Text

Amends 48 & 41 to Licenses NPF-35 & NPF-52,respectively, Changing Tech Spec Sections 3.0 & 4.0 to Conform to Generic Ltr 87-09
	ML20151A446
Person / Time
Site:	Catawba
Issue date:	07/12/1988
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20151A449	List: ML20151A446;
References
	GL-87-09, GL-87-9, NUDOCS 8807190382
	Download: ML20151A446 (75)
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c UNITED STATES NUCLEAR REGULATORY COMMISSION o

WASHING TON, D. C. 20555

+... 4l DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.

DOCKET N0. 50-413 CATAW8A NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. NPF-35 1.

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

M' in.

I A.

The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,

(licensees dated January 11, 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 as 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 ond regulations of the Conmission; 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 conducted in compliance with the Comnission's regulations set forth in 10 CFR Chapter !;

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.

8807190382 880712 PDR ADOCK 05000413 P

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. 2.

Accordingly, the license is hereby amended by page changes to the Technical

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Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 48, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

F6R THE NUCLEAR REGULATORY COMMISSION Original signed by:

David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects _1/II

Attachment:

Technical Specification Changes Date of Issuance:

July 12, 1988

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UNITED STATES NUCLEAR REGULATORY COMMISSION 7.

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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. NPF-52 1.

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

,.d-I A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by tha Duke Power Company acting for itself, North Carolina Municipal Power Agency No. 1 and Piedmont Municipal Power Agency, (licensees) dated January 11, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, ac amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The f6cility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.

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Accordingly, the license is hereby amended by 'page changes to the Technical Specifications as' indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. HPF-52 is hereby

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amended to read as follows:

(2) Technical Specifications The Technica1' Specifications contained in Appendix A, as revised through Amendment No. 41, are hereby incorporated into the license.

The licensee shall operate.the facility-in accordance with the Technical Specifications and the Environmental Protection Plan, p-g l'

3.

This license amendment is effective-as of its date of issu'ance.-

FOR THE tiUCLEAR REGULATORY COMillSS10H Griginal signed by:

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David B. Matthews, Director t

Project Directorate 11-3 L'

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ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE N0. NPF-35 DOCKET NO. 50-413 AND TO LICENSE ANENDMENT N0.

FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specificat;oas with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding over-leaf pages are also provided to maintain document completeness.

Amended Page Overleaf Page 3/4 0-1 d'

1.-

I 3/4 0-2 3/4 0-3 83/4 0-1 83/4 0-2 83/4 0-3 83/4 0-4 new page B3/4 0-5 new page B3/4 0-6 new page 3/4 2-14 3/4 2-13 3/4 3-2 3/4 3-3 3/4 3-5 3/4 3-15 3/4 3-16 3/4 3-17 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-21 3/4 3-22 3/4 3-23 3/4 3-25 3/4 3-51 3/4 3-52 3/4 3-55 3/4 3-56 3/4 3-59 3/4 3-60 3/4 3-70 3/4 3-71 3/4 3-72 3/4 3-79 3/4 3-80 3/4 3-85 3/4 3-86 3/4 3-92a 3/4 4-39 3/4 4-40

l*

e l

Amended Page Overleaf Page 3/4 7-25 3/4 7-26 3/4 7-27 3/4 7-28 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-36 3/4 7-35 3/4 9-9 3/4 9-10 3/4 9-13 3/4 9-14 3/4 11-5 3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-13

'3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-17 3/4 11-18 3/4 11-19 3/4 12-2 d'

3/4 12-13 3/4 12-14

'a-i 3/4 12-15 e

W i i

3/4 LIMITING CONDITIONS FOR' OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Complicnce with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

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

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

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a.

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

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

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

Where corrective measures are completed that permit operation under the ACTI,0,N j, g

requirements, the action may be taken in accordance with the specified time' limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be i

made when the conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a l

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 i

required to comply with ACTION requirements.

Exceptions to these requirements l

are stated in the individual specifications.

3.0.5 Limiting Conditions for Operation including the associated ACTION requirements shall apply to each unit individually unless otherwise indicated as follows:

a.

Whenever the Limiting Condition for Operation refers to systems or components which are shared by both units, the ACTION requirements will apply to both units simultaneously.

This will be indicated in l

the ACTION section; b.

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

Whenever certain portions of a specification contain operating parameters, setpoints'etc., which are different for each unit, this l

will be identified in parentheses or footnotes.

(For example,

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

CATAWBA - UNITS 1 & 2 3/4 0-1 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) l

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

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

a.

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

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

4.0.3 Failure to perform a Surveillance Requirement within the allowed sur-veillance interval, defined by Specification 4.0.2, shall constitute noncompli-ance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it isa-d' I

identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be Jelayed 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) associatea with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

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

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

a.

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

CATAWBA - UNITS 1 & 2 3/4 0-2 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) b.

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

ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually Atleastonceper366dg{s I

The provisions of Specification 4.0.2 are applicable to the above I

c.

required frequencies for performing inservice inspection and testir; activities; d.

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

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

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

I CATAWBA - UNITS 1 & 2 3/4 0-3 Amencment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

3/4.0 APPLICABILITY BASES Specification 3.0.1 through 3.0.4 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.

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

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

g.

g case, conformance to the ACTION requirements provides an acceptable level o f safety for unlimited continued operation as long as the ACTION requirements continue to be met.

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

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

If these actions are not completed within the allowable outage time limits, a shutdown is required i.o 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 removed from service for surveillance testing or investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutdown is required to 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 applicable if the requirements of the Limiting Condition for Operable are not met.

Specification 3.0.2 establishes'that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirement have not been implemented within the specified CATAWBA - UNIfS 1 & 2 8 3/4 0-1 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

APPLICABILITY BASES 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 Limitin'; 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 condition is not specifically addresses 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 (routina) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation.

This time permits the operatord' I

to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

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

This reduces thermal stresses on components of the primary coolant system and the potenti'al for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remecial measures permitting limited continued operation of the facility under the provisions of the ACTION requiren nts are completed, the shutdown may be terminated.

The time limits of the ACTION requirements are applicable l

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

Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required i

actions.

l 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 l

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

operation.

If the plant is in a lower MODE of operation when a shutdown is requireo, 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 r'ach COLD SHUT 00WN, or other applicable l

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 l

time allowed to reach HOT SHUTDOWN is the ney.t 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time l

to reach HOT SHUT 00WN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

l 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 i

operation in less than the total time al, lowed.

