5.1-2) shall be. limited:

l l

a.

During any calendar quarter to less than or equal to 1.5 mrom to the total body and to less than,or equal to 5 mrom to any organ, and 4

b.

During any calendar y' ear to less than or equal to 3 mrom to the total body and to less than or equal to 10 mrom to any organ.

t APPLICABILITY At all times.

ACTION a.

With the calculated dose from the release of radioactive l

l materials in liquid effluents exceeding any of the above limits,

]

prepare and submit to the Cormnission within 30 days, pursuant to I

l 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 l

1 corrective actions to be taken to assure the subsequent releases l

will be within the above limits.

(This Special Report shall also l

)

include (1) the results of radiological analyses of the drinking i'

i 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).*

i

)

b.

Tne provisions of Specification 3.0.3 are t.at' applicable.

l l

1 i

i Applicable only if drinking water supply is taken from the j

receiving water body within 3 miles of the plant discha*ge (3 miles j

downstream only).

1 Amgn g Ng

, K corrected BEAVER VALLEY - UNIT 1 3/4 11-6

I 0,,

UNITE 3 STATES

[

NUCLEAR REGULATORY COMMISSION 5

WASHINGTON. D. C. 20H6 t

'+9.....

DUQUESNE LIGHT COMPANY OHIO ED! SON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY j

THE TOLEDO EDISON COMPANY DOCKET h0. 50-412 BEAVER VALLEY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 4 i

License No. NPF-73 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Compa'ny, et al.

(the licensee) dated January 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisicns of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authori ed by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

+

4

l 2

i 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license l

amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as follows:

l (2) Technical Specifications The Technical Sp6cifications contained in Appendix A. as revised through Amendment No. 4, are hereby incorporated in the license, e

The licensee shall operate the facility in accordance with the l

Technical Specifications.

3.

This license amendment is effective on issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMNISSION

/

Joh'n

. Stolz Directo '

P ct Directorate I-4 0

sion of Reactor Projects 1/!!

Office of Nuclear Reactor Regulation Attachrent:

Changes to the Technical Specifications

'i Date of Issuance: August 9,1988 i

f I

.f

]

i l

_z

.m._

ATTAC MENT TO LICENSE AMENDMENT NO. 4 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 1

i Replace the following p1ges of the Appe'ndix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment nurber and contain vertical lines indicating the areas of change.

a teneve Faces gar,3.VM 3/4 0-1 7

3/4 0 2 0.' ?

'u 33/4 0 1 e.. u 33/4 0-2 33/4 0-3

a.., <.J 33/4 0-4 33/4 0 4 33/4 0-)

a 33/4 0 ;

33/4 0,=7 83/4 0-8 3/4 3-39

/4 3-;9 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 3/4360 3/4 3-65 3/4 3-65 3/4 4 38 3/4 4 38 3/4 7-20 J/4 7 20 i

3/4 11-1 3/4 11-1 1/4 's.1-6 3/4 11-6 3/4 11-7 3/4 11 7 3/4 11-0 3/4 11-8 3/4 11-9 3/4 11-9 3/4'11-13 3/4 11o13 3/4 11-14 3/4 11*14 3/4 11-15 3/# 11-15 3/4 11-16 3/4 11-16 3/4 11-17 3/4 11-17 3/4 11-18 3/4 11-10 3/4 11-19 3/4 11-19 3/4 12 1 3/4 12 1 l

3/4 12-9 3/4 12-9 3/4 12 10 3/4 12-10 1

r

3/4 LIMIT NG 50NCITIONS 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 Ve 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 ACTICN rc.quirements 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 ur.it in a MOUE in which the specification ooes not ap,1y by placing it, as applicable, in:

1.

At least HOT STAND 3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

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

At least COLD SHUT 00WN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit aperation under the ACTION requirements, the ACTION aay 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 conditiens for the Limiting Condition 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 j

may be made in accordance with ACTION requirements when conformance to them

)

permits continued operatinn of the facility for an unlimited period of time.

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

Exceptions to these requirements are stated in the individual specifications.

3.0.5 When a system, subsysta:n, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or Iolely j

because its normal pcwer source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable limiting Con-dition 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , action shall be initiated to place the unit in I.

