Text

Application for Technical Specification Change Re Mode Change Limitations and Adoption of a Technical Specification Surveillance Requirement 3.0.1 and Associated Bases, Using the Consolidated Line Item Improvement Process
	ML032471660
Person / Time
Site:	Cook
Issue date:	08/27/2003
From:	Powers R; Indiana Michigan Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	AEP:NRC:3304
	Download: ML032471660 (247)
	v • d • e

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER August 27, 2003 AEP:NRC:3304 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001

SUBJECT:

Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 Application for Technical Specification Change Regarding Mode Change Limitations, and Adoption of a Technical Specifications Bases Control Program and Standard Technical Specification Surveillance Requirement 3.0.1 and Associated Bases, Using The Consolidated Line Item Improvement Process

Dear Sir or Madam:

In accordance with the provisions of 10 CFR 59.90, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, is submitting a request for an amendment to the Technical Specifications (TS) of Facility Operating Licenses DPR-58 and DPR-74.

The changes are consistent with Nuclear Regulatory Commission (NRC) approved industry/Technical Specification Task Force (TSTF) standard technical specification change TSTF-359, Revision 8, as modified by the notice in the Federal Register published on April 4, 2003 (Incorporated into TSTF-359, Revision 9, which was approved by the NRC on May 12, 2003). That Federal Register notice announced the availability of this TS improvement through the consolidated line item improvement process (CLIIP).

The proposed amendment would modify TS requirements for mode change limitations in Specification 3.0.4 and Specification 4.0.4. Changes to TS pages that are affected by the changes to TS 3.0.4 and TS 4.0.4 (i.e., those that refer or will refer to the revised TS) are also proposed. In conjunction with the proposed change, TS requirements for a bases control program consistent with the TS Bases Control Program described in Section 5.5 of the Westinghouse Standard Technical Specifications (STS), and adoption of STS SR 3.0.1 (CNP TS 4.0.1) and its associated bases are also being proposed.

U. S. Nuclear Regulatory Commission AEP:NRC:3304 Page 2 Additionally, I&M proposes format changes to the affected TS pages that improve appearance but do not introduce other changes. provides an affirmation pertaining to this letter. Enclosure 2 provides a description of the proposed change (including a table of affected TSs with a brief description of the change), the requested confirmation of applicability, and plant-specific verifications. Attachment la provides the existing Unit 1 TS pages marked up to show the proposed change.

Attachment lb provides the existing Unit 2 TS pages marked to show the proposed change. Attachment 2a provides the revised Unit 1 TS pages. b provides the revised Unit 2 TS pages. Attachment 3 provides a summary of the regulatory commitments made in this submittal.

I&M requests Nuclear Regulatory Commission (NRC) review and approval in accordance with normal NRC review schedules for this type of request. I&M requests a 45-day implementation period following approval.

I&M submittal AEP:NRC:3403, dated August 27, 2003 impacts pages that are included in this submittal. I&M will coordinate changes to the pages with the NRC Project Manager to ensure proper TS page control when the associated license amendment requests are approved.

Copies of this letter and its attachments are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality, in accordance with the requirements of 10 CFR 50.91.

Should you have any questions, please contact Mr. Brian A. McIntyre, Manager of Regulatory Affairs, at (269) 697-5806.

Sincerely, E ViPowers Executive Vice President RV/rdw

U. S. Nuclear Regulatory Commission AEP:NRC:3304 Page 3

Enclosures:

I. Affirmation

2. Application for Amendment, License Amendment Request to Revise Technical Specifications 3.0.4 and 4.0.4 Attachments:

1a. Unit 1 Technical Specifications Pages Marked To Show Proposed Changes lb. Unit 2 Technical Specifications Pages Marked To Show Proposed Changes 2a. Unit 1 Proposed Technical Specifications Pages 2b. Unit 2 Proposed Technical Specifications Pages

3. Commitments c: J. L. Caldwell, NRC Region III K. D. Curry, Ft. Wayne AEP, w/o enclosures/attachments J. T. King, MPSC, w/o enclosures/attachments MDEQ - WHMD/HWRPS NRC Resident Inspector M. A. Shuaibi, NRC Washington, DC

U. S. Nuclear Regulatory Commission AEP:NRC:3304 Page 4 bc: D. C. Baker G. E. Carlson M. J. Finissi D. W. Jenkins, w/o enclosures/attachments J. A. Kobyra, w/o enclosures/attachments D. A. Moul B. A. McIntyre, w/o enclosures/attachments J. E. Newmiller D. J. Poupard R. P. Powers, w/o enclosures/attachments M. K. Scarpello, w/o enclosures/attachments T. K. Woods, w/o enclosures/attachments J. A. Zwolinski, w/o enclosures/attachments

Enclosure 1 to AEP:NRC:3304 AFFIRMATION I, R. P. Powers, being duly sworn, state that I am Executive Vice President of American Electric Power Service Corporation and Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.

American Electric Power Service Corporation R. P. Powers Executive Vice President SWORN TO AND SUBSCRIBED BEFORE ME Tilts /DYO A Y, 2003 JULIE E.NEWMILLER Notary Public, Berrien County, Ml My Commission Expires Aug 22,2004

/ / Nota~ry Public My Commission Expires 9

_' a - ._ i - -

Enclosure 2 to AEP:NRC:3304 Application for Amendment License Amendment Request to Revise Technical Specifications 3.0.4 and 4.0.4

1.0 DESCRIPTION

The proposed amendment would modify technical specification (TS) requirements for mode change limitations in Specification 3.0.4 and Specification 4.0.4. Pages requiring changes because of the changes to Specification 3.0.4 and Specification 4.0.4 are also being revised and are included in this submittal. In conjunction with the proposed change, TS requirements for a TS Bases Control Program described in Section 5.5 of the Westinghouse Standard Technical Specifications (STS), and adoption of STS SR 3.0.1 (Donald C. Cook Nuclear Plant TS 4.0.1) and its associated bases are also being proposed.

Additionally, Indiana Michigan Power Company (I&M) proposes format changes to the affected TS pages that improve appearance but do not introduce other changes.

The changes are consistent with Nuclear Regulatory Commission (NRC) approved industry/Technical Specification Task Force (TSTF) standard technical specification change TSTF-359, Revision 8, as modified by the notice in the Federal Register published on April 4,2003 (Incorporated into TSTF-359, Revision 9, which was approved by the NRC on May 12, 2003). That Federal Register notice announced the availability of this TS improvement through the consolidated line item improvement process (CLIIP).

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation I&M, the licensee for Donald C. Cook Nuclear Plant (CNP) Units I and 2 has reviewed the safety evaluation dated April 4, 2003 as part of this CLIIP. This included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-359, Revision 9. I&M has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to CNP Units 1 and 2 and justify this amendment for the CNP Units 1 and 2 TS.

2.2 Optional Changes and Variations I&M is proposing one deviation from TS changes described in the modified TSTF-359, Revision 9. The following paragraph in the STS SR 3.0.4 bases is not applicable to CNP Units I and 2, because the individual affected CNP TS do not have surveillance frequencies that allow entry into the condition of applicability without performing the surveillance requirement.

Therefore, the present exceptions to Specification 4.0.4 continue to be required for CNP Units 1 and 2. Therefore, this paragraph has not been included in the Specification 4.0.4 bases (the CNP equivalent of STS SR 3.0.4).

to AEP:NRC:3304 Page 2 "The precise requirement for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A surveillance that could not be performed until after entering the LCO's Applicability, would have its Frequency specified such that it is not 'due' until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency."

I&M is not proposing any variations or deviations from the NRC staffs model safety evaluation dated April 4, 2003.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination I&M has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the CLIIP. I&M has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to CNP Units 1 and 2 and is.

hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a). Format changes to improve readability and appearance are not addressed in the NSHCD published in the Federal Register. However, the format changes do no alter any requirements and do not alter the NSHCD conclusions.

3.2 Verification and Commitments As discussed in the notice of availability published in the Federal Register on April 4, 2003 for this TS improvement, plant-specific verifications were performed as follows:

The proposed amendment establishes TS bases for Specification 3.0.4 and Specification 4.0.4 which state that use of the TS mode change limitation flexibility established by Specification 3.0.4 and Specification 4.0.4 is not to be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to operable status before entering an associated mode or other specified condition in the TS applicability.

The proposed amendment includes changes to the bases for Specification .3.0.4 and Specification 4.0.4 that provide details on how to implement the new requirements.

to AEP:NRC:3304 Page 3 The proposed amendment includes bases changes that provide guidance for changing modes or other specified conditions in the applicability when an Limiting Condition for Operation (LCO) is not met.

The proposed amendment includes bases changes that describe in detail how Specification 3.0.4.a allows entry into a mode or other specified condition in the applicability with the LCO not met when the associated actions to be entered permit continued operation in the mode or other specified condition in the applicability for an unlimited period of time. Specification 3.0.4.b allows entry into a mode or other specified condition in the applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the mode or other specified condition in the applicability, and establishment of risk management actions, if appropriate.

Specification 3.0.4.c allows entry into a mode or other specified condition in the applicability with the LCO not met based on a provision in the Specification, which is typically applied to Specifications that describe values and parameters (e.g., Containment Air Temperature, Containment Pressure, Moderator Temperature Coefficient), though it may be applied to other Specifications based on NRC plant-specific approval.

The proposed amendment contains bases stating that any risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182, "Assessing and Managing Risks Before Maintenance Activities at Nuclear Power Plants," and that the results of the risk assessment shall be considered in determining the acceptability of entering the mode or other specified condition in the applicability, and any corresponding risk management actions.

The proposed amendment contains bases stating that upon entry into a mode or other specified condition in the Applicability with the LCO not met, Specification 3.0.1 and Specification 3.0.2 require entry into the actions for no more than the duration of the applicable completion time or until the LCO is met or the unit is not within the applicability of the TS.

The proposed amendment contains bases stating that Specification 4.0.4 does not restrict changing modes or other specified conditions of the applicability when a surveillance has not been performed within the specified frequency, provided the requirement to declare the LCO not met has been delayed in accordance with Specification 4.0.3.

I&M will implement a bases control program consistent with Section 5.5 of the STS, and is proposing TS changes that are the equivalent of STS SR 3.0.1 and its associated bases.

to AEP:NRC:3304 Page 4 4.0 ENVIRONMENTAL EVALUATION I&M has reviewed the environmental evaluation included in the model safety evaluation dated April 4, 2003 as part of the CLIIP. I&M has concluded that the staff's findings presented in that evaluation are applicable to CNP Units 1 and 2 and the evaluation is hereby incorporated by reference for this application.

5.0 REFERENCE Federal Register, Volume 68, Number 65, Page 16579, dated April 4, 2003.

to AEP:NRC:3304 Page 5 TABLE 1 UNIT 1 TECHNICAL SPECIFICATION CHANGES Technical Specification Number Change 3.0.4 Incorporate TSTF-359, Revision 9.

4.0.1 Incorporate Westinghouse Standard Technical Specification SR 3.0.1 4.0.4 Incorporate TSTF-359, Revision 9.

3.1.2.3 Delete ACTION e.

Table 3.3-1 Delete footnotes to ACTIONs 2, 6, and 7.

Delete reference to Specification 3.0.4.