CATAWSA - UNITS 1 & 2 B 3/4 0-2 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) l

APPLICABILITY BASES The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

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

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

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

Specification 3.0.4 establishes limitations on MODE changes when a Limiting

. Condition for Operation is not 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 woulde d-i 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 provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

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.

l Specification 3.0.5 delineates the applicability of each specification to j

Unit 1 and Unit 2 operation.

l Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements.

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

l l

"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."

CATAWBA - UNITS 1 & 2 8 3/4 0-3 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) 1

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

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable.

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

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

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

Item a. permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions thatr d' I

may not be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maim enance activities.

Item b.

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

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

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

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

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

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

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

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a, violation of the OPERABILITY CATAWBA - UNITS 1 & 2 8 3/4 0-4 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

l l

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

Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportcble 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 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 Requiru.ents that have not been performed.

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

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

This provision also provides a time w d-

)

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 time limits of the ACTION requirements are applicable at that time.

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

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

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

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 purposa of this specification is to ensure that system and component OPERABILITY requirement; or parameter limits are met before entry into a MODE or condition for which these system, 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.

CATAWBA - UNITS 1 & 2 B 3/4 0-5 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

o APPLICABILITY BASES Syecification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME 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 Vessel Code and applicable Addenda.

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

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

The requirements of Specification 4.0.4 d'

to perform surveillance activities before entry into an OPERATIONAL MODE ore I

other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to i

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable, i

Specification 4.0.6 delineates the applicability of the surveillance l

activities to Unit 1 and Unit 2 operations.

l l

i CATAWBA - UNITS 1 & 2 B 3/4 0-6 Amendment No.48 (Unit 1)

Amendment No.41 (Unit 2)

{

i

f POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT RATIO at least once ner hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2.

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of

"+' M,

g 1, within 30 minutes; 3.

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

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

or greater RATED THERMAL POWER.

c.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

CATAWBA - UNITS.1 & 2 3/4 2-13 c

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hourt; and 3.

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

SURVEILLANCE REQUIREMENTS I

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

a.

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

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

c.

The provisions of Specification 4.0.4 are not applicable.

l l

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble l

locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l l

l CATAWBA - UNITS 1 & 2 3/4 2-14 Amendment No. 48(Unit 1)

Amendment No. 41(Unit 2)

s.

TABLE 3.3-1 n

D REACTOR TRIP SYSTE>iJNSTRUMENTATION 6

MINIMUM cz TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g

1.

Manual Reactor Trip 2

1 2

1,. 2 1

2 1

2 3*, 4*, 5*

10-

.m 2.

Power Range, Neutron Flux a.

High Setpoint 4

2 3

1, 2 2

b.

Low Setpoint 4

2 3

1###, 2 2

3.

Power Range, Neutron F1t,x 4

2 3

1, 2 2

l High Positive Rate w

4.

Power Range, Neutron Flux, 4

2 3

1, 2 2

l High Negative Rate w

E 5 '.

Intermediate Range, Neutron Flux 2

1 2

1###, 2 3

6.

Source Range, Neutron Flux a.

Startup 2

1 2

2##

4 b.

Shutdown 2

1 2

3*, 4*, 5*

10 gg 7.

Overtemperature AT gg Four Loop Operation 4

2 3

1, 2 6

l I

=a 8.

Overpower AT 55 Four Loop Operation 4

2 3

1, 2 6

l zz

??

9.

Pressurizer Pressure-Low 4

2 3

1 6**

l i

l 22 E. E.

ro w E

TABLE 3.3-1 (Continued) 52 REACTOR TRIP SYSTEM INSTRUMENTATION 5

MINIMUM E

TOTAL NO.

C"^.MNELS CHANNELS APPLICABLE

((

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

['

10.

Pressurizer Pressure-High 4

2 3

1, 2 6**

l

' ^*

11.

Pressurizer Water Level-High 3

2 2

1 6

l 12.

Reactor Coolant Flow-Low a.

Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1

6 any oper-

.each oper-ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1

6 l

below P-8) two oper-each oper-us 30 ating loops ating loop u>

O 13.

Steam Generator Water 4/stm 2/stm gen 3/stm gen 1, 2 6**

l

~

Level--Low-Low gen in any each operating operating stm gen sta gen 14.

Undervoltage-Reactor Coolant 4-1/ bus 2

3 1

6 l

pp Pumps (Above P-7) ee i

ELEL 15.

Underfrequency-Reactor Coolant 4-1/ bus 2

3 1

6 l

(! 2 Pumps (Above P-7) ee 2: z 16.

Turbine Trip PP a.

Stop Valve EH Pressure 4

2 3

1####

6 I

- Low b.

Turbine Stop Valve Closure 4

4 1

1####

11 CC EL 5L 17.

Safety Injection Input from ESF 2

1 s 2

1, 2 9

t?t:

s

/

TABLE 3.3-1 (Continued)

TABLE NOTATIONS

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

- Comply with the provitions of Specification 3.3.2, for any portion of the channel required to be OPERABLE by Specification 3.3.2.

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

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

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

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

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

d'

\\

a.

The inop:.rable channel is placed in the tripped coroition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , D.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and c.

Either, THERMAL POWER is restricted tc less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoi..t is reduced to less than o; equel to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADR \\NT "0WER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3 - With the n"mber of e nels OPEPABLE one les. than the Minimum Channels OPEP.ABLE

.s irement and with the THERMAL POWER level:

a.

Oelow the P-6 (Intermediate Range Neutron Flux In+.erlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL P0kiR above the P-6 Setpoint; or b.

Above the P-6 (Intermediate Range Neutron Flux Irterlock)

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

CATAWBA - UNITS 1 & 2 3/4 3-5 A.mendment No.48 (Unit 1)

Amendment No.41 (Unit 2) l.

TABLE 3.3-3 g:

~2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

E MINIMUM C1 TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES p.

-ACTION 1.

Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Ar':a Vantilation Opera-tion, h txiliary Feedwater-Motor-Dr'ven Pump, furge &

Exhaust 1 solation, Annulus Ventilation Operation, Auxiliary Building Filtered t'

Exhaust Opeiation, Emergency Diesel Generater Operation, Y

Component Cooling Water, u;

Turbine Trip, e.nd Nuclear Service Water Operation) a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation 2

1 2

1,2,3,4 14 gg Logic and Actur. tion Relays E"

!h l

c.

Containment 3

2 2

1,2,3 15 lLll Pressure-High zz

?f d.

Pressurizer 4

2 3

1, 2, 3#

19 Pressure-Low

, o.

~m f

7272 e.

Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 EL El Low in any steam line j

03t" t

~,

TABLE 3.3-3 (Continued) 4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRU'ENTATION M

s MINIMUM c:

TOTAL NO.

CHANNELS CHANNELS APPLICABLE 25 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 2.

Containment Spray 4

H e.

a.

Manual Initiation 2

1 2

1,2,3,4 18 ro b.

Automatic Actuation 2

1 2

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

c. ' Containment Pressure-4 2

3 1,2,3 16 High-High R*

3'.

Containment Isolation s.

a.

Phase "A" Isolation tg 1)

Manual Initiation 2

1 2

1,2,3,4 18 2)

Automatic Actuation 2

1 2

1,2,3,4 14 logic and Actuation Relays 3)

Safety Injection See Jtem 1. above for.'ll Safety Injection initiating functions and requirements.

b.

Phase "B" Isolation (Nuclear Service Water Operation) 1)

Manual Initiation 2

1 2

1,2,3,4 18 2)

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays 3)

Containment 4

2 3

1,2,3 16 Pressure-High-High f

F i

.y_

TABLE 3.3-3 (Continued) n D

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION y

e 3.

Containment Isolation (Continued)

,m c.

Purge aad Exhau t Isciation 1)

Manual Initiation 2

1 2

1,2,3,4 17 2)

Automatic Actuation 2

1 2

1,2,3,4 17 Logic and Actuation i

Relays y

s

[

3.)

Safety Injection See Item 1. above for all Safety Injection initiating functions and' requirements.

N 4.

Steam Line Isolation a.

M.sual Initiation gg 1)

System 2

1 2

1,2,3 22 gg 2)

Individual 1/ steam line 1/ steam line 1/operat.ing 1,2,3 23 aa steam line 55 ss b.

Automatic Actuation 2

1 2

1,2,3 21

((

Logic and Actuation pp Relays e o.

c.

Containment Pressure-4 2

3 1,2,3 16

((

High-High d.

Steam Lina Prassure-3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 l

ee Low in any steam j j

g 1ine E

TABLE 3.3-3 (Contir.ued)

Y Et'GINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

2 E

MINIMUM Z

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

{

FUNCTICNAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

,[

4.

Steam Line Isolation (Continued) e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/ steam line 3##

15 l

Negative Rate-High in any steam line S.

Feedwater Isolation a.

Automatic Actuation 2

1 2

1, 2 27 t

Re'says Logic and Actuation

[,

4 4

b.

Steam Generator 4/sta. gen.

2/stm. gen.

3/stm. gen.

1, 2 19 l

Water Level-in any oper-in each oper-High-High (P-14) ating stm.

ating stm.

gen.

c.

T

-Low (P-1 avg l

Interlock) 4 2

3 1, 2 19 5"

d.

Doghouse Water yy Level-High 2

1 2

1, 2 27 EE e.

Safety Injection See Item 1. above for all Safety Injection initiating functions

((

and requirements.

oo 6.

Turbine Trip r=

22 a.

Manual Initiation 1

1 1

1,2 25 oo$$

b.

Automatic Actuation Logic end Actuation 3

w Relays 2

1 2

1,2 27 g

m

'O TABLE 3.3-3 (Continued) n D

ENGINEERED SAFETY FEATl!RES ACTUATION SYSTEM INSTRUMENTATION MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICASLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g

e.

6.

Turbine Trip (Continued)

.m c.

Steam Generator Water Level-High-High (P-14) 4/sta. gen.

2/sta. gen.

3/stm. gen.

1,2 19 in any in each operating stm. operating stm.

gen.

d.

Trip of All Main y'g Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2#

25 e.

Rea.cor Trip (P-4) 2 2

2 1,2,3 22 f.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

7.

Containment Pressure Control System

((

a.

Start Permissive 4/ train 2/ train 3/ train 1, 2, 3, 4 19 b.

Termination 4/ train 2/ train 3/ train 1, 2, 3, 4 19 oo

((

8.

Auxiliary Feedwater

??

a.

Manual Initiation 1/ train 1/ train 1/ train 1,2,3 26 w co gg b.

Automatic Actuation Logic 2

1 2

1,2,3 21 o o,,

and Actuatior Relays se UU

TABLE 3.3-3 (Continued) 52 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5>

E MINIMUM El TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

}

8.

Auxiliary Feedwater (Continued) c.

Stm. Gen. Water Level-Low-Low

1) Start Motor-Driven Pumps 4/ete. gen.

2/sta, gen.

3/stm. gen.

1,2,3 19 l

in any opera-in each ting stm. gen. operating

}{

stm. gen.

T

2) Start Turbine-l E!

~

Driven Pump 4/stm. gen.

2/stm. gen.

3/sta. gen.

1,2,3 19 in any two in each operating operating stm. gen.

stm. gen.

d.

Safety Injection-pg Start Motor-Driven Pumps See Item 1. above for all Safety Injection initiating functions 3m and requirements.

SE M2 e.

Loss-of-Of fsite Power-E' 5' Start Motor-Driven 2: z Pumps and Turbine-Driven P?

Pump 6-3/ bus 2/ bus 2/ bus 1,2,3 15 1

either bus

- co 7E72 f.

Trip of All Main

3. 3.

Feedwater Pumps-Start Motor-j E3tj Driven Pumps 2/ pump 1/ pump 1/ pump 1, 2#

25 E

m mM-v

TAB!E 3.3-3 (Continued) n ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5>

c MINIMUM 3

TOTAL NO.

CHANNELS CHANNELS APPLICABLE d

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 8.

Auxiliary Feedwater (Coritinued) to g.

Auxiliary Feedwater Suction Pressure-Low

1) CAPS 5220, 5221, 3/ pump 2/ pump 2/ pump 1,2,3 15 5222

2) CAPS 5230, 5231, 5232 3/ pump 2/ pump 2/ pump 1,2,3 15 9.

Containment Sump q

Recirculation a.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation 4

Relays b.

Refueling Water Storage Tank Level-Low 4

2 3

1,2,3,4 1G Coincident With Safety Injection See Item 1. above for all Safety Injection initiating functions and gg requirements.

((

10.

Loss of Pmeer

!3 l

a.

4 kV Bus Undervoltage-3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 15 55 Loss of Voltage EE b.

4 kV Bus Undervoltage-

((

Grid Degraded Voltage 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 15 11.

Control Room Area jy Ventilation Operation 33 3

Automatic Actuation Logic 33 ana Actuation Relays 2

1 3

2 All 24 E

TABLE 3.3-3 (Continued) g Y

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5

E MINIMUM Z

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

]

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 11.