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

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

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

This specification is not applicable in MODES 5 or 6.

BEAVER VALLEY - UNIT 2 3/4 0-1 Amendment No. 4

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

4,0,2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25% of the surveillance interval, 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 withir. the allowed surveil-lance 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 identi-fied that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be perforrned 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 Requiren nts for inservice inspection and testing of ASME Code Class 1, 2, and 3 componerts shall be applicable as follows:

a.

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

b.

Surveillance intervals specified ir.Section XI of the ASME Boiler and Pressure Vessal Code and applicable Addenda for the inservice inspection and te., ting 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 Amendment No. 4

l 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Specification' 3.0.1 through 3.0.5 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):

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

i When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the techr.ical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement within each indi-vidual spacification 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 require-ments establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

I There are two basic types of ACTION requirements.

The first specifies the remedial measures that permit ct,.. inued operation of Se facility which is not further restricted by the time limits of'the ACTI0t quirements.

In this case, conformance to the ACTION requirements provides an a. aptable level of safety for unlimited continued operation as long as th A.CTION requirements continue to be met.

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met.

This time limit is the allowable outage time to restore an inoper-able system or component to OPERABLE status or for restoring parameters within specified limits.

If these actions are not completed within the allowable out-age time limits, a shutdown is required to place the facility in a MODE or condition in which the 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 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 met.

The time limits of the ACTION requirements are also applicable when a system or component is remosed from service for surveillance testing or investi-gation of operational problems.

Individual specifications may include a speci-fied 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 comply with ACTION requirements, the plant-may have entered a MODE in which a new specification becomes applicable.

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

BEAVER VALLEY - UNIT 2 B 3/4 0-1 Amendment No. 4

1 3/4.0 APPLICABILITY BASES (Continued) l Specification 3.0.2 establishes that noncompliance with a specification exists when the requirements of tne Limiting Condition for Operation are not met and I

the associated ACTION requirements have not been implemented within the speci-fied time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time inter-val constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition for 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 condi-tion 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 i;s ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systerr; 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 pre-pare for an orderly shutdown before initiating a change in plant operation.

This time permits the operstor to coordinate the reduction in electrical genera-tion 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 M ceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown caaabilities of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on compunents 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, the shutdown may be terminated if the ACTION require-ments 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.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in i

the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of 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 applies.

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

For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed j

BEAVER VALLEY - UNIT 2 8 3/4 0-2 Amendment No. 4 L

e

3l4.0 APPLICABILITY BASES (Continued) to reach HOT SHUTDOWN'is the next 11 houts because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to POWER o;eratior.,

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

The same principle applies with regard to the allowable outage timt limits of the ACTION requirements, if compliance with the ACTION requiremen's for one specification results in entry into a MODE or condition of operat fon for another specification in which the requirements of the Limiting Conditica for Operation are not met.

If the new specification becomes applicable in leir time than specified, the difference may be added to the allowable outage t.mi limits of the second specification.

However, the allowable outsge time limits of ACTION requirements for a higher MODE of operation may not be used,o extend the allow-able outage time that is applicable when a Limiting Conditi<,n for Operation is not met in a lower MODE of operation.

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

.Sjecification 3.0.4 establishes limitation on MODE changes when a Limiting Condition for Operation is not met.

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 noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specifica, ion is to ensure that facility operation is not initiated or that higher MODES of operation are not antered when corrective action is being taken to obtain compliance with a specification by r..toring equipment to OPERABLE status or paraiteters to speci-fied limits.

Compliance with ACTION requirements that permit continued opera-tion 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 P0DE change.

Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements.

The provisions of this specifica-tion should not,.however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to 0 PERT.8LE status before plant startup.

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

BEAVER VALLEY - UNIT 2 8 3/4 0-3 Amendment No. 4

3/4.0 APPLICABILITY BASES (Continued)

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 tource 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 dev1cas 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 each 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 be OPERABLE.

The ACTION statement provides for a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months es.t-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, 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 laast one normal (" one emergency power source OPERABLE).

If they 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.