Table 3.3-3 Delete footnotes to ACTIONs 14, 18, and 19.

Delete references to Specification 3.0.4.

3.3.3.1 Delete ACTION c reference to Specification 3.0.4.

Table 3.3-6 Delete ACTION 22A.3 reference to Specification 3.0.4.

Delete ACTION 22B.4 reference to Specification 3.0.4.

3.3.3.2 Delete ACTION statement reference to Specification 3.0.4.

3.3.3.3 Delete ACTION c reference to Specification 3.0.4.

3.3.3.4 Delete ACTION c reference to Specification 3.0.4.

3.3.3.5 Delete ACTION b.

3.3.3.5.1 Delete ACTION c.

3.3.3.8 Delete ACTION c.

3.3.3.9 Delete ACTION c reference to Specification 3.0.4.

3.4.8 Add ACTION c to state Specification 3.0.4.c is applicable.

3.4.9.3 Delete ACTION e.

3.4.10.1 Delete ACTION d.

3.4.11 Delete ACTION h.

3.4.12.1 Delete ACTION c.

to AEP:NRC:3304 Page 6 TABLE I (Continued) 3.4.12.2 Delete ACTION c.

3.5.3 Added ACTION e to state that Specification 3.0.4.b is not applicable to the centrifugal charging pump.

3.6.1.7 Delete ACTION d.

3.6.3.1 Delete ACTION reference to Specification 3.0.4.

3.7.1.1 Delete ACTION c.

3.7.1.2 Delete ACTION reference to Specification 3.0.4. and add ACTION d to state that Specification 3.0.4.b is not applicable.

3.7.1.5 Delete reference to Specification 3.0.4.

3.7.3.1 Delete ACTION reference to Specification 3.0.4.

3.7.4.1 Delete ACTION b.2 reference to Specification 3.0.4.

3.7.5.1 Delete ACTION f.

3.7.7.1 Delete ACTION b reference to Specification 3.0.4.

3.8.1.1 Add ACTION f to state that Specification 3.0.4.b is not applicable to diesel generators.

3.9.12 Delete ACTION b reference to Specification 3.0.4.

3.11.1 Delete ACTION b reference to Specification 3.0.4.

3.11.2.1 Delete ACTION c reference to Specification 3.0.4.

3.11.2.2 Delete ACTION b reference to Specification 3.0.4.

6.8.5 Add new section to require a Technical Specification Bases Control Program.

3.0.4 BASES Incorporate TSTF-359, Revision 9.

4.0.1 BASES Incorporate Westinghouse Standard Technical Specification bases for SR 3.0.1.

4.0.4 BASES Incorporate TSTF-359, Revision 9.

3/4.4.8 BASES Incorporate TSTF-359, Revision 9.

3/4.5.2 and 5.3 BASES Incorporate TSTF-359, Revision 9.

3/4.7.1.2 BASES Incorporate TSTF-359, Revision 9.

3/4.8 BASES Incorporate TSTF-359, Revision 9.

to AEP:NRC:3304 Page 7 TABLE 2 UNIT 2 TECHNICAL SPECIFICATION CHANGES Technical Specification Number Change 3.0.4 Incorporate TSTF-359, Revision 9.

4.0.1 Incorporate Westinghouse Standard Technical Specification SR 3.0.1 4.0.4 Incorporate TSTF-359, Revision 9.

3.1.2.3 Delete ACTION e.

Table 3.3-1 Delete ACTION 2, 6, and 7 footnotes.

Delete reference to Specification 3.0.4.

Table 3.3-3 Delete footnotes to ACTIONs 14, 18, and 19.

Delete references to Specification 3.0.4.

3.3.3.1 Delete ACTION c reference to Specification 3.0.4.

Table 3.3-6 Delete ACTION 22A.3 reference to Specification 3.0.4.

Delete ACTION 22B.4 reference to Specification 3.0.4.

3.3.3.2 Delete ACTION statement reference to Specification 3.0.4.

3.3.3.3 Delete ACTION c reference to Specification 3.0.4.

3.3.3.4 Delete ACTION c reference to Specification 3.0.4.

3.3.3.5 Delete ACTION b.

3.3.3.5.1 Delete ACTION c.

3.3.3.6 Delete ACTION c.

3.3.3.9 Delete ACTION c reference to Specification 3.0.4.

3.4.8 Add ACTION c to state that Specification 3.0.4.c is applicable.

3.4.9.3 Delete ACTION e.

3.4.10.1 Delete ACTION d.

3.4.11 Delete ACTION h.

3.4.12.1 Delete ACTION c.

3.4.12.2 Delete ACTION c.

3.5.2 Delete ACTION b reference to Specification 3.0.4.

to AEP:NRC:3304 Page 8 TABLE 2 (Continued) 3.5.3 Add ACTION e to state that Specification 3.0.4.b is not applicable to the centrifugal charging pump.

3.6.1.7 Delete ACTION d.

3.6.3.1 Delete ACTION reference to Specification 3.0.4.

3.7.1.1 Delete ACTION c.

3.7.1.2 Delete ACTION reference to Specification 3.0.4 and add ACTION d to state that Specification 3.0.4.b is not applicable.

3.7.1.5 Delete reference to Specification 3.0.4.

3.7.3.1 Delete ACTION reference to Specification 3.0.4.

3.7.4.1 Delete ACTION b.2 reference to Specification 3.0.4.

3.7.5.1 Delete ACTION f.

3.7.8.1 Delete ACTION b reference to Specification 3.0.4.

3.8.1.1 Add ACTION f to state that Specification 3.0.4.b is not applicable to diesel generators.

3.9.12 Delete ACTION b reference to Specification 3.0.4.

3.11.1 Delete ACTION b reference to Specification 3.0.4.

3.11.2.1 Delete ACTION c reference to Specification 3.0.4.

3.11.2.2 Delete ACTION b reference to Specification 3.0.4 6.8.5 Add new section to require a Technical Specification Bases Control Program.

3.0.4 BASES Incorporate TSTF-359, Revision 9.

4.0.1 BASES Incorporate Westinghouse Standard Technical Specification bases for SR 3.0.1.

4.0.4 BASES Incorporate TSTF-359, Revision 9.

3/4.4.8 BASES Incorporate TSTF-359, Revision 9.

3/4.5.2 and 5.3 BASES Incorporate TSTF-359, Revision 9.

3/4.7.1.2 BASES Incorporate TSTF-359, Revision 9.

3/4.8 BASES Incorporate TSTF-359, Revision 9

Attachment la to AEP:NRC:3304 UNIT 1 TECHNICAL SPECIFICATIONS PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT I 3/4 0-1 3/4 3-21 3/4 3-54 3/4 7-1 3/4 11-3 3/40-2 3/4 3-21a 3/4 3-57 3/4 7-5 6-9 3/4 0-3 3/4 3-21b 3/4 4-21 3/4 7-10 B 3/4 0-1 3/4 1-11 3/4 3-22 3/4 4-31 3/4 7-15 B 3/4 0-4 3/4 3-3 3/4 3-35 3/4 4-33 3/4 7-17 B 3/4 0-4a 3/4 3-4 3/4 3-37 3/4 4-36 3/4 7-19 B 3/4 4-5 3/4 3-5 3/4 3-39 3/4 4-37 3/4 7-26 B 3/4 5-2 3/4 3-6 3/4 3-40 3/4 4-39 3/4 8-2 B 3/4 7-2 3/4 3-16 3/4 3-43 3/4 5-7 3/4 9-13 B 3/4 8-3 3/4 3-17 3/4 3-46 3/4 6-9a 3/4 11-1 3/4 3-20 3/4 3-48a 3/4 6-14 3/4 11-2

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification, except as provided in Specification 3.0.6.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification, except as provided in Specification 3.0.6. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

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

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

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications.

3.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements unless other-wise excepted. This provision shall not prevent passa.e throubh OPERATIONAL MODES as required to comply with ACTION sweme t :

t e_ m an ppe inblstyB~_llh"yfide made:

______d_ in ebf peritd time; We st p erma tafin coTmpsse smen i determindtoi be i ab sl ecnd a e its eeeyp es rcis inoperable, theolelyabea uofsthe it a lpoesr inopPEraTIONma Os conid dOP BEforthe pupcofsatisfy3inge osed Apptihabiiitreendtstablishcable riskitnanagement forOperatkioprovided: 1f)its corr esponding normaTIor emergenA ypowersour ceoiO R Land (2) 3.0.5 When a system, subsystem, train, component-or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (I) its corresponding normnal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

COOK NUCLEAR PLANT-UNIT 1 Page 314 0-1 AMENDMENT264

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

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

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

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

This Specification is not applicable in MODES 5 or 6.

3.0.6 Equipment removed from service or declared inoperable to comply with ACTION requirements may be returned to service under administrative controls solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Specifications 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SURVEILLANCE REOUIREMENTS 4.0.1 Surveillance requirements shall be applicable durinig the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual

-c s AoppicAbity f I niduh itligj~CditionCTIfii!Opers n

,spac u.ei .....

i ia ent ilu s failure x encediiuinng the 'p~eifoorancef Szurviine I or~ etween "' o f ce sdifthe Srvehllance, sha "efiItf:metV Lfitiig d, itioh forperation. ilure .erflornid 9llance w tbin

~~ ~ Lmutn ~ ~ ~ provided inper speification r4.0.32setSurno-m Ne to be iperfomed&ion-onor-fvariabIrable eopment d

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less. This delay period is permitted to allow performance of the surveillance.

If the surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

When the surveillance is performed within the delay period and the surveillance criteria are not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

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

4.0.4 Entr' into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirenient(s) associated with the Limiting Condition-for Operation have been performed wsithin the stated sunveillance intervl orathwise P ilnli i ,ayeb RedrCtindititinSiles thi splIft n qy,:xcept COOK NUCLEAR PLANT-UNIT I Page 3/4 0-2 AMENDMENT 98,443,4-90,263

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

_his~prpviso __ ma 0 veillainceseX~~~~~~~fient. T E~~~~~bi2 W d~~ifieondtinhir 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 performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.

SURVEILLANCE REQUIREMENTS

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 Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for inservice inspection and testing activities inservice inspection and testing criteria 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 Yearly or annually At least once per 366 days

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

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

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

4.0.6 Deleted 4.0.7 Deleted COOK NUCLEAR PLANT-UNIT I Page 3/4 0-3 AM ENDM ENT 4-00,4-24,444,243

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3

a. One charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

b. One charging flowpath associated with support of Unit 2 shutdown functions shall be available APPLICABILITY: Specification 3.1.2.3.a. - MODES 5 and 6 Specification 3.1.2.3.b. - At all times when Unit 2 is in MODES 1,2, 3, or 4.

ACTION:

a. With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes except: 1) heatup or cooldown of the reactor coolant volume provided that SHUTDOWN MARGIN sufficient to accommodate the change in temperature is maintained in accordance with Specification 3.1.1.2 in MODE 5 or Specification 3.9.1 in MODE 6, and the heatup or cooldown rate is restricted to 501F or less in any one-hour period in MODE 5, or 2) addition of water from the RWST, provided the boron concentration in the RWST is greater than or equal to the minimum required by Specification 3.1.2.7.b.2.

b. With more than (ne charging pump OPERABLE or with a safety injection pump(s) OPERABLE when the temperature of any RCS cold leg is less than or equal to 1520 F, unless the reactor vessel head is removed, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within one hour.

c. The provisions of Specification 3.0.3 are not applicable.

d. In addition to the above, when Specification 3.1.2.3.b is applicable and the required flow path is not available, return the required flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return the required flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e. The requirements of Specification 3.0.4 arc not applicable when Specification 3.1.2.3.b applies.