Control Room Area Ventilation Operation (Continued) l b.

Loss-of-Offsite Power 3

2 2

1,2,3 15 c.

Safety Injection See Item 1. above for all Safety Injections initiating functions and requirements.

12.

Containment Air Return and Hydrogen Skimmer Operation wy.

w a.

Manual Initiation 2

1 2

1,2,3,4 18 a

b.

Automatic Actuation Logic and Actuation Relays 2

1 2

1,2,3,4 14 c.

Containment Pressure-High-High 4

2 3

1,2,3 16 FF 13.

Annulus Ventilation Operation EE a.

Manual Initiation 2

1 2

1,2,3,4 18 EE b.

Automatic Actuation Logic yy and Actuation Relays 2

1 2

1,2,3,4 14 c.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

mm55 14.

Nuclear Service Water Operation S

nw a.

Manual Initiation 2

1 2

1,2,3,4 18 b.

Automatic Actuation Logic and Actuation Relays 2

1 2

1,2,3,4 21

TABLE 3.3-3 (Continued) 9

--e ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

,z MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION y

e-14.

Nuclear Service Water Operation

,m (Continued) l c.

Loss-of-Offsite Power 3

2 2

1,2,3 15 d.

Containment Spray See Item 2. above for all Containment Spray initiating functions and requirements.

e.

Phase "B" Isolation See Item 3.b. above for all Phase "B" Isolation initiating functions and requirements.

f.

Safetj I.;jection See Item 1. above for all Safety Injection initiating functions and requirements.

m h

g.

Suction Transfer-Low Pit Level 2

1 2

1,2,3,4 21 15.

Emergency Diesel Generator Operation (Diesel Building Ventilation Operation, Nuclear Service Water Operation) kk a.

Manual Initiation 2

1 2

1,2,3,4 18 55 b.

Automatic Actuation Logic 55 and Actuation Relays 2

1 2

1,2,3,4 21

((

c.

Loss-of-Offsite Power 3

2 2

1,2,3,4 15 gg d.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

16.

Auxiliary Building Filtered Exhaust Operation j

00

~

a.

Manual Initiation 2

1 2

1,2,3,4 18 L

b.

Automatic Actuation Logic and Actuation Relays 2

_1 2

1,2,3,4 21

g..

TABLE 3.3-3 (Continued)

TABLE NOTATIONS

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

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

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

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided thp d.

)

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

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and t u Minimum Channels OPERABLE requirement is met.

One additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

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

t ACTION 18 - With the number of OPERABLE channels one 1 css than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY i

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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

h.

The inoperable channel is placed in the tripped condition I

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for sur-i veillance testing of other channels per Specification 4.3.2.1.

CATAWBA - UNITS 1 & 2 3/4 3-25 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

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

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

~

a.

With a radiation monitoring channel Alarm / Trip Setpoint for plar.t operations 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, d'

b.

With one or more radiation monitoring channels for plant operatio&f I

inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

f 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations l

sha'l be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

i t

CATAWBA - UNITS 1 & 2 3/4 3-51 Amendment No. 48 (Unit 1) l Amendment No. 41 (Unit 2)

I

TABLE 3.3-6 RADIATIONMONITORINGINSTRUMENTATf0NFORPLANTOPERATIONS I

MINIMUM i

g CHANhtLS CHANNELS APPLICABLE ALARM / TRIP FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION g

~

1 Containment e

a. Containment Atmosphere - High 1

1 All N

30 Gaseous Radioactivity (Low Range - EMF-39)

b. Reactor Coolant System Leakage Detection

1) Particulate Radioactivii.y R

(Low Range - EMF-38)

N.A.

1 1,2,3,4 N.A.

33

+

2) Gaseous Radioactivity y

(Low Range - EMF-39)

N.A.

1 1,2,3,4 N.A.

33 g

.,2.

Fuel, Storage Pool Areas

a. High Gaseous Radioactivity 1

(Low Range - EMF-42) 1 1

5 1.7x10 4 pCi/ml 34 i

b. Criticality-Radiation Level (Fuel Bridge - Low Range -

IEMF-15, 2 EMF-4) 1 1

< 15 mR/h 32 3.

Control Room Air Intake-Radiation Level -

1/ intake 2 (1/in-All

< 1.7x10 4 pCi/ml 31 High Gaseous Radioactivity take)

~

(Low Range - EMF-43 A & B) 4.

Auxiliary Building Ventilation 1

1 1,2,3,4 5 1.7x10 4 pCi/ml 35 High Gaseous Radioactivity (Low Range - EMF-41) 5.

Component Cooling Water System h

(EMF-46 A&3) 1 1 g All 5 1x10 3 pCi/a1 36

.-V INSTRUMENTATION H0VA8LE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

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

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

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

a.

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

Monitoring the QUADRANT POWER TILT RATIO, or w-d' c.

Measurement of F H, and F (Z) q ACTION:

With the Movable Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at l

least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by irradiating each detector used and determining the acceptability of its voltage curve for:

a.

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

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFh,andF(Z).

c.

9 l

l l

CATAWBA - UNITS 1 & 2 3/4 3-55 Amendment No. 48 (Unit 1)

I Amendment No. 41 (Unit 2) l

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

l APPLICABILITY: At all times.

ACTION:

a.

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

The nrovisions of Specification 3.0.3 are not applicable.

.. d -

\\

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

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

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

Data retrieved from the triaxial time-history accelerograph shall include a post-event CHANNEL CALIBRATION obtained by actuation of the internal test and calibrate function immediately prior to removing data.

CHANNEL CALIBRATION shall be performed immediately after insertion of the new recording media in the triaxial time-history accelero-graph recorder.

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

CATAWBA - UNITS 1 & 2 3/4 3-56 Amendment No. 48 (Unit 1) 1 Amendment No. 41 (Unit 2) l l

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

APPLICABILITY:

At all times.

ACTION:

a.

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

The provisions of Specification 3.0.3 are not applicable.

,..d>

\\

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

CATAWBA - UNITS 1 & 2 3/4 3-59 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) n

o 3..

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT' LOCATION OPERABLE 1.

Wind Speed a.

Meteorological Tower Nominal Elev. 661'10" I

b.

Meteorological Tower Nominal Elev. 768'10" 1

2.

Wind Direction a.

Meteorological Tower Nominal Elev. 661'10" 1

~ ~ ~

b.

Meteorological Tower Nominal Elev. 768'10" 1

3.

Air Temperature - AT Meteorological Tower Nominal Elev. 768'10"-661'10" 1

.u

G CATAWBA - UNITS 1,,& 2 3/4 3-60 s.