In this case, this would mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, BEAVER VALL:Y - JNIT 2 B 3/4 0-4 Amendment No. 4

3/4.0 APPLICABILITY BASES (Continued) trains, components and devices in the other division must be OPERABLE, 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 specification.

In MODES 5 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.

4 Sycifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requireme,nts.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

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

Specifications 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 unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specifi-cation 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 Excep-tion are only applicable when the Special Test Exception is used as an allow-able exception to the requirements of a specification.

3 Specification 4.0.2 establishes the conditions under which the specified time 4

interval for Surveillance Requirements may be extended.

Item a. permits an allowable extension of the normal surveillance interval to facilitate surveil-lance scheduling and consideration of plarit 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 4

the surveillance interval beyond that specified.

The limits of Specifica-tion 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verifica-tion of conformance with the Surveillance Requirements.

These provisions are BEAVER VALL EY - UNIT 2 8 3/4 0-5 Amendment No. 4 l

____.______________.,--_-,_.____l_,_.3_

3/4.0 APPLICABILITY BASES (Continued) sufficient to ensure that the reliability ensured through surveillance activ-ities is not significantly degraded beyond that obtair.ed from the specified surveillance ' interval.

Specification 4.0.3 establishes the failure to perform a Surveillance Require-ment 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 the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Require-ments.

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 require-ments 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 out-age time limits of the ACTION requirements restores compliance with the require-ments 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 Liriting 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 j

Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(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 j

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

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

The purpose of this allowance is to permit the completion of a surveillance before a shut-down 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 surveil-lance, 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 consequencs of MODE changes imposed by ACTION requirements and for completing Surveillance Require-ments that are applicable when an exception to the requirements of Specifica-tion 4.0.4 is allowed.

If a surveillance i's not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the BEAVER VALLEY - UNIT 2 8 3/4 0-6 Amendment No. 4 l

3/4.0 APPLICABILITY BASES (Continued)

Surveillance Requirements are not met, the time limits of the ACTION require-ments are applicable at the time that the surveillance is terminated.

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

How-ever, the Surveillance Requirements have to be met to demonstrate that inoper-able equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable surveil-lances 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 thes.e systems and components ensure safe operation of the facility.

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

Under the provi ioris of this specification, the applicable Surveillance Require-ments must be ssrformed within the specified surveillance interval to ensure that the Limit.ng Conditions for Operation are met during initial plant startup or following a plant outage.

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

Specification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 componer.ts and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and pressure Vessel Ccde and Addenda as required by 10 CFR 50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

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

This clarifica-tion is provided to ensure consistency in surveillance intervals throughout the.

Technical Specifications and to remove any ambiguities relative to the fre-quencies for performi,ng the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL 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 BEAVER VALLEY - UNIT 2 8 3/4 0-7 Amendment No. 4 l

~

l 3/4.0 APPLICABILITY BASES (Continued) j of performing its specified function, is declared inoperable and. takes preced-ence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be i'ncapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

l l

BEAVER' VALLEY - UNIT 2 B 3/4 0-8 Amendment No. 4-l i

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

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

.a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit 1

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

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

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REOUIREMENTS 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.

\\

i BEAVER VALLEY - UNIT 2 3/4 3-39 Amendment No. 4

INSTRUMENTATION i

MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERAT16N i

l 3.3.3.2 The. movable incore detection system shall be OPERABLE with:

a.

At least 75% of the detector thimbles, l

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 detection system, B.

Monitoring the QUADRANT POWER TILT RATIO, or C.

Measurement of F " and Fq (Z).

3g ACTION:

4 With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Measurement of F " and F9 (Z).

c.

3 i

3EAVER VALLEY - UNIT 2 3/4 3-45 Amendment No. 4

r s.

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

APPLICABILITY:

At all times.

ACTION:

a.

With the number of OPERABLE seismic monitoring instruments less 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.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE RE0VIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, C.HANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

A.3.3.3.2 A seismic event greater than or equal to 0.01g shall be reported to the Commission within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Amendment No. 4 e

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

APPLICABILITY:

At all times.

ACTION:

a.