SURVEILLANCE REOUIREMENTS 4.1.2.3.1.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.

A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 1520F.

COOK NUCLEAR PLANT-UNIT I Page 314 1-Il AM ENDM ENT 98,440, 4,464, 4-, 203, 230

r) TABLE 3.3-1 0

0 r, REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

> FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION z~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

1. Manual Reactor Trip 2 1 2 1, 2 and 12 z 2. Power Range, Neutron Flux 4 2 3 1, 2 and 2

- 3. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1,2 2 High Negative Rate

5. Intermediate Range, 2 1 2 1, 2 and 3 Neutron Flux

6. Source Range, Neutron Flux A. Startup 2 1 2 21 and 4 B. Shutdown 2 0 1 3,4and5 5

7. Overtemperature AT 4 2 3 1, 2 6 Four Loop Operation

8. Overpower AT 4 2 3 1, 2 6#

Four Loop Operation z

3

0 TABLE 3.3-1 (Continue) 0 REACTOR TRIP SYSTEM INSTRUMENTATION z MINIMUM c

TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Z 9. Pressurizer Pressure - Low 4 2 3 1,2 6A

10. Pressurizer Pressure -- High 4 2 3 1,2

11. Pressurizer Water Level -- 3 2 2 1,2 3 High

Z

12. Loss of Flow - Single Loop 3/loop 2/loop in any 2/loop in each 1 (Above P-8) operating loop operating loop

13. Loss of Flow - Two Loops 3/loop 2/loop in two 2/loop in each I 7%

(Above P-7 and below P-8) operating loops operating loop

14. Steam Generator Water 3/loop 2/loop in any 2/loop in each 1,2 Level -- Low-Low operating loop operating loop

15. Steam/Feedwater Flow 2/loop-level and 1/loop-level 1/loop-level and 1,2 Mismatch and Low Steam 2/loop-flow coincident with 2/loop-flow mis-Generator Water Level mismatch in same 1/loop-flow match or 2/loop-loop mismatch in level and I/loop-same loop flow mismatch z

M-.1

0 0 TABLE 3.3-1 (Continued) x REACTOR TRIP SYSTEM INSTRUMENTATION zt MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

16. Undervoltage-Reactor Coolant 4-1/bus 2 3 I Pumps

17. Underfrequency-Reactor 4-1/bus 2 3 Coolant Pumps

18. Turbine Trip A. Low Fluid Oil 3 2 2 I Pressure B. Turbine Stop Valve 4 4 4 1 w11 Closure W

19. Safety Injection Input from 2 I 2 1,2 l ESF

20. Reactor Coolant Pump Breaker Position Trip Above P-7 I/breaker 2 I/breaker per I 11 operating loop 2:

M 21. Reactor Trip Breakers 2

z I 2 1,2' 13, 15 IV M 3 ,4',5' 14 z 22. Automatic Trip Logic 2 I 2 i 1,2 1 S 3 ,4,*5 14 t4 2:

4 =

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION . .

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

II The nFovisions of Snecification 3.0.4 are not aX licable.

1. 1 High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 4.3.1.1.1.

ACTION 2- 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.

a. The inoperable channel is placed in tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable 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 of the other channels per Specification 4.3.1.1.1.

c. Either THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to less than or equal 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 QUADRANT POWER 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.c.

ACTION 3- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

3/4 3-6 AMENDMENT NO. 74, 4-20, 254 D.C.COOK'-UNITI D. C. COOK - UNIT I 314 3-6 AM ENDM ENT NO. -74, M, 254

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS a Manual Initiation See Functional Unit 9 2

I 2 1,2,3,4 I

b. Automatic Actuation 13 Logic

c. Containment Pressure 3 2 2 1,2,3 14'

- High

d. Pressurizer Pressure - 3 2 2 1,2,3# 14' Low

e. Differential Pressure Between Steam Lines -

High Four Loops Operating 3/steam line 2/stearn line 2/steam line 1,2,3" 141 any steam line Three Loops Operating 3/operating steam 1""/steam line, 2/operating 15 line any operating steam line steam line COOK NUCLEAR PLANT-UNIT I Page 314 3-16 AMENDMENT 90,M, 153

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

f. Steam Line Pressure -

Low I Four Loops Operating I pressure/loop 2 pressures any I pressure any 1,2,3"' 14#

loops 3 loops Three Loops Operating I pressure/ I"'/ pressure in I pressure in 15 operating loop any operating any 2 operating loop loops COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-17 AMENDMENT 91, 4-2,0,4-53,214

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

4. STEAM LINE ISOLATION

a. Manual See Functional Unit 9 2

I

b. Automatic Actuation 2 I 1,2,3 13 Logic

c. Containment Pressure - 4 2 3 1,2,3 16 High-High

d. Steam Flow in Two Steam Lines - High Four Loops Operating 2/steam line I/steam line I/steam line 1,2 , 3 u' 141 any 2 steam lines Three Loops Operating 2/operating steam Il'any I/operating 15 line operating steam steam line line COOK NUCLEAR PLANT-UNIT I Page 3/4 3-20 AMENDMENT 90,420,153

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION COINCIDENT WITH Tog - Low-Low Four Loops Operating I Tv'loop 2 T. any loops I Tg any 3 1,2, 3" 14' loops I*" TV,, in any Three Loops Operating I Tvgloperating operating loop I T. in any 3A## 15 loop two operating loops

e. Steam Line Pressure-Low I Four Loops Operating I pressure/loop 2 pressures any I pressure any 1, 2, 3" 14' loops 3 loops Three Loops Operating I pressure/ I#a pressure in I pressure in 15 operating loop any operating any 2 operating loop loops

5. TURBINE TRIP &

FEEDWATER ISOLATION

a. Steam Generator Water Level - High-High 3/loop 2/loop in any 2/loop in each 1,2,3 14' operating loop operating loop COOK NUCLEAR PLANT-UNIT I Page 314 3-21 AMENDMENT 9-1,4-2-0,4-53,214

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION.

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 141 Level - Low-Low any Stm. Gen.

b. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2, 3 141 Voltage Pump Start 2/bus (TI IA -

Train B; TI ID

- Train A)

Valve Actuation (Both 2/bus on (Tl IA trains) &TIl1B or 2/busses TI 1C

&TIID)

I

c. Safety Injection 2 2 1,2,3 18*

d. Loss of Main Feedwater 2 2 2 1,2 181 Pumps

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 141 Level - Low-Low any 2 Stm. Gen.

2

b. Reactor Coolant Pump 4-1/Bus 3 1,2,3 I 91 Bus Undervoltage

8. LOSS OF POWER

a. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3,4 14#

Voltage

b. 4 kV Bus Degraded 3/Bus 2/Bus 2/Bus 1,2,3,4 141 Voltage (TI IA-Train B; (TI IA-Train (TIA -Train Tl ID-Train A) B;TIID- B; TI ID-Train A) Train A)

COOK NUCLEAR PLANT-UNIT I Page 314 3-21 a AMENDMENT 92,435,1553,243

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

9. MANUAL

a. Safety Injection (ECCS) 2/train I/train 2/train 1,2,3,4 18 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray 1/train I/train I/train 1,2,3,4 18 Containment Isolation -

Phase "B" Containment Purge and Exhaust Isolation I

c. Containment Isolation - I/train I/train I/train 1,2,3,4 18 Phase "A" Containment Purge and Exhaust Isolation

d. Steam Line Isolation 2/steam line (I per 2/steam line (I 2/operating 1,2,3 20 train) per train) steam line (I per train)

e. Containment Air I/train I/train I/train 1,2,3,4 18 Recirculation Fan

10. CONTAINMENT AIR RECIRCULATION FAN

a. Manual -See Functional Unit 9-

b. Automatic Actuation 2 I 2 1,2,3 13 Logic

c. Containment Pressure - 3 2 2 1,2,3 14' High COOK NUCLEAR PLANT-UNIT I Page 314 3-21 b AMENDMENT4-53,234

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be bypassed in this MODE below P-I 1.

Trip function may be bypassed in this MODE below P-12.

1. 1. The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

1. 1. 1. Manually trip all bistables which would be automatically tripped in the event pressure in the associated active loop were less than the pressure in the inactive loop. For example, if loop I is the inactive loop then the bistables which indicate low pressure in loops 2, 3 and 4 relative to loop I should be tripped.

The provisions of Specification 3.0.1 are not applicable.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Total Number of Channels, 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 ; 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 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the 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 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel associated with an operating loop 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 4.3.2.1.1.

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 the 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 4.3.2.1.1.

COOK NUCLEAR PLANT-UNIT I Page 3/41 3-22 AMENDMENT94,120

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarn/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

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

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

c. The provisions of Specifications 3.0.3 and-3.0.4-are not applicable.

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

COOK NUCLEAR PLANT-UNIT I Page 3/41 3-35 AMENDMENT 60

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9. This ACTION is not required during the performance of containment integrated leak rate test.

ACTION 22A- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. Technical Specification Sections 3.0.3 and 3.0.4 1 Not Applicable.

ACTION 22B- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. In the event of an accident involving radiological releases initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Technical Specification Sections 3.0.3 and 3.A4 E Not Applicable.

COOK NUCLEAR PLANT-UNIT I Page 3/4 3-37 AMENDMENT94,4-34,168

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles,

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

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

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the axial flux difference detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement ofF F and FQ(Ze) I ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and3-.04-are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.32 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output to be used during its use when required for:

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

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement ofF NH and FQ (Z.!).

I COOK NUCLEAR PLANT-UNIT I Page 3/4 3-39 AMENDMENT25

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

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

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed 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. 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.

COOK NUCLEAR PLANT-UNIT I Page 3/41 3-410

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION METEOROLOGICAL LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

b. With one or more required meteorological monitoring channels inoperable for more than 7 days, 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.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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.

COOK NUCLEAR PLANT-UNIT I Page 3/41 343

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

run l

h -

The .

rMrnIASIon Ot SnecitcatiOn i3_UA are nOt annhicOb4e-

. _ . _ . . A _ . ._ I

- --r I r Err SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

COOK NUCLEAR PLANT-UNIT I Page 3/4 3-46 AMENDMENT 262

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The Appendix R remote shutdown instrumentation channels shown in Table 3.3-9A be OPERABLE with an opposite unit power supply available and with read out capability at the LSI panels.

APPLICABILITY: MODES 1, 2, and 3 ACTION:

a. With the number of OPERABLE Appendix R remote shutdown monitoring channels less than required by Table 3.3-9A, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the opposite unit power supply not available, restore the power supply to available status within 7 days, or provide fire watches in the affected areas and restore the inoperable channel to OPERABLE status within the next 60 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each Appendix R remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6A.