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

APPLICABILITY:

All MODES.

ACTION:

a.

With one Chlorine Detection System iroperable, restore the incperable system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the Control Room Area Ventilation System with flow through the HEPA filters and activated carbon adsorbers, b.

With both Chlorine Detection Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the Control Room Area

'**d' I

Ventilation System with flow through the HEPA filters and activated carbon adsorbers.

SURVEILLANCE REQUIREMENTS 4.3.3.7 Each Chlorine Detection System shall be demonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an ANALOG CHANNEL l

OPERATIONAL TEST 'at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

l

\\

l I

l CATAWBA - UNIT 1 & 2 3/4 3-70 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

h, ;,, e INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY:

Whenever equipment protected by the fire detection instrument Ts required to be OPERABLE.

ACTION:

a.

With any, but not more than one-half the total in any fire zone, Function A fire detection instruments shown in Table 3.3-11 inoperable, restore the inoperable instrument (s) to OPERABLE status within 14 days or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

d-m.

I b.

With more than one-half of the Function A fire detection instruments in any fire zone shown in Table 3.3-11 inoperable, or with any Fun: tion B fire detection instruments shown in Table 3.3-11 inoperable, or with any two or more adjacent fire detection instruments shown in Table 3.3-11 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the contain-ment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specificot. ion 4.6.1.5.

c.

The provisions of Specification 3.0.3 are not applicable.

SjJRVEILLANCEREQUIREMENTS 4.3.3.8.1 Each of the abc o required smoke detection or flame detection instru-ments which are accessibl. during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.

Detectors which are rot accessible during plant operation shall be demon-strated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.2 Each of the nove required heat detection instruments shall be demon-strated OPERABLE as fo'.aws:

a.

For nonrestorable spot-type detectors, at least two detectors out of every hundred, or fraction thereof, shall be removed every 5 years and functionally tested.

For each failure that occurs on the detectors remov'rd, two additional detectors shall be removed and tested; and CATAWBA - UNIT 1 & 2 3/4 3-71 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

4 INSTRUMTxTATION' FIRE DETECTION INSTRUMENTATION SURVEILLAkiE REQUIREMENTS (Continued) b.

For restorable spot-type heat detectors, at least one detector on each signal initiating circuit shall be demonstrated OPERABLE at least once per 6 months by performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST.

Different detectors shall be selected for each test.

Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a TRIP ACTUATING DEVICE OPERATIONAL TEST during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.3.8.3 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

w e6 -

\\

g CATAWBA - UNITS 1 & 21 3/4 3-72

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

APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With one or more Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

Ek '

.n=

\\

S RVEILLANCE REQUIREMENTS 4.3.3.9 Each channel of the Loose-Part Detection Systems shall be demonstrated OPERABLE by performance of:

a.

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

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

A CHANNEL CALIBRATION at least once per 18 months.*

This surveillance need not be performed until prior to entering STARTUP following the Unit 1 first refueling.

(This applies to Unit 1 only.)

CATAWBA - UNITS 1 & 2 3/4 3-79 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Snecification 3.11.1.1 are not exceeded.

The Alarm /

Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY:

At all times.

ACTION:

~

a.

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

,..d-i b.

With less than the minimum nunber of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specifica-tion 6.9.1.7 why this inoperability was not corrected within the time specified.

c.

Tie provisions of Specification 3.0.3 are not applicable.

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

l l

L CATAWBA - UNITS 1 & 2 3/4 3-80 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING C0hDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.

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

APPLICABILITY:

As shown in Table 3.3-13.

ACTION:

a.

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

" j, channel inoperable.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected within the time specified.

c.

The provisions of Specification 3.0.3 are not applicable.

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

CATAWBA - UNITS 1 & 2 3/4 3-85 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

TABLE 3.3-13 g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

=

MINIMUM CHANNELS E

INSTRUMENT OPERABLE APPLICABILITY ACTION

~-.

[

1.

WASTE GAS HOLDUP SYSTEM I

a.

Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release (Low Range - EMF-50)

I per station 45 b.

Effluent System Flow Rate Measuring Device 1 per station 46 w

2.

WASTE GAS HOLDUP SYSTEM Explosive Gas 1

Monitoring System a.

Hydrogen Monitors 1/ train per station S1 b.

Oxygen Monitors 2/ train per station 49 3.

Condenser Evacuation System Noble Gas 1

1,2,3,4 47 Activity Monitor (Low Range - EMF-33) 4.

Vent System a.

Noble Gas Activity Monitor 1

47 (Low Range - EMF-36) b.

Iodine Sampler (EMF-37) 1 S0 c.

Particulate Sampler (EMF-35) 1 S0 d.

Flow Rate Monitor 1

46 f

e.

Sampler Flow Rate Monitor 1

46 5-

INSTRUMENTATION 3/4.3.3.12 BORON DILUTION MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.12 As a minimum, two trains of the Boron Dilution Mitigation System shall be OPERABLE and operating with Shutdown Margin Alarm ratios set at less than or equal to 4 times the steady-state count rate.

APPLICABILITY:

MODES 3, 4, AND 5#

ACTION:

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

(2) verify two Source Range Neutron Flux Monitors are OPERABLE wt'th d' i

I Alarm Setpoints less than or equal to one-half decade above the F

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

(b) With both trains of the Boron Oilution Mitigation System inoperable or not operating, restore the inoperable trains to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or (1) suspend all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or l

(2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade above the steady-state cour.t rate and verify that the combined flow rate I

from both Reactor Makeup Water Pumps is less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) within the next hour.

SURVEILLANCE REQUIREMENTS 4.3.3.12.1 Each train of the Boron Dilution Mitigation System shall be demon-l strated OPERABLE by performance of:

l l

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

Not applicable for Unit 2 until after entering Mode 2 followng the first I

refueling outage.

{

CATAWBA - UNITS 1 & 2 3/4 3-92a Amendment No.48(Unit 1)

Amendment No.41(Unit 2)

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

APPLICABILITY:

All MODES.

ACTION:

a.

With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Ructor Coolant System temperature more than 50 F above the minimum temperature required by NDT considerations.

With the structural integrity of any ASME Code Class 2 component (s) j.

b.

not conforming to the above requirements, restore the structural *'

\\

integrity of the affected component (s) to within its limit or 'solate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.

c.

With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

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

l I

i CATAWBA - UNITS 1 & 2 3/4 4-39 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

L

n I

h-REACTOR COOLANT SYSTEM

-3/4.4.11 REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one Reactor Coolant System vent path consisting of at least

-two valves in series powered from emergency buses shall be OPERABLE and closed

at each of the following-locations:

a.