With the number of OPERABLE meteorological monitoring channels less 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 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

The provisions of Specification 3.0.3 are not applicable.

l c.

i SURVEILLANCE REQUIREMENTS I

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 operati,ons at the frequencies shown in Table 4.3-5.

t e

BEAVER VALLEY - UNIT 2 3/4 3-49 Amendment No. 4 1

g

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

APPLICABILITY:

H0 DES 1, 2, 3, 4, 5 and 6.

ACTION:

a.

With one chlorine detection system inoperable, operation may continue provided the inoperable detector is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , isolate outside air inlet to the control room.

c.

With no chlorine detection system OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolate outside air inlet to the control room.

SURVEILLANCE REOUIREMENTS 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.

BEAVER VALLEY - UNIT 2 3/4 3-56 Amendment No. 4

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INSTRUMENTATION RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

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 alarm / 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.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REOUIREMENTS 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 Amendment No. 4

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION COR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of 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-1 tion channels inoperable, take the ACTION shown in Table 3.3-13 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.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REOUIREMENTS 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 2 3/4 3-65 Amendment No. 4

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 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 i

integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

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 Amendment No. 4

PLANT SYSTEMS 3/4.7.9 SEALED 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 1 0.1 micro-curies of any other material, including alpha emitters, shall be free of 1 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.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.7.9.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

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

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

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

a.

Sources in use (excluding startup sources previously subjected 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 Amendment No. 4

3/4.11 RADI0 ACTIVE 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/mi 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.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.1.1 Radioactive liquid 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 Drains shall be monitored as specified in Section 4.11.1.1.3.

Recirculation drain pump discharge shall be monitored as specified in Section 4.11.1.1.4.

BEAVER VALLEY - UNIT 2 3/4 11-1 Amendment No. 4

RADI0 ACTIVE EFFLUENTS j

DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to MEMBER (S) 0F THE PUBLIC from radio-active materials in liquid effluents released from the reactor unit (see Figure 5.1-1) shall be limited:

a.

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

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

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, 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 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 Orinking Water Act).*

b.

The provisions of Specification 3.0.3 are not applicable l

SURVEILLANCE REOUIREMENTS j

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 Amendment No. 4 5

9 t

RADI0 ACTIVE 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 each liquid waste batch prior to its discharge when the projected doses due to liquid effluent releases from 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.

ACTION:

a.

With liquid waste being discharged without treatment and exceedino the limits specified, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 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 inoperabia equipment to opera-tional 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 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.

BEAVER VALLEY - UNIT 2 3/4 11-7 Amendment No. 4

RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS 1

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of cadioactive material contained in each miscellaneous temporary outside radioactive liquid storage tank shall be limited to 110 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTION:

a.

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

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

i BEAVER VALLEY - UNIT 2 3/4 11-8 Amendment No. 4 e

RADI0 ACTIVE 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 13000 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 11500 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 SURVcILLANCE REOUIREMENTS 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 00CM.

)

j 4.11.2.1.2 The dose rate, inhalation pathway only, for I-131, tritium and all l

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 ODCM by obtaining represen-tative samples and performing analyses in accordance with the samp18ng and anal-ysis program specified in Table 4.11-2.

During containment purge the dose rate may be averaged over 960 minutes.

BEAVER VALLEY - UNIT 2 3/4 11-9 Amendment No. 4

RADIOACTIVE EFFLUENTS DOSE-NOLLE GASES LIMITING CONDITION FOR 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 5 5 mrad for gamma radiation and 510 mrad a.

for beta radiation.

b.

During any calendar year, to 1 10 mrad for gamma radiation and 5 20 mrad for beta radiation.

APPLICASILITY:

At all times.

ACTICN:

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 tha 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.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REOUIREMENTS 4.11.2.2 Dose Calculations.

Cumulative dose contributions shall be determined in accordance with the 00CM at least once every 31 days, l

l BEAVER VALLEY - UNIT 2 3/4 11-13 Amendment No. 4 g.m

O RADI0 ACTIVE EFFLUENTS DOSE-RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIOES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to MEMBER (5) 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 effluents released from the reactor unit (see Figure 5.1-1) shall be limited to the following:

a.

During any calendar quarter to 17.5 mrem to any organ, and b.