COOK NUCLEAR PLANT-UNIT I Page 3/4 3-48a AMENDMENT 131

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The post-accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-1 1 (except item 8), either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE post-accident monitoring channels one less than required by Table 3.3-11, item 8, Refueling Water Storage Tank Water Level:

1. Either restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

2. Within one hour, bypass the Residual Heat Removal Pump trip function from the Refueling Water Storage Tank Water Level for the pump associated with the out-of-service instrument.

c. The provisions of Specification 3.0.4 arc not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

COOK NUCLEAR PLANT-UNIT I Page 314 3-54 AMENDMENT 49,4-24,4-44,232

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With an explosive gas monitoring instrumentation channel alarm/trip setpoint less conservative than the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days. If unsuccessful, prepare and submit a SPECIAL REPORT to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and-3.0.4are not applicable.

SURVEILLANCE REOUIREMENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION. and analog CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

COOK NUCLEAR PLANT-UNIT I Page 3/14 3-57 AMENDMENT 69,4---4,189

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY I LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity ofthe reactor coolant shall be limited to:

a. Less than or equal to I microCurie per gram DOSE EQUIVALENT 1-131, and

b. Less than or equal to I 00/E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES 1,2,3,4and5 ACTION:

MODES 1, 2 and 3

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T,8 , less than 500F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the reactor coolant greater than 100/ E microCuries per gram, be in HOT STANDBY with Tvg less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 1, 2,3,4 and 5

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 or greater than 100/ microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.

SURVEILLANCE REOUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the I sampling and analysis program of Table 4.44.

With Tavg greater than or equal to 5000F. I COOK NUCLEAR PLANT-UNIT I Page 314 4-21 AMENDMENT 142

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 - REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a lift setting of less than or equal to 435 psig, or

b. One power operated relief valve (PORV) with a lift setting of less than or equal to 435 psig and the RHR safety valve with a lift setting of less than or equal to 450 psig.

APPLICABILITY: Mode 5 When the temperature of any RCS cold leg is less than or equal to 152 0F, and Mode 6 when the head is on and fastened to the reactor vessel and the RCS is not vented through a 2-square-inch or larger vent, or through any single blocked open PORV.

ACTION:

a. With one of two PORVs required by item a above or either the PORV or RHR safety valve required by item b above inoperable, either restore the inoperable PORV or RHR safety valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months . Maintain the RCS in a vented condition until the inoperable PORV or RHR safety valve has been restored to OPERABLE status.

b. With both PORVs and the RHR safety valve inoperable, complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Maintain the RCS in a vented condition until both PORVs or one PORV and the RHR safety valve have been restored to OPERABLE status.

c. With the RCS vented per ACTION a or b above, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. In the event either the PORVs, the RHR safety valve or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vents on the transient, and any corrective action necessary to prevent recurrence.

e. The provisions of Specification 3.0.1 are not applicable.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 4-31 AMENDMENT88,46-7,176

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1.2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.

APPLICABILITY: ALL MODES ACTION:

a. With the structural integrity of any ASME Code Class I component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 500F above the minimum temperature required by NDT considerations.

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.

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

d. The provisions of Specification 3.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33 AMENDMENT 98,217

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

g. With PORVs and block valves not in the same line inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the valves to OPERABLE status or close and de-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.

h. The provisions of Specification 3.0.4 arc not applicable.

SURVEILLANCE REQUIREMENTS 4.4.11.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and

b. At least once per 18 months by operating the PORV through one complete cycle of fnl travel during MODES 3 or 4, and

c. At least once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and

d. At least once per 18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.11.

4.4.11.3 Deleted.

COOK NUCLEAR PLANT-UNIT 1 Page 314 4-36 AMENDMENT 4-44,468,4-7-6,211

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM REACTOR VESSEL HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12.1 At least one of the Reactor Vessel head vent paths, consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Reactor Vessel head vent paths inoperable, and at least one of the Pressurizer steam space vent paths OPERABLE (see Specification 3.4.12.2), operation in MODES 1, 2, 3 or4 may continue, provided the inoperable vent paths are maintained closed with power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Reactor Vessel head vent paths within 30 days 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 .

b. With both of the Reactor Vessel head vent paths and both of the Pressurizer steam space vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

c. The provision of Specification 3.0.1 are not applicable.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-37 AMENDMENT 98

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS LIMITING CONDITION FOR OPERATION 3.4.12.2 At least one of the Pressurizer steam space vent paths, each consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Pressurizer steam space vent paths inoperable, and at least one of the Reactor Vessel head vent paths OPERABLE (see Specification 3.4.12.1), operation in MODES 1, 2, 3 or 4 may continue, provided the inoperable vent paths are maintained closed with the power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Pressurizer steam space vent paths within 30 days 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 in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both of the Pressurizer steam space vent paths and both of the Reactor Vessel head vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

c. The provisions of Specification 3.0.4 are not applicable.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-39 AMENDMENT98

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ECCS SUBSYSTEMS - T. < 3500 F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,#

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Tvg less than 3507F by use of alternate heat removal methods.

c. With more than one charging pump OPERABLE or with a safety injection pump(s)

OPERABLE when the temperature of any RCS cold leg is less than or equal to 1520 F, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within I hour.

d. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

A maximum of one centrifugal charging pump shall be OPERABLE and both safety injection pumps shall be inoperable whenever the temperature of one or more of the RCS cold legs is less than or equal to 152 0F.

COOK NUCLEAR PLANT-UNIT I Page 3/4 5-7 AMENDMENT 88, 167

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities. No more than one purge supply path and one purge exhaust path shall be open at a time.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , either:

1) Restore the inoperable valve to OPERABLE status, or,

2) Deactivate the automatic valve secured in the closed position.

b. Operation may then continue until performance of the next required valve test provided that the automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 31 days.

c. Otherwise, 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. The provisions of Specification 3.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The surveillance requirements of Technical Specifications 3/4.6.1.2 and 3/4.6.3.1 apply.

COOK NUCLEAR PLANT-UNIT I Page 3/4 6-9a AMENDMENT 66,4r5, 209

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE. Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control. The ACTION statement of T/S 3/4.6.3.1 is not applicable to the containment purge supply and exhaust isolation valves. The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.

APPLICABILITY: MODES 1, 2,3 and 4.

ACTION:

With one or more of the containment isolation valve(s) inoperable, either

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or

d. 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The pro'isions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

COOK NUCLEAR PLANT-UNIT I Page 3/4 6-14 AMENDMENT95,4-70,181

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. MODES I & 2: With 4 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and comply with action statement b.

b. MODE 3: With a minimum of 3 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves associated with an operating loop inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the reactor trip breakers are opened; otherwise, be in HOT SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. The PrFOsiziOn of Specification 3.0.4 arc not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with lift settings as shown in Table 4.7-1. The safety valve shall be reset to the nominal value +/-1% whenever found outside the +/-1% tolerance. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-1 AMENDMENT 4N, 464,4S2,210

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2

a. At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

1. Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and

2. One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.

b. At least one auxiliary feedwater flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.1.2.a - MODES 1, 2, 3.

Specification 3.7.1.2.b - At all times when Unit 2 is in MODES 1, 2, or 3.

ACTIONS:

When Specification 3.7.1.2.a is applicable:

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

When Specification 3.7.1.2.b is applicable:

With no flow path to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The reauirement1 aof Secification 3.0.4 are not aonlicable.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-5 AM ENDM ENT 92, A, -26, 43, 168

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator stop valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE I - With one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 2 - With one or more steam generator stop valves inoperable, close the inoperable valve(s) within and 3 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and verify the inoperable valves are closed at least once per 7 days. Otherwise, be in at least MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , with the unit in at least MODE 3 within the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

T:c provisiensof Specification 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.

4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-10 AMENDMENT 4-20,447.,4-64,185

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.7 PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1

a. At least two independent component cooling water loops shall be OPERABLE.

b. At least one component cooling water flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3. .a - MODES 1, 2, 3 and 4.

Specification 3.7.3.I.b - At all times when Unit 2 is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.7.3.I.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

When Specification 3.7.3.l.b is applicable:

With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The reouirements of SneAification 3.0.4 are not aunlicable.

SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

c. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per 18 months by verifying that the unit cross-tie valves can cycle full I travel. Following cycling, the valves will be verified to be in their closed positions.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-15 AMENDMENT 407, 34, 444, 464, 243, 275

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 a. At least two independent essential service water loops shall be OPERABLE.

b. At least one essential service water flowpath associated with support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4. L.a - Either Unit in MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b - At all times when Unit 2 is in MODES 1, 2, 3 or 4.

ACTION:

a. When Unit I is in MODES 1, 2, 3, and 4:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. When Unit 2 is in MODES 1, 2, 3 and 4:

1. With any Unit I essential service water pump not OPERABLE, within one hour close at least one crosstie valve on the associated header or have Unit 2 enter ACTION a for Unit 2 Specification 3.7.4.1 for the Unit 2 essential service water pump sharing the same header with the inoperable Unit 1 essential service water pump.

2. With no essential service water flow path available in support of Unit 2 shutdown functions, return at least one flow path to available status within 7 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The requirements of Specification 3.0.4 arc not applicable.

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months by verifying that each automatic valve servicing safety I related equipment actuates to its correct position on a Safety Injection test signal.

c. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per 92 days by verifying that each closed crosstie valve, in the available essential service water flowpath associated with support of Unit 2 shutdown functions, can be cycled from the control room.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-17 AMENDMENT 407, 4, 444,4-64, 253, 275

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system (CREVS) shall be OPERABLE with:

a. Two independent pressurization trains, and

b. One charcoal adsorber/HEPA filter unit.

-NOTE The control room envelope/pressure boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, and during the movement of irradiated fuel assemblies.

ACTION:

MODES 1, 2, 3, and 4:

a. With one pressurization train inoperable, restore the inoperable train to OPERABLE status within 7 days 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the filter unit inoperable, restore the filter unit to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With two CREVS pressurization trains inoperable due to an inoperable control room envelope/pressure boundary, restore the control room envelope/pressure boundary to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

During the movement of irradiated fuel assemblies:

d. With one pressurization train inoperable, restore the inoperable pressurization train to OPERABLE status within 7 days, or initiate and maintain operation of the remaining OPERABLE train in the pressurization/cleanup alignment.

e. With any of the following: (1) both pressurization trains inoperable; (2) the filter unit inoperable; or (3) the control room envelope/pressure boundary inoperable, immediately suspend all operations involving the movement of irradiated fuel assemblies.

f. The provisions of Specification 3.0.1 are not applicable to movement of irradiated fuel assembies.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-19 AMENDMENT 4-59,2,74,276

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of 2 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

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

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.7.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

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

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

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

a. Sources in use (excluding startup sources and fission detectors previously subiected to core flux) -

At least once per six months for all sealed sources containing radioactive materials.

COOK NUCLEAR PLANT-UNIT I Page 314 7-26 AMENDMENT235

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS ACTION (Continued)

c. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. offsite source by performing Surveillance Requirement 4.8.1.1.l.a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and if the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirement 4.8.1.1 .2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With the diesel generator restored to OPERABLE status, follow ACTION Statement a.* With the offsite circuit restored to OPERABLE status, follow ACTION Statement b.*

d. With two of the above required offsite A.C. circuits inoperable, restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6-hours. With only one offsite source restored, follow ACTION Statement a.

e. With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one diesel generator unit restored, follow ACTION Statement b or c*.