Reactor Vessel head b.

Pressurizer steam space a

APPLICABILITY: Modes 1, 2, 3 and 4 ACTION:

a.

With one of the above Reactor Coolant System vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve acbmand-I tor of all the valves in the inoperable vent path; restore the inoper-able vent path to OPERABLE status within 30 days or be in HOT STAN08Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With both of the above Reactor Coolant System vent paths inoperable, maintain the inoperable vent paths closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.11 Each Reactor Coolant System vent path shall be demonstrated OPERABLE at least once per 18 months by:

a.

Verifying all manual isolation valves in each vent path are locked in the open position, and b.

Cycling each valve in the vent path throtgh at least one complete cycle of full travel from the control room during C0LO SHUTOOWN or REFUELING.

a "For the plants using power operated relief valve (PORV) as a vent path, PORV block is not required to be closed if the 90RV is operable.

s CATAWBA - UNITS 1 & 3.

3/4 4-40

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

' APPLICABILITY:

At all times.

ACTION:

a.

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

1.

Decontaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Comission ta-d' i

Regulations.

b.

The provisions of Specification 3.0.3 are not applicable.

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

a.

The licensee, or b.

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

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

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

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

1)

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

and 2)

In any form other than gas.

CATAWBA - UNITS 1 & 2 3/4 7-25 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Stored sources not in use - Each sealed soLrce and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months.

Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use; and Startup sources and fission detectors - Each sealed startup source c.

and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

457[9.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcurie of removable contamination.

c' 9 -

.s CATAWBA - UNITS 1 &' 2 3/4 7-26

PLANT SYSTEMS s

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

At least two fire suppression pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header, and b.

An OPERABLE flow path capable of taking suction from Lake Wylie and transferring the water through distribution piping with OPERABLE sectionalizing control valves and isolation valves for each sprinkler, hose standpipe, or Spray System riser required to be OPERABLE per Specifications 3.7.10.2 and 3.7.10.4.

APPLICABILITY:

At all times.

d-n.

I ACTION:

a.

With one of the above required pumps and/or one Water Supply /Distri-bution System inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply.

The provisions of Specification 3.0.3 are not applicable, b.

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

l t

CATAWBA - UNITS 1 & 2 3/4 7-27 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) j l

L

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.10.1 The Fire Suppression Water System shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by starting each electric motor-driven pump and operating it for at least 15 minutes on recirculation flow, b.

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

At least once per 6 months by performance of a system flush of the outside distribution loop to verify no flow blockage by fully opening the hydraulically most remote hydrant, d.

At least once per 12 months by cycling each testable va:/e in the flow path through at least one complete cycle of full travel, At least once per 18 months by verifying that each valve (manual, "

e.

N power-operated, or automatic) in the flow path which is inaccessible during plant operations is in its correct position, f.

At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and:

1)

Verifying that each automatic valve in the flow path actuates to its correct position, 2)

Verifying that each pump develops at least 2500 gpm at a net pressure of 144 psig by testing at three points on the pump performance curve, 3)

Cycling each valve in the flow path that is not testable during l

plant operation through at least one complete cycle of full l

travel, and 4)

Verifying that each fire suppression pump starts within 10 psig of its intended starting pressure (A pump, primary switch-95 psig; B pump, primary switch-90 psig; and C pump, primary switch-85 psig).

g.

At least once per 3 years by performing a flow test of the system in accordance with Chapter 8, Section 16 of the Fire Protection Handbook, 15th Edition, published by the National Fire Protection Association.

l CATAWBA - UNITS 1 & 2-3/4 7-28

PLANT SYSTEMS CO SYSTEMS 2

LIMIIING CONDITION FOR OPERATION 3.7.10.3 The following High Pressure and Low Pressure C02 Systems shall be OPERABLE:

a.

Low Pressure C02 System - Diesel generator rooms, and b.

High Pressure C02 System - Auxiliary feedwater pump rooms.

APPLICABILITY: Whenever equipment protected by the CO2 Systems is required to be OPERABLE.

ACTION:

a.

With one or more'of the above required C0 2 Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly.. d-

)

fire watch patrol.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.3.1 Each of the above required CO2 Systems shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.

4.7.10.3.2 Each of the above required Low Pressure CO 2 Systems shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying the CO2 storage tank level to be greater than 44% of full capacity, and b.

At least once per 18 months by verifying:

1)

Each system actuates rpinually and automatically, upon receipt of a simulated actuatior, signal, 2)

Damper closure devices receive an actuatien signal upon system operation, and 3)

By a visual inspection of discharge nozzles to assure no blockage.

CATAWBA - UNITS 1 & 2 3/4 7-31 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) i

o PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.10.3.3 Each of the above required High Pressure CO2 Systems shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying the weight uf each CO2 storage cylinder to be at least 90% of full charge weight, and b.

At least once per 18 months by:

1)

Verifying each system actuates manually and automatically upon receipt of a simulated actuation signal, 2)

Verifying that damper closure devices receive an actuation signal upon system operation, and 3)

A visual inspection of the discharge nozzles to assure no blockage.

%% d' g

i l

l l

N CATAWBA - UNITS 1-& 2 3/4 7-32

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.10.4 The rire hose stations given in Table 3.7-3 shall be OPERABLE.

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

ACTION:

a.

W3th one or more of the fire hose stations given in Table 3.7-3 inoperable, provide gated wye (s) cn the nearest OPERABLE hose station (s).

One outlet of the wye shall be connected to the standard length of hos? provided for the hose station.

The seccnd outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.

Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to station personnel, plant equipment, or the hose itself, the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station.

Signs shall be mounted above the gated wye (s) to identif9 I

the proper hose to use.

The above ACTION requirement shall be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.4 Each of the fire hose stations given in Table 3.7-3 shall be demonstrated OPERABLE:

a.

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

At least once per 18 months, by:

1)

Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, 2)

Removing the hose for inspection and reracking, and 3)

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

c.

At least once per 3 years, Ly:

1)

Partially opening each hose station valve to verify valve l

OPERABILITY and no flow blockage, and 2)

Conducting a hose hydrostatic test at a pressure of 200 psig or at least 50 psig above maximum fire main operating pressure, l

whichever is greater.

CATAWBA - UNITS 1 & 2 3/4 7-33 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

TABLE 3.7-3 FIRE HOSE STATIONS LOCATION ELEVATION HOSE RACK #

1.