During any calendar year to 115 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) witn 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 correctiv.e 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 REQUIRE'1ENTS m_

4.11.2.3 Dose Calculations.

Cumulative dose contributions shall be determined in accordance with the 00CM at least once every 31 days.

BEAVER VALLEY - UNIT 2 3/4 11-14 Amendment No. 4

RADIOACTIVE EFFLUENTS GASEOUS RA0 WASTE 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 subsy' stems 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 REOUIREMENTS 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 2 3/4 11-15 Amendment No. 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, immediately suspend all cdditions of radioactive material to the tanks and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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.

c.

The provisions of Specification 3.0.3 are not applicable.

l

,$URVEILLANCE 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months wt.en radioactive materials are being added to

'the tanks.

1 BEAVER ~ VALLEY - UNIT 2 3/4 11-16 Amendment No. 4 r

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 < 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 < 4% within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , b.

With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 2% by volume, immediately suapend all additions of waste gases to the affected tank and recuce the concentration of, oxygen to less than or equal to 2% by volume within twelve hours.

c.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTE 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 ennjunction with its associated action statement.

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l BEA'!ER VALLEY - UNIT 2 3/4 11-17 Amendment.No. 4

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RADIOACTIVE EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION i

3.11.3..'

The solid radwaste system shall be used, as applicable, to solidify and per age radioactive wastes, and to ensure meeting the requirements of 10 CF6 6art 20, 10 CFR Part 61 and of 10 CFR Part 71.

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

APPLICABILITY:

At all times.

1 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 raolo-active 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 Red'9 active Effluent Release Report in Specification 6.9.1.12 shall include the tollowing information for each type of solid waste shipped offsite during the report period:

a, container volume; b.

total curie QJantity (determined by measurement or estimate);

principal radionuclides (determined by measurement or estimate);

c.

d.

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

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

e.

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 Amendment No. 4

~ - - -

RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4'.1 The dose or dose commitment to MEMBER (S) 0F THE PUBLIC from all facility releases is limited to < 25 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 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.s, or 3.11.2.3.b, prepar5 nd submit a Special Report to the Commission within 30 days pursuant to.p cification 6.9.2 defining the corrective action and limit the subsequent leases such that the dose or dose commitment to MEMBER (S) 0F THE Pl.

..C is limited to i 25 mrem to the total body or any organ (except thyroid, which is limited to 5 75 mrem) for a calendar year.

This special report shall describe the steps to be taken or modifications necesjary 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 Speciffcation 3.0.3 are not applicable.

1 SURVEILLANCE REOUIREMENTS 4.11.4.1 Dose Calculations.

Cumulative cose contributions from liquid and 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.

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BEAVER VALLEY - UNIT 2 3/4 11-19 Amendment No. 4

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM M CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILIT.Y,:

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 Anriual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans fer 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 ccrrective action prior to 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 ar.y 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; hcwever, 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 r, port shall be submitted if:

Concentration (1)

Concentration (2)

+

.... > 1. 0 Limit Level (1)

Limit Level (2)

)

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.

Th'e locatioat from which samples were unavailable may then be deleted from t'~ose required by Table 3.12-1 and the ODCM provided the locations from which the replacement saalles were obtained are added to the environmental monitoring program as replacement locations, if available.

l d.

The provisions of Specification 3.0.3 are not applicable.

l BEAVER VALLEY - UNIT 2 3/4 12-1 Amendment No. 4

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12 2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A lan'd use census shall be conducted and shall indentify the locatire 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 meteo-rological 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 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 tha same exposure pathwaM 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 La added to the radio-logical environmental monitoring program within 30 days, ff 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.

c.

The provisions of Specification 3.0.3 are not applicable.

l 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 info-mation which will provide the best results, such as by a door-to-door survey **, aerial survey, or by consultirig local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the hignest 0/Q in lieu v* the garden census.

- Confirmation by telephone is equivalent to door-to-door, BEAVER VALLEY - UNIT 2 3/4 12-9 Amendment No. 4

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.

The provirions of Specification 3.0.3 are not applicable.

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

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BEAVER VALLEY - UNIT 2 3/4 12-10 Amendment No. 4

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