SURVEILLANCE REOUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class I E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and --

b. Demonstrated OPERABLE at least once per 18 months by transferring the unit power source automatically from the normal auxiliary source to the preferred reserve source and by transferring manually to the alternate reserve source.

The ACTION statement time shall be based upon the time associated with the component inoperability, and is not reset when exiting this ACTION statement.

COOK NUCLEAR PLANT-UNIT I Page 3/4 8-2 AMENDMENT-115,183

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS I STORAGE POOL VENTILATION SYSTEM**

LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage poolt until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

I. Deleted

2. Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfhi +/- 10%.

The crane bay roll-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over I the storage pool.

- Shared system with D.C. COOK - UNIT 2.

t This does not include the main load block. For purposes of this specification, a de-energized main load block need not be considered a load.

COOK NUCLEAR PLANT-UNIT I Page 3/4 9-13 AMENDMENT4-Z4,243

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS LIOUID HOLDUP TANKS*

LIMITING CONDITION FOR OPERATION 3.11.1 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tanks.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay 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.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Page 3/4 11-1 AMENDMENT69,4-4,4-89 I COOK PLANT-UNIT 1I NUCLEAR PLANT-UNIT COOK NUCLEAR Page 314 11-1 AMENDMENT 69,4-54,4-99 1

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 3% by volume if the hydrogen in the system is greater than or equal to 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 3% by volume but less than or equal to 4% by volume and containing greater than or equal to 4% hydrogen, restore the concentration of oxygen to less than or equal to 3% or reduce the hydrogen concentration to less than 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

b. With the concentration of oxygen in the waste gas holdup system or tank greater than 4% by volume and greater than 4% hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to less than or equal to 3% or the concentration of hydrogen to less than or equal to 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months in the system or tank.

c. The provisions of Specifications 3.0.3 anda3.04 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

COOK NUCLEAR PLANT-UNIT I Page 3/4 11-2 AMENDMENT -73,4-54,189

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay 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.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days whenever radioactive materials are added to the tank and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary coolant system degassing operations.

COOK NUCLEAR PLANT - UNIT I Page 3/4 11-3 AMENDMENT 69,4-54,4-83,4.89,231

6.0 ADMINISTRATIVE CONTROLS PROCEDURES'AND;PRO(GAMS>(ontinuled) 6 ITh is tot li requiresmengthsoe1Cof FederalRaltise followin g~~~~~~~~~~~~~~~~~~ .5 reot 2hl be subited tothe egioal AdminitalSetorAnle yss otherwise ased.ta~ ti,'du 6... h tatprpr haladesecho h etsietfe n h SRadshl nld ma~~~ecrpino the maure auso h prtn odtoso hrceitcbanddrn

~c - Treceipt of n operatiglicnyse (2) amendment tovteicense

~ t no lvensur ha ptlanned) anreas in tower F~ ~~~h tetpormada oprsno hsevlewihdsgpriconadseifatn.Ay i_~~orcieatosta eereurdt banstsatr prainsalas edsrbd n dsripton ofenhe measurdvaus of th op Ieraingcniin rcaateitc banddrn 6.9.1naddtion tosth aplicrabledre mportisng requirement o ofs 1,Cdesg ofrederiosaR nd peguliations,.h wite folwng 6.9.1In addition t a esp cifpical depotais requiredmnientseo ndTition baseCde on otheracommiatments, shafllowbe b ud inmtedthirepoRt incrshal goa.diitrtruls thrientd 6.9.1.1Asummryetv repotiofs plant staertqupiand pooweri escaatisfcony tpesationg shallbes sbmecitted.folowngy1 receiptiofnan operaingficdenaisreq()iaendmentoth niionvolvidng planed license cmincrease inal poer hyruincl nti rper ormac fthepat COOK NUCLEAR PLANT-UNIT 1 Page 6-9 COOK AMENDMENT NUCLEAR I 7,4-54, PLANT-UNIT 6-9 M, 226 Page 1

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

3.0.1 This specification defines the applicability of each specification in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 The specification delineates the measures to be taken for those circumstances not directly provided for in the ACTION Statements and whose occurrence would violate the intent of a specification. For example, Specification 3.5.2 requires two independent ECCS Subsystems to be OPERABLE and provides explicit ACTION requirements if one ECCS Subsystem is inoperable. Under the requirements of Specification 3.0.3, if both the required ECCS Subsystems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further example, Specification 3.6.2.1 requires two Containment Spray Systems to be OPERABLE and provides explicit ACTION requirements if one Spray System is inoperable. Under the requirements of Specification 3.0.3 if both the required Containment Spray Systems are inoperable, within one hour measure must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.0.4 This specification provides that entry into an OPERATIONAL MODE or other specified applicability condition must be made with (a) the full complement of required systems, equipment or components OPERA.BLE and (b) all other Ameter ar specified in the Limiting Conditions fOr Operation being met wAthout regard fr abl dviations and out fserviceproviSOinS contained inA tTheACTONstatement.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

Exceptions to this provision have been provided for a limited number ofspecifications when startup with inoperable equipment would ot affect plant safety. These exceptions are stated in the ACTION statement of the apprcprlate spgee*t*eains-COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 0-1 AMENDMENT 46

INSERT I

- -- w_-.. - __1. - . -1 - - - I . __ II I. . . .7---111. -1 -11 "I ____ I-. ---- . 11-- - - - -I- - - - - - - -I I- - -- .-

B.0f1V Speciticatbon 30.4 ;establishesplimiitationsan chIanges .mk EKATIONALl.MUOVES ~orjOther

,p~cifie~dcnditidns Fin the Appihcaility uwin~h fiitiorItiet.Ii iod pacn theunit in anOPERATOA$IODEoifiereiindiii, rfsjted iniithE (e g cApplicability the desird to entere)' uni cid'hothasufiq qnremeiOs of th';e~Lmtnger nditioitmr: &em > m lg ig 4ci El&°.3 iti0o ~ 34 jhificat iion34~~3t4 DP O N OP ~~ION eMDE; iefieedafiidt in honptiailt D~~~iEION~~~~lj<<oLa i th the'sL~imiting~ondit ioFn - forQ~riont~or,,4inot erj~§p etevhi~asociat PtE PERK-Oal miOsAnODtered iMOEoreceflI ptrm ctind! OPEN R ODE ~cfsft othere o o 1Ess~iONAL~mg and DE i jcasee KetiyitiesffiOeRaPO W d~~ti~if3.0A~b`

.. WIU 'II S.~~~~~~~~~~~~, on, in J~idelinel = ~~~~~~~~~~~~DE" dsentsifER ecifec cnditio i Ibd -tApli~^i~abiclitpecf6catuiiiiiit~d App~~~icabi~~~~ityit~fiith theati intiirtijeit speriod of imeY rnnce .cmIchwitWn equiiinsthnat e teniud; operationo~euit rand components, fo aniii'sm'edncpidpati6duf i&Idgim ihS mni 6ninuedseWtion: -i:iit kh er-1:~ihl js'ofthiih sntd befrsedor iaderth heriska'ss'e'ssm Guldeo6 entg82h& Siidor~sest.

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TquantitaftiVemanagetant4colndedapprersS '

in~i~~ii~ii

' 'd d and tew sessffibnen wiR e aconductd usEng tfih 1%program, procedures nan rteaco mpement ,'1,0 CFRI~50'.65(~a(4)'" ,which uiretesth*tih~risk,',h$iso mitipaacte's~b sessed anhd m~anged fh'erisk assesstnentjfor6iniipupobseso j~cf~in~ 4b ~iti uipnen igiilded _mthe`norml'fi , O'dFJ50.65(4) 4)" .is sesetsoe 4e7iI 182 "A.ssessin~ -Bfor Ma~in'tenanceAcitesaNuerPorPlis' uidefnlinefor Mofoigth fetveeso>aintenancea ula oe lns l~e c~i'ets;ade~iea guianefr onuct o thefikassmn uniaiehn ions S pThese,~~~~ o h panjand 6rs,'

cdu ~~exmdu=i" Hire w.erallis~ e riiskI iiaens 'by-shiWt~nd, maaeetpronlctions rdueOh tiraoh ',of4hecondition,; ctio6'Ks~o.'rnimmze thl etpisliffiencof

)ackup .~s'ucc~ess ~,paths `or compensatoyl aue a~~eemnto £th~t<ii rproposd PERATJONALMIMODE ~cang,,si;acceptable. ,t bKonsidation~ should WI Nfl-6If peratin~wou be mt priorstorathexira~uc',littion mpuiinfi etionJ glatonid reqire.~~

3dtiiigihfi~~~~~~~~ji~~~licability,~~~~ a j~ic~ton,0 bmaybe~se ~wthsinle~r nu~ip&syt~maid~cmpnens unava7alel siilHhe k§ dinTs'h Will 3nsidYd OPERATION MODEKoi ihi' d" he' ' '2:specified :conitionIii eippicaiiy,n2 ary bci-iesonding 3.0.4.1* iik'asenisLn6ihive1o Ll6Piiniehied.

ilie:. technical MSpecitications 'e'allow continued -peration unavailable'>^ mi witl1~equipment, ePERATIONaLvD iratioiof the Conplebon Tiih iSince this ISallowableiand inmc igeiseeRkifipfthatNpmicila'KiOPERATIONALDEMOD b e skof ,

oansitonginto<ndfh oug ih Jicab OPERATONAYMODES rotherspeif onaditions Min'r-.tle. gpplicibety aithe^irniti iCond trraio ohthee e of.iathe pei ification 3 OA>b0a1Io Sil rl!geneasil ptce a aslaes rikis asd and nanaged as stated aboye. i;Howevertlthere 4ssarsmall subset of systems tand components that havc en. dteiinne~d ~tip ~ior.. ,, ] ^. i't'Zl6 zitci smiot amplicable peclcation3ao.0 4tallows entij'into an"OPERATIONAL MODE or otherdspecified conditionira hlpcIabilty withthe LimiiifiAgdOndi WOperation,, no mti p t att pcficationlhich states is apiable TIhte stpecific i^liowanices~pernmit SpecE~iTIMeifipcaion ediht^o.0.4.c0.4aa owaneas ssiaied' ACTIO~s to be jmtord daon t continued operation for aniiiunllte rd ef3i&Xd ~aisk='sessmtbwwnotlewpifr . Th is allow nceiipp~~ o ']lhe h<iise of Specification 3 c +fiTcifiiclf onThe risk asThse ntirfte jto ec fovation~owhisch cfct~hbil ne sue oabecucalon'.~u.4 ~

-suall~~hy,,ol;consider systems ahd :ompo~nents a*For, this .reason' pecifICation 3.04 c ilS typmcaiiy~aappledf&oSpecilfcations ,whmch~describe, vatues iand .parameters 46acstattedpci

,,e,5g.,,,,ReA,4oar loowast 'i, rpnmteo aent b Rff pODEcifirthnspbased _ e_

lequtatory nlant-sne'cifipc~V.i lwow Commissions i nd ZODES or thifisteofill~onto§ inte plcaltehtrsu foanun htdn,'n xssoDiatES OPERATIUNA cODEiion indothe t e^pfomafi h tmie4o^an orotalpp ygIf his contexts a unitshutdopejliscdefineaas a changeot u&PERATIONAL MODE or'O s onditiont the Apl'catiityio associated hti'th0transitiornng bldmi, eMODE' OPERATaONAL EdRT A eMOeE ____an e MODP DPE1PTIONAiMODEI'3fElTTif ,

_ hti3s ititoxtan ;PERATIAL;MODE ihsbi-- fied-condition -in'-th-eA'jAp-libi Wbi he1lsFLla1tmgszo iaotlohW for .ueratbfoined onot ihesoicated o aoonp variabee

~utsidetthe~specified limits) j5srihitted by 'efiain401?;TreeulzngScfcton p.otbeenperfsored is'no~ta'-ilto o'f Sup&fcmih inoperable equipment Spcif'ati iS~ribnOAfbiat'io.Siirveiliacasthce

,Howeye SurveillanceRequirem mustib'e',,net vithp~ Iimit)jadresoring c'jj~5Xvmthe tenditoi'f&at

3/4 BASES 3/4.0 APPLICABILITY 4.0.1 This soREifeatien provides that surveillance aetiyities neeessary te insure the Limiting Conditions f.F Operation arem et and ,ill be performed during the OPERA TIONAL MODES or o ther conditio ns fo wr hich the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed regard without to the applicable OPERATIONAL MODES or other conditions are provided the in individualS Rrements.