Auxiliary Building 59, FF 522+0 1RF235 55, FF 522+0 1RF248 63-64, KK 543+0 1RF210 63, MM 543+0 1RF211 60, MM 543+0 1RF212 58, PP 543+0 1RF218 59, GG-HH 543+0 1RF236 60-61, FF-GG 543+0 1RF237 3, CC 543+0 1RF238 57, JJ 543+0 1RF242

'~

54-55, GG 543+0 1RF249 57,FF 543+0 1RF250 52-53, GG 543+0 1RF2S5 51, CC 543+0 1RF256 50-51, JJ-KK 543+0 1RF262 e un'

't 53, m 543+0 1RF268 50-51, NN 543+0 1RF271 62, MM-NN 560+0 1RF203 63, JJ-KK 560+0 1RF213 58, PP 560+0 1RF219 56, NN 560+0 1RF220 59, HH 560+0 1RF239 57, KK 560+0 1RF243 54-55, FF-GG 560+0 1RF251 51, KK 560+0 1RF263 52, MM-NN 560+0 1RF269 58, BB 554+0 1RF484 65, BB-CC 560+0 1RF485 62, AA-BB 560+0 1RF486 56, BB 554+0 1CF487 52, AA-BB 560+0 1RF488 49, BB-CC 560+0 1RF489 68-69, BB 560+0 1RF996 45-46, BB 560+0 1RF997 63, NN 577+0 1RF204 61, LL 577+0 1RF214 63, KK-LL 577+0 1RF215 58, PP 577+0 1RF221 59, JJ 577+0 1RF230 58, GG 577+0 1RF240 56, KK 577+0 1RF244 54, GG 577+0 1RF252 52-53, KK 577+0 1RF258 51, KK 577+0 1RF264 51-52, NN 577+0 1RF272 56, PP 577+.0 1RF278 68-69, BB

'57740 1RF478 CATAWBA - UNITS I-& 2 3/4 7-34

i TABLE 3.7-3 (Continued)-

FIRE HOSE STATIONS 3

l LOCATION ELEVATION HOSE RACK #

65, 88-CC 577+0 1RF479 59, 00 574+0 1RF480 60, AA 574+0 1RF431 i

49, BB-CC 577+0 1R/490 i

45, 88 577+0 1RF491 55, 00 574+0 1RF492 54, AA 574+0 1RF493 63, AA 577+0 1RF993

)

51, AA 577+0 1RF998 62, NN 594+0 1RF205 57, M 594+0 1RF222 63, JJ 594+0 1RF231 57, HH 594+0 1RF245 57, EE 594+0 1RF253 4

51, JJ 594+0 1RF259 52, NN 594+0 1RF275 64, 28 594+0 1RF984 e *-

V 50, 88 594+0 1RF985 51, XK 605+10 1RF265 63, JJ 605+10 1RF233 63-64, M 031+6 1RF483 50-51, MM 631+6 1RF495 2.

Fuel Pools 65, TT-UU 605+10 1RF208 48, TT-UU 605+10 1RF276 63-64, M 605+10 1RF482 50-51, MM 605+10 1RF822 3.

Nuclear Service Water Pep Structure East Section 600+0 1RF939 Wast Section 600+0 1RF940 4

I l

CATAWBA-UNITSJ.&2 3/4 7-35

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

APPLICABILITY:

At all times.

. ACTION:

~

With one or more of the above required fire barrier penetrations a.

and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either establish a ccntinuous fire watch on at ' east one side of che affected pene-tration, or verify the OPERADI.ITY of fire detectors on at least one side of W inoperable penetration and establish an hourly fire watch patrol.

+

'8 '

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11.1 At 'least once ?sr 18 months the above required fire barrier penetrations and sealirg devices shall be verified OPERABLE by performing a visual inspection of:

a.

The exposed surfaces of each fire rated assembly; b.

At least 10% of all fire dampers.

If apparent changes in appearance or abnormal degradation are found, a visual inspection of an additional 10% of the dampers shall be made.

This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.

Samples shall be selected such that each fire damper will be inspected every 15 years; and c.

At least 10% of each type of sealed penetration.

If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10%.i tach type of sealed penetration shall be made, j

This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.

Samples shall be selected such that each penetration seal wfil be inspected every 15 years, t

CATAWBA - UNITS 1 & 2 3/4 7-36 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) i l

REFUELING OPERATIONS

=-

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITIN3 CONDITION FOR OPERATION j.

t 3.9.7 Loads in excess of 3000 pounds

shall be prohibited from travel over fuel assemblies in the storage pool.

t, APPLICABILITY:

With fuel assemblies in the storage pool.

ACTION:

a.

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

The provisions of Specification 3.0.3 are not applicable, b.

d' n.

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

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

i CATAWBA - UNITS 1 & 2 3/4 9-9 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) l l

c _ 7 REFUELING OPERATIONS 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At laast one residual heat removal loop shall be OPERABLE and in operation.*

APPLICABILITY:

MODE 6, when the water level above the top of the reactor i

vessel flange is greater than or equal to 23 feet.

ACTION:

With no residual heat removal loop CPERABLE and in operation, suspend all operations involving a,n increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate' corrective action to return the required residual heat removal loop to OPERABLE and operating status as soon as possible.

Close all containment penetration e' D

providing direct access from the containment atmosphere to the outside atmos-phe,re within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one residual heat removal loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 3000 gpm at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l l

l "The residual heat removal loop'may be removed from operation for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months l

per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.

CATAWBA - UNITS 14 2 3/4 9-10

< a:

~-

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

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

ACTION:

a.

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

The provisions of Specification 3 0.3 are not applicable.

...d-

\\

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

CATAWBA - UNITS 1 & 2 3/4 9-13 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

{

w REFUELING OPERATIONS 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM LIMITING CONDITION FOR OPCRATION 3.9.11 At least one train of the Fuel Handling Ventilation Exhaust System shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a.

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

The provisions of Specification 3.0.3 are not applicable.

..d-I I

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

4.9.11.2 Both trains of the Fuel Handling Ventilation Exhaust System shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating, from the control room, flow through the HEPA filters and activated carbon adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; b.

At least once per 18 months or (1) af ter any structural maintenance on the HEPA filter or activated carbon adsorber housings, or (2) fol-lowing painting, fire, or chemical release in any ventilation zone communicating with the system by:

1)

Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test procedure guidance in Regulatory Positions C.S.a. C.S.c, and C.S.d* of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 16,565 cfm i 10%;

The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with heaters on and operating.

CATAWBA - UNITS 1 & 2 3/4 9-14 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

m h

RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:

a.