4.0.2 This specification establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an1 8-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is 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. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

Specification 4.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a surveillance has not been completed within the specified surveillance interval. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less, applies from the point in time that it is discovered that the surveillance has not been performed in accordance with Specification 4.0.2, and not at the time that the specified surveillance interval was not met.

This delay period provides adequate time to complete surveillances that have been missed. This delay period permits the completion of a surveillance before complying with ACTION requirements or other remedial measures that might preclude completion of the surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the surveillance, the safety significance of the delay in completing the required surveillance, and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements. When a surveillance with a surveillance interval based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, Specification 4.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the surveillance.

Specification 4.0.3 also provides a time limit for completion of surveillances that become applicable as a consequence of MODE changes imposed by ACTION requirements.

Failure to comply with specified surveillance intervals for surveillance requirements is expected to be an infrequent occurrence. Use of the delay period established by Specification 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend surveillance intervals.

COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 0-4 AMENDMENT46,4-43,W

INSERT 2 SpeciticationA.U.'1Lestablishes' thee 'requirement that-Surveillance"Requiremernts must ,be mtet luriing hO iOi I AMOD Sik eipe ciioisn, Apicabili o the 0thtl tCondition6r idn>oripl unlessioorwise WiediuirerRns- fthitimitin q s. ip iseci ie he

)'erforme'd tov~e'rify thO@PERAB8IL'ITY ofsystemsT S d6cintentsj andth>fviria cidifdu tSurveiIr umetiar Surveits ithehsueifiedjllHenwit, ldVriMyes pSii6ti6 .2,Wcoxi stiiite,+ s. a.faiuret..iet 'imtiggA __di.tionfo.p.,at~iontS vk, system~~L nents aueecyPEaccorEncewit corn uav~ilie R?4iiients orf m

.4~bWi Thegqu4E-lt.ir;mentspp@ of

,:§,X~aheg~ SiiivEillanc_ < ar*nw~ntob etbetwervrqu

~uii11aneprfrmanieskP"

~~~~Thlances do~b Fntae~Wobe priortdwhen'the 'urnt ~iijs~imn-t~i,'OERATION4ALflvIODE~i

&specfiedlAcondlit i forhhO&h the reqilrements of the associated rLitiingi zondition 5for

~pisfin ieioai7plcle uls ohrie pcfedgTeSurveillqu iirReumeent le evients ysaisf eeuireets(ncbe ptancecriteriq) Tg he~perf~i-mance'bf$h&S~eilyant RIequirementsIASilowanc includesicablsSuylli uirwelnents>wh'ose~perfnarice eisnormally precludedotnar giiventdAT AMODEgorr urelacs mvo bylcngte equired Adios, o~othgp o~eneonned p

,m ', iiiiithion of ,inteRnancce, ap atse postdmantenagn&& iguls eqreegd toaii e 4iiipieht OPERABLE; This includes ensuring appli&~ica Siiivell~ances~ are noti faiied and the~ir gteitprfranei g~gggin' s codnewt Speitifeci tdnd 4.0 2 P?-st m~aintegnantce te4tiWii

'ab ji6sibl&in the scubi OPRAIODAOE brother specified ondai~itio 4idi Npp~itcabilitiuetoi'du~neessa'°yj 2trs4>5iz.l i hcsd titiaij~gQ~~th'q mntmybconsi dere PEALE grovidedtsighsbensatsatorily ornpleted

.%'compleion6f-eFa totthe .extent gpossible tr (aFVppr :4isst ~othemtiseestingap 9and '~the 9equipment)s~tiimbne~ainteniance. belieyed iel~ihhrequirelA*,elr

,to 9be 9mapbe-o ujpfi~h'OPRAB'E. sattemea ~

Sy i Pe;rABEYj isjjo tiran estngatstam prssurs'9OOi.7Hwie@rif othe tsftil

'p'a~tsii~i fining i ion 1 w r in- c n

~ ~,mg'li~

,g,,,ese~~~~~~~t fid'a atyp~

uteamlpressu i o pRe vrsotfeavienseentesteAb I

3/4 BASES 3/4.0 APPLICABILITY 4.0.3 (Continued)

If a surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the time limits of the ACTION requirements for the applicable Limiting Condition for Operation begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the equipment is inoperable or the variable is outside the specified limits, and the time limits of the ACTION requirements for the applicable Limiting Condition for Operation begin immediately upon the failure of the surveillance.

Completion of the surveillance within the delay period allowed by this Specification, or within the completion time of the ACTIONS, restores compliance with the Limiting Condition for Operation requirements.

4.0.4 In This specification ensures that the surveillance activities asociated with a Limiting Condition for Operation have been peerformed within the specified time inten.aI priorNto en" into an OPERATIONAL MODE other or applicable condition. The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.

Under the tevrs of this specification, for example, during initial plant staftup or- following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance inter.al prior to placing or returning the system or equipment into OPERABLE status.

COOK NUCLEAR PLANT-UNIT I Page B 3/4 0-4a AMENDMENT 263

INSERT 3 e bei 4&e0establishes thet~rerquirement >that-all 'p'plicabl& Su'rv§eila~nce &Requiremrentsmust into afn,,,OPERATI 01Af MODE $6fi'd -- --

hi 'ea 6i ti~ii7on ~jensures t st irAdc'mpneifO iPERXB-IT,1Y r~Iiirees and variable ie<mitsaret IS before ensues t~pelficatln fe.t--bhntO ryainritoPERATIONALIMODES lxsystemsana co6ffp or ~rlEaf ioet¢.PsABILI requol'-raetion'conditions other specified .ofts~uhtan invae'A the tplcblt.or-wlc mlts r a hse.

rt ytems~tan O omoentsisuie d

Oendtorsinge -. < ae/oealno te.nttth .the thpeclfai~ea ionxercise oodwevractneo f ,rtifgi qems flIpngcooneitasyto OPERAB Es men illn oftths:ipcfi iictatlnxhua^o3 '-Urpet dasendosmgqueifluet~xrl 2h tprovision ea stspe cuded o ieMODE.6r;other specifiea .condition n.the ppuicabli.tywhena .>iLiiitig Coiidition -.or Operabon lsnno et daue .to Suvilne.nttym

- et-ocijd mn ac&6iduance

~wltn-S ecificaiion 3.0A4 ifeifiddondiJitin te Ap4icthe%

Sowever,t ~incertain circumstances xaling to~rneet -a .urveillance' Requirement fwll notrresult iim pecification ~3 04 -restricting <an uPERAiTIONAL MODE: change or other specified'coiidtiion

,nne.Shn. .ytm subsystem, cBvson*.cmoedevice, or s.variable ;is inojerbIeD r utszde ilts2 specified Slimits :the gassociatd .$urv~eillance ;Requitrement s) flre not. required to}tb~e erformed,-perSpecification"40, thatsurveillances do not havte'tobbeperformed'on noperable equipment"When equpment iis mopjerable, Specification 4' 04. does not apply tothe ssociate Surveillance Requirement(s) slnuceiih remeinrih fAor-the Survell ance Requirhment(s o oe deroredsis reoedTe perormd rOemoved inefoeiln a-toor~e~lfai in~gi p~erform perfor the-Itre a Surveilllances) M

.within the specfled requency in SoesWC' peificatikii rsition s to g O ATI ODjESor 4it^~~~~~se

'.w ^<fI othper .Qtmi b ife~lconditi~

ie-d t'bndiiitkgA<> i gr iftc Applicabityi-s i 4>t "I "Hoeer t>tsb: icee it>*i-t.eY~ th i~iij iti;

>,.in vondition for Operation is not met in thismstanc,, Specification 3,0.4Iwill govern anyrestrictons Itar iikarV(6or giaS'jf ?xy ~

'i iiWitwiugtr esm aN inot)ag toXPERATIANUs'pODE]IA oied jdVie~6NDsO~,bkjthkro'rp~'the'as~cnitiehd tonditio)hages.

ondeuons ofIthe:.ADDI~cabllltv'dwhenta Surveillance ~has ~notbeen pertormed wlthmine specified iiaccr~nce ~I ecihciin41~

lreivi-P g Xh,~

le provisions, o Sp'dfc~ti~tonl 4.0. 'shall no t'- 'revent Xe~ntrytsmnto~'uPERA lONA~IZMOl Zs.~or zther 6iecified con'ditons (In athe pliabiith& arrequired to - ly ith CTIONs In dtion6 dtor~j th 'ahfeifiin6 jmprovisions ofiSpe iflcationTA4.0.4AshaInges^Imr:OPnu-lONai o~rvfh~1i~PRTO uDES'orbot er~specd ied. conditlns-initheyapla~lyta reutfoinyI nitshitdo'nFl 4piit'lat;^Jt~~I"",'fin itioLEI nnte WODE i2a OPERATIONAL2MODEg2o 8 OPERTIbNAL 'MODE ', 4tOPERATIONMMODEE 3 mo OPEkATIONAMOE 'ad tOPER1INXLMODE4tt OPERi4IIONM A;MODP

314 BASES 3/4.3 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Cook Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the re-evaluation of the specific activity limits of this site. The re-evaluation may result in higher limits.

Reducing Ta.g to less than 500'F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if'justified by the data obtained.

40'yj~~

fic~~~.tk -

Page B 3/4 4-5 ANIENDMENT 144, 466, 400,238 NUCLEAR PLANT-UNIT I COOK NUCLEAR PLANT-UNIT I Page B 3/4 4-5 AMENDMENT 44, A6, A, 238

3/4 BASES 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 3507F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps, except the required OPERABLE charging pump, to be inoperable below 1520 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration', (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

YIODE~~~~4~~ ~ i~:g'OERAT`IONMJMOD RAINi jd- toIRF& FA-Vi - -I

' Observing these limits while flow balancing the SI pumps in the injection mode will ensure they are not exceeded in the recirculation mode (RHR pumps provide a suction pressure boost) due to the higher system resistance resulting from splitting of the SI trains when in the recirculation lineup.

I COOK NUCLEAR PLANT-UNIT I Page B 3/4 5-2 AMENDMENT 88,4-58,4-P, 229

3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant system can be cooled down to less than 350'F from normal operating conditions in the event of a total loss of off-site power.

Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators. The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.

This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant system temperature to less than 350'F when the Residual Heat Removal system may be placed into operation.

The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60'F.

Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions.

In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation). During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.

The auxiliary feedwater flowpath, with a pump and associated water supplies and piping, will support shutdown cooling requirements of Unit 2. This capacity addresses the 10 CFR 50 Appendix R safe shutdown requirements.

Fire watches posted in the affected opposite unit areas (i.e., Unit 2 areas requiring use of the Unit I auxiliary feedwater system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specification 3.7.1.2. In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per the Administrative Technical Requirements Manual and establish hourly fire I watch patrols. The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfilling its intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure. An additional procedure details how the above noted fire watches will be implemented.

COOK NUCLEAR PLANT-UNIT I Page B 3/4 7-2 AMENDMENT 131, Revised 07/31/02

3/4 BASES 3/4.8 ELECTRICAL POWER SYSTEMS For surveillance requirements 4.8.1.1.2.e.4.b, 4.8.1.1.2.e.6.b, and 4.8.1.1.2.e.11, the requirement to verify the connection of permanent and auto-connected loads is intended to satisfactorily show the relationship of these loads to the DG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance, ECCS injection valves are not desired to be stroked open, or high pressure injection systems are not capable of being operated at full flow, or RHR systems performing a decay heat removal function are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of connection and loading of loads, testing that adequately shows the capability of the DG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified.

~~6hs~f2Sj ~pficatllon no Jese1,fgnertr 4,h Jar-nrwdik attibnPorrMpation.ir r<'fu'ttc*vt

[2ocati'o wth~~~~~~~g15 Ei:) O D E~~~~~~o2 Iothrs"

_ ~ ,~ ~~ ~~~~~~~~~~~~~~~~~o epc COOK NUCLEAR PLANT-UNIT I Page B3/4 8-3 AMENDMENT Revised 5/27/03

Attachment lb to AEP:NRC:3304 UNIT 2 TECHNICAL SPECIFICATIONS PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT 2 3/4 0-1 3/4 3-20 3/4 3-53 3/4 7-1 3/411-3 3/4 0-2 3/4 3-20a 3/4 4-20 3/4 7-5 6-9 3/4 0-3 3/4 3-21 3/4 4-29 3/4 7-10 B 3/4 0-1 3/4 1-11 3/4 3-34 3/4 4-31 3/4 7-12 B 3/4 0-3 3/4 3-2 3/4 3-36 3/4 4-33 3/4 7-13 B 3/4 0-4 3/4 3-3 3/4 3-38 3/4 4-34 3/4 7-14 B 3/4 4-5 3/4 3-4 3/4 3-38a 3/4 4-36 3/4 7-25 B 3/4 5-2 3/4 3-5 3/43-39 3/4 5-3 3/4 8-2 B3/4 7-2 3/4 3-15 3/4 3-42 3/4 5-7 3/4 9-12 B 3/4 8-3 3/43-18 3/43-44a 3/46-9a 3/4 11-1 3/43-19 3/43-45 3/46-13 3/4 11-2

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification, except as proviced in Specification 3.0.6.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification, except as provided in Specification 3.0.6. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

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

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

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications.

3.0.4 Entry into an OPERATIONAL MODE cr other specified applicability condition shall not be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION statements unless other-wise exccpted. This provision shall not prevent passage through OPERATIONAL MIODES as required to oml B Tit ACTO oraoh's' ti _c

-e~

pflidbilii1i& 4 f ~

wane ~ ~ adi ~ ~M ~ i 3;~axk

~i 6nit 3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (I) and (2) are satisfied, COOK NUCLEAR PLANT-UNIT 2 Page 3/4 0-1 AMENDMENT.30, 246

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

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

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

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

This Specification is not applicable in MODES 5 or 6.

3.0.6 Equipment removed from service or declared inoperable to comply with ACTION requirements may be returned to service under administrative controls solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Specifications 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SURVEILLANCE REQUIREMENTS

_L_81 L_ .1 _'__ sL _ anon A BLAT A I s ZAtLO __ COWL__

4.0.1 Sur~iI~nc~Roomur-ments shall he annhicable rs Our-mLg the (JI-'EKA41(NAL. N4014h or otier- conditions 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

If it is discovered that a surveillance was not performed .within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less. This delay period is permitted to allow performance of the surveillance.

If the surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

When the surveillance is performed within the delay period and the surveillance criteria are not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

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

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 0-2 AMENDMENT 150,430,4476,245 I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY 4.0.4 Entry into an OPERATIONAL M4ODE or other specified applicability condition shall net be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as other.ise seie AZiO theris eafied condltlonr~m,-lheWA~ppicabilityi-6f wtmirinngR onditid foraOperabon shall oIl rbesmade he, h 1fitnCdf~i~~ tnsSArv il a ceshav 'been' iiikt within t~heirispecifi~d.fr~ie~c Jroide iuPERASurlAdtiuD uneplacsnthvnz~ ebe,>n orohr.14lie odiin ri...

.<-i"-'.' mZ. 52dy +/-I*anrn+

,&-4*ttf-r<rarit.MFsWSa~ =,>Xmr a38 .rtb u-A~iJt.21*t

-=, ti. -nou-'. I rv."'. 111m ) ujliewcondivions,m!

&i 'Ka.,oij44 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 performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.

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 Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for inservice inspection and testing activities inservice inspection and testing criteria 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 Yearly or annually At least once per 366 days

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

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

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

4.0.6 Deleted 4.0.7 Deleted COOK NUCLEAR PLANT-UNIT 2 Page 3/4 0-3 AMENDMENT -78,9-7,4-34,224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3

a. One charging pump in the boron injection flow path required by Specification 3.12.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

b. One charging flow path associated with support of Unit I shutdown functions shall be available.*

APPLICABILITY: Specification 3.1.2.3.a. - MODES 5 and 6 Specification 3.1.2.3.b. - At all times when Unit I is in MODES 1,2,3, or4.

ACTION:

a. With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes except: 1) heatup or cooldown of the reactor coolant volume provided that SHUTDOWN MARGIN sufficient to accommodate the change in temperature is maintained in accordance with Specification 3.1.12 in MODE 5 or Specification 3.9.1 in MODE 6, and the heatup or cooldown rate is restricted to 50'F or less in any one-hour period in MODE 5, or 2) addition of water from the RWST, provided the boron concentration in the RWST is greater than or equal to the minimum required by Specification 3.1.2.7.b.2.

b. With more than one charging pump OPERABLE or with a safety injection pump(s)

OPERABLE when the temperature of any RCS cold leg is less than or equal to 152 0F, unless the reactor vessel head is removed, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within one hour.

c. The provisions of Specification 3.0.3 are not applicable.

d. In addition to the above, when Specification 3.1.2.3.b is applicable and the required flow path is not available, return the required flow path to available status within 7 days, or provide equivalent shutdown capability in Unit I and return the required flow path to available status within the next 60 days, or have Unit I in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e. The rceuir-ements f Specification 3.0.4 are nct appliVabl Specification Awhen 3.t2.3.b OPPlies.

SURVEILLANCE REQUIREMENTS 4.1.2.3.1.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5

A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 1520F.

COOK NUCLEAR PLANT-UNIT 2 Page 314 1-II AMENDMENT 8, 407, 446, 488, 213

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

1. Manual Reactor Trip 2 1 2 1,2 and

12

2. Power Range, Neutron Flux 4 2 3 1, 2 and

2#

3. Power Range, Neutron Flux 4 2 3 1,2 2# I High Positive Rate

4. Power Range, Neutron Flux 4 2 3 1,2 High Negative Rate

5. Intermediate Range, Neutron 2 2 1,2and* 3 Flux I

6. Source Range, Neutron Flux A. Startup 2 2 2## and

4 B Shutdown 2 0 1 3, 4 and 5 5

7. Overtemperature AT 4 2 3 1,2 Four Loop Operation

8. Overpower AT Fo ur 4 2 3 1,2 Loop Operation AMENDMENT 82 2 Page 3/4 3-2 NUCLEAR PLANT-UNIT COOK NUCLEAR PLANT-UNIT 2. Page 314 3-2 AMENDMENT 82

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

9. Pressurizer Pressure-Low 4 2 3 1,2

10. Pressurizer Pressure-High 4 2 3 1,2

11. Pressurizer Water Level-High 3 2 2 1,2

12. Loss of Flow - Single Loop 3/loop 2/loop in any 2/loop in each (Above P-8) operating loop operating loop I

13. Loss of Flow - Two Loops 3/loop 2/loop in two 2/loop in each

.1 (Above P-7 and below P-8) operating loops operating loop

14. Steam Generator Water Level- 3/loop 2/loop in any 2/loop in each 1,2 Low-Low operating loop operating loop

15. Steam/Feedwater Flow 2/loop-level and Iloop-level I/loop-level 1,2 Mismatch and Low Steam 2/loop-flow coincident with and 2/loop-Generator Water Level mismatch in same 1/loop-flow flow mismatch loop mismatch in or 2/loop-level same loop and I/loop-flow mismatch COOK NUCLEAR PLANT-UNIT 2 Page 3141 3-3 AMENDMENT 45,107

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

RIEACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

16. Undervoltage-Reactor Coolant 4-1/bus 2 3 I 6#

Pumps

17. Underfrequency-Reactor 4-1/bus 2 3 6X-Coolant Pumps

18. Turbine Trip A. Low Fluid Oil Pressure 3 2 2 7bt B. Turbine Stop Valve 4 4 3 6#

Closure

19. Safety Injection Input from 2 2 1,2 ESF