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

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

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.

3-

)

submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed correctivJ actions to be taken to assure that subsequent releases will be in compliance with the above limits.

This Special Report shall also include:

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

b.

The provisions of Specification 3.0.3 are not applicable.

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

"The requirements of ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within 3 miles downstream of

-i the plant discharge.

CATAWBA - UNITS 1 & 2 3/4 11-5 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

a l

RADI0 ACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION F0k OPERATION 3.11.3.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the. projected doses due to the liquid effluent, from each unit, to UNRESTRICTED f.WEAS (see Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged withguts-

)

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

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

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

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Liquid Radwaste Treatment Systems are not being fully utilized.

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

CATAWBA - UNITS 1 & 2 3/4 11-6 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each temporary unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable, so.

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

't CATAWBA - UNITS 1 & 2 3/4 11-7 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

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

A 264

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

Aj = pond inventory limit for single radionuclide "j", in Curies; C3 = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", microcuries/ml; V = design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microCuries/ Curie per milliliter / gallon.

APPLICABILITY:

At all times.

I j

ACTION:

[

a.

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

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.5 The quantity of radioactive material contained in each batch of resin / water slurry to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative 7, ample of the batch to be transferred to the chemical treatment ponds and shall be limited by the expression:

I

< 0.006 j C 3

Where:

c) = radioactive resin / water slurry concentration for radionuclide "j" entering the UNRESTRICTED AREA chemical treatment ponds, in microcuries/ milliliter; and i

C) = 10 CFR Part 20, Appendix B, Table II, Column 2, concentration for single radionuclide "j", in microcuries/ milliliter.

CATAWBA - UNITS 1 & 2 3/4 11-8 Amendment No. 43 (Unit 1)

Amendment No. 41 (Unit 2)

RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 5.1-4) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and b.

During any calendar year:

Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY:

At all times.

ACTION a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit tg. g, g

the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above

limits, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

CATAWBA - UNITS 1 & 2 3/4 11-13 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

l

,.3 RADI0AtTIVE EFFLUENTS DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE B0UNDARY (see Figure 5.1-4) shall be limited to'the following:

a.

During any calendar quarter:

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

During any calendar year:

Less than or equal to 15 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of Iodine-131, Iodine-la3,d -

)

tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

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

CATAWBA - UNITS 1 & 2 3/4 11-14 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

/

i RADIOACTIVE EFFLUENTS GASEOUS RA0 WASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLOUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1-4) would exceed either:

a.

0.2 mrad to air from gamma radiation, or b.

0.4 mrad to air from beta radiation, or c.

0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY:

At all times.

ACTION:

With radioactive gaseous waste being discharged without treatment, g.

a.

g 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 t'nat includes the following information:

1.

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

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

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

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOU40ARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLOUP SYSTEM shall be considered OPERABLE by meeting Specification 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

l l

l CATAWBA - UNITS 1 & 2 3/4 11-15 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2) l t-

i; RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal 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 greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , b.

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

.d-

\\

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and 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 hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.

4 CATAWBA - UNITS 1 & 2 3/4 11-16 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

_7

RADI0 ACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 97,000 Curies of noble gases (con-sidered as Xe-133 equivalent).

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 describe the events leading to this condition in the next Semiannual Padioactive Effluent Release Report pursuant to Specification 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable.

.d-

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SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage 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.

CATAWBA - UNITS 1 & 2 3/4 11-17 Amendment No.48 (Unit 1)

Amendment No.41 (Unit 2)

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTES LIMITING CONDITION FOR OPERATICN 3.11.3 Radioactive wastes shall be solidified or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY:

At all times.

ACTION:

a.

With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the Solid Radwaste System as necessary to pre-vent recurrence.

b.

With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAA, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent" d' recurrence.

c.

1he provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM:

a.

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

SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; b.

If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each i

consecutive batch of the same type of wet waste until at least three consecutive ir.itial test specimens demonstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and c.

With the installed equipment incapable of meeting Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for' contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.

CATAWBA - UNITS 1 & 2 3/4 11-18 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY:

At all times.

ACTION:

a.

With the calc 4'Eted doses from the release of radioactive materials in liquid or m eus effluents exceeding twice the limits of Specifi-cation 3.11.3

, 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a.,

or 3.11.2.3b., n iculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to f Mken to reduce subsequent d '

i releases to prevent recurre' ice of exce C w the above limits and includes the schedule for achieving con.T ice with the above limits.

This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is gr+. ted until staff action on the request is complete, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units i

and from radwaste storagi tanks shall be determined in accordance with the l

methodology and parameters in the 00CM.

This requirement is applicable only l

under conditions set forth in ACTION a. of Specification 3.11.4.

l CATAWBA - UNITS 1 & 2 3/4 11-19 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

RADIOLOGICAL ENVIRONMENTAL M0_NITORING LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12 1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given-in the ODCM.

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

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report. documentation for e change in the 00CM including a revised figure (s) and table for the ODCM reflecting the new loca-tion (s) with supporting information identifying the cause of the unavailability of samples and justifying the selectioa of the new i

location (s) for obtaining samples, d.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

...d.

i 4.12.1 The radiological environmental monitoring samoles shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

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I CATAWBA - UNITS 1 & 2 3/4 12-2 Amendment No.48 (Unit 1)

Amendment No.41 (Unit 2)

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

of greater than 50 m2 2

(500 ft ) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a.

With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new loca-tion (s) in the next Semiannual Radioactive Effluent Release Report pursuant to' Specification 6.9.1.7.

s b.

With a Land Use Census identifying a location (s) that yields a calculateddoseordosecommitment(viathesameexposurepathwayl,g.

)

20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.

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

Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the 00CM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s), with information supporting the change in the sampling locations.

c.

The provisions of Specification 3.0.3 are not applicable.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/Qs in lieu of the garden census.

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

CATAWBA - UNITS 1 & 2 3/4 12-13 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

i RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

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A CATAWBA - UNITS 1-& 2 3/4 12-14 i

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission, that correspond to samples required by Table 3.12-1.

APPLICABILITY:

At all times.

ACTION:

a.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

4 b.

The provisions of Specification 3.0.3 are not applicable.

r

_ SURVEILLANCE REQUIREMENTS l

..s-i I

4.12.3 The Interiaboratory Comparison Program shall be described in the ODCH.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

i CATAWBA - UNITS 1 & 2 3/4 12-15 Amendment No. 48 (Unit 1)

Amendment No. 41 (Unit 2)

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ML20151A446

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