20. Reactor Coolant Pump Breaker Position Trip Above P-7 I/breaker 2 I/breaker per 11 operating loop .

21. Reactor Trip Breakers 2 I 2 1,2, 13, 15 3*, 4*, 5* 14 I

22. Automatic Trip Logic 2 2 1,2 3*, 4*, 5* 14 NUL ALNg / - M N M N 6 - ,42,4 2 6

~ - ~

COOK~~~~~NT~ 2P~

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-4 AM ENDM ENT 86,447,4-27, In, 260

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

TABLE NOTATION

With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

,. The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION I - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 4.3.1.1.1.

ACTION 2 - 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:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable 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 of the other channels per Specification 4.3.1.1.1.

c. Either, THERMAL POWER is restricted to

75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER 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.c.

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

AMENDMENT 8, 236 2 Page 3/4 3-5 COOK NUCLEAR PLANT-UNIT COOK NUCLEAR PLANT-UNIT 2 Page 314 3-5 AMENDMENT 82,236

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Manual Initiation -- See Functional Unit 9

b. Automatic Actuation 2 I 2 1,2,3,4 13 Logic

c. Containment Pressure 3 2 2 1,2,3 14

- High

d. Pressurizer Pressure - 3 2 2 1,2,3' 14!

Low

e. Differential Pressure Between Steam Lines -

High Four Loops Operating 3/steam line 2/steam line 2/steam line 1, 2, 3"' 141 any steam line Three Loops 3/operating steam 1#"/steam line, 2/operating 15 Operating line any operating steam line steam line

f. Steam Line Pressure -

Low Four Loops Operating I pressure/loop 2 pressures any I pressure any 14A loops 3 loops Three Loops I pressure/ 1/ pressure in - I pressure in 3## 15 Operating operating loop any operating any 2 operating loop loops COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-15 ,AMENDMENT8-2,137

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

4. STEAM LINE ISOLATION

a. Manual - See Functional Unit 9 - -

b. Automatic Actuation 2 I 2 1,2,3 13 Logic

c. Containment Pressure - 4 2 3 1,2,3 16 High-High

d. Steam Flow in Two Steam Lines -- High Four Loops Operating 2/steam line 1/steam line I/steam line 1,2,3" 141 any 2 steam lines Three Loops Operating 2/operating steam l'"/any I/operating 15 line operating steam steam line line COINCIDENT WITH TV - Low-Low Four Loops Operating I T,/Ioop 2 T.VS any loops I T,, any3 1,2, 3" 141 loops Io T,, in any Three Loops Operating I T.Woperating operating loop I T., in any 15 loop two operating loops I

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-18 AMENDMENT 8-2,137 I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

e. Steam Line Pressure-Low Four Loops Operating I pressure/loop 2 pressures any I pressure any loops 3 loops Three Loops Operating I pressure/ IM pressure in I pressure in 3# 15 operating loop any operating any 2 operating loop loops

5. TURBINE TRIP &

FEEDWATER ISOLATION

a. Steam Generator Water Level - High-High 3/loop 2/loop in any 2/loop in each 1,2,3 14+/-

operating loop operating loop

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 141 Level - Low-Low any Stm. Gen.

b. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3 141 Voltage Pump Start 2/bus (TI IA -

Train B; TI ID

- Train A)

Valve Actuation (Both 2/bus on (TIIA trains) &TIlBor 2/busses TI IC

&TIID) l

c. Safety Injection 2 2 1,2,3 181

d. Loss of Main Feedwater 2 2 2 1,2 181 Pumps COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-19 AMENDMENT 8Z, 4-34,137 I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS TO CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TRIP OPERABLE MODES ACTION

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. any 2/Stm. Gen. 1,2,3 141 Level - Low-Low 2 Stm. Gen.

2

b. Reactor Coolant Pump 4-1/Bus 3 1,2,3 I91 Bus Undervoltage

8. LOSS OF POWER

a. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3,4 141 Voltage

b. 4 kV Bus Degraded 3/Bus 2/Bus 2/Bus 1,2,3,4 141 Voltage (TIIA-TrainB) (TI lA-Train B) (TI IA-Train B)

(TIID-TrainA) (TI ID-Train A) (TI ID-Train A) I

9. MANUAL

a. Safety Injection (ECCS) 2/train I/train 2/train 1,2,3,4 18 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray I/train 1/train I/train 1,2,3,4 18 Containment Isolation -

Phase "B" Containment Purge and Exhaust Isolation

c. Containment Isolation - 1/train 1/train I/train 1,2,3,4 18 Phase "A" Containment Purge and Exhaust Isolation

d. Steam Line Isolation 2/steam line (I per 2/steam line (I 2/operating 1,2,3 20 train) per train) steam line (1 per train)

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-20 ADMENDM ENTX,420,4A,4-7, 224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

e. Containment Air I/train l/train I/train 1,2,3,4 18 Recirculation Fan

10. CONTAINMENT AIR RECIRCULATION FAN

a. Manual sNee eFunctional Unit 9

b. Automatic Actuation 2 I 2 1,2,3 13 Logic

c. Containment Pressure - 3 2 2 1,2,3 141 High COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-20a ADMENDMENT217

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be bypassed in this MODE below P- I1.

Trip function may be bypassed in this MODE below P-12.

1. 1. The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

1. ~## Manually trip all bistables which would be automatically tripped in the event pressure in the associated active loop were less than the pressure in the inactive loop. For example, if loop I is the inactive loop then the bistables which indicate low pressure in loops 2, 3 and 4 relative to loop I should be tripped.

-1he uorovisions of Snecifieation 4.0.4 are not anakeiable.

bA ]

ACTION STATEMENTS ACTION 13- With the number of OPERABLE Channels one less than the Total Number of Channels, 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 ; 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 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 15- With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel associated with an operating loop 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 4.3.2.1.1.

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 the 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 4.3.2.1.1.

COOK NUCLEAR PLANT-UNIT 2 Page 314 3-21 AMENDMENT 82,4-34,137

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

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

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

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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

COOK NUCLEAR PLANT-UNIT 2 Page 314 3-34 AMENDMENT43,224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.9.9. This ACTION is not required during the performance of containment integrated leak rate test.

ACTION 22A- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. Technical Specification Sections 3.0.3 and404 Not Applicable.

I ACTION 22B- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. In the event of an accident involving radiological releases initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Technical Specification Sections 3.0.3 and-34 Not Applicable.

I COOK NUCLEAR PLANT-UNIT 2 Page 314 3-36 AMENDMENT80,44-9,151

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles,

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

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

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the excore neutron flux detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of FNH and FQ(Z).

ACTION:

With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3:2 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output when required for:

a. Recalibration of the excore neutron flux detection system, or

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of FNH and FQ(Z).

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-38 AMENDMENT 82

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION SEISMIC INSTRUMENTATION*

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

APPLICABILITY: At all times.

ACTION:

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

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

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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

4.33.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed 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. 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.

Shared System with D.C. Cook Unit I.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-38a AMENDMENT 45

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION*

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

APPLICABILITY: At all times.

ACTION:

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

b. With one or more required meteorological monitoring channels inoperable for more than 7 days, 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.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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.

Shared System with D.C. Cook - UNIT I.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-39 AMENDMENT 45

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. The provisions of Specification 3.0.1 arc not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 342

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The Appendix R remote shutdown instrumentation channels shown in Table 3.3-9A shall be OPERABLE with an opposite unit power supply available and with read out capability at the LSI panels.

APPLICABILITY: MODES 1, 2, and 3 ACTION:

a. With the number of OPERABLE Appendix R remote shutdown monitoring channels less than required by Table 3.3-9A, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the opposite unit power supply not available, restore the power supply to available status within 7 days, or provide fire watches in the affected areas and restore the inoperable channel to OPERABLE status within the next 60 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c. The provisions of Speciflcation 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each Appendix R remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6A.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 344a AMENDMENT 116

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10 (except item 8), either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE post-accident monitoring channels one less than required by Table 3.3-10, item 8, Refueling Water Storage Tank Water Level:

I. Either restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

2. Within one hour, bypass the Residual Heat Removal Pump trip function from the Refueling Water Storage Tank Water Level for the pump associated with the out-of-service instrument.

c. The provisions of Specification 3.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-45 AMENDMENT215

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specifications 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With an explosive gas monitoring instrumentation channel alarm/trip setpoint less conservative than the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days. If unsuccessful, prepare and submit a SPECIAL REPORT to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and analog CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

COK ULERPLNTUIT2Pae3/ 35 AEDMNT$, 4,_7 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-53 AMENDMENTS4,4-38,175

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to I microCurie per gram DOSE EQUIVALENT I-13 1, and

b. Less than or equal to 100/ E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3

a. With the specific activity of the reactor coolant greater than 1 microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval for exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T,,p less than 500TF within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the reactor coolant greater than 100/ E microCuries per gram, be in HOT STANDBY with T.,, less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ERZ ~ jitih~04isapl~I MODES 1, 2, 3, 4 and 5

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 or greater than 100/ E microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.

SURVEILLANCE REOUIREMENTS I

4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

I With Tang greater than or equal to 500'F.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-20 AMENDMENT 129

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a lift setting of less than or equal to 435 psig, or

b. One power operated relief valve (PORV) with a lift setting of less than or equal to 435 psig and the RHR safety valve with a lift setting of less than or equal to 450 psi, or APPLICABILITY: Mode 5 when the temperature of any RCS cold leg is less than or equal to 1527F, and Mode 6 when the head is on and fastened to the reactor vessel and the RCS is not vented through a 2-square-inch or larger vent or through any single blocked open PORV.

ACTION:

a. With one of two PORVs required by item a above or either the PORV or RHR safety valve required by item b above inoperable, either (I) restore the inoperable PORV or RHR safety valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months . Maintain the RCS in a vented condition until the inoperable PORV or RHR safety valve has been restored to OPERABLE status.

b. With both PORVs and the RHR safety valve inoperable, complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Maintain the RCS in a vented condition until both PORVs or one PORV and the RHR safety valve have been restored to OPERABLE status.

c. With the RCS vented per ACTION a or b above, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. In the event either the PORVs, the RHR safety valve or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

e. The provisions of Specification 3.0.4 are not applicable.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-29 AMENDMENT39,161

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1.2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10. 1.

APPLICABILITY: ALL MODES ACTION:

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

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.

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

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-31 AMENDMENT 39,201

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

g. With PORVs and block valves not in the same line inoperable due to causes other than excessive seat leakage, within I hour restore the valves to OPERABLE status or close and de-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.

I - - - I __I:L -II fl. the pr-eyisien5 01fapccifiiatien j.0.4 arc not appnicabie.

SURVEILLANCE REQUIREMENTS 4.4.11.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and

b. At least once per 18 months by operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

c. At least once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and

d. At least once per 18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation. I 4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.1 1.

4.4.11.3 Deleted.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-33 AMENDMENT 4a, 458, 449, 64, 496, 224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM REACTOR VESSEL HEAD VENTS LIMITING CONDITIONS FOR OPERATION 3.4.12.1 At least one of the Reactor Vessel head vent paths, consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Reactor Vessel head vent paths inoperable, and at least one of the Pressurizer steam space vent paths OPERABLE (see Specification 3.4.12.2), operation in MODES 1, 2, 3 or 4 may continue, provided the inoperable vent paths are maintained closed with power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Reactor Vessel head vent paths within 30 days 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 .

b. With both of the Reactor Vessel head vent paths and both of the Pressurizer steam space vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

c. The provisions of Speciflcation 3.0.1 are not applicable.

COOK NUCLEAR PLANT-UNIT 2 Page 314 4-34 AMENDMENT 65

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS LIMITING CONDITION FOR OPERATION 3.4.12.2 At least one of the Pressurizer steam space vent paths, each consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Pressurizer steam space vent paths inoperable, and at least one of the Reactor Vessel head vent paths OPERABLE (see Specification 3.4.12.1), operation in MODES 1, 2, 3 or 4 may continue, provided the inoperable vent paths are maintained closed with the power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Pressurizer steam space vent paths within 30 days 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 in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both of the Pressurizer steam space vent paths and both of the Reactor Vessel head vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

C. -1he DrFovisionz or Specification 3.i.q~ are no3t a0Danca4e.

COOK NUCLEAR PLANT-UNIT 2 Page 314 4-36 AMENDMENT 65

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T,, 2 3500 F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a. One OPERABLE centrifugal charging pump,

b. One OPERABLE safety injection pump,

c. One OPERABLE residual heat removal heat exchanger,

d. One OPERABLE residual heat removal pump,

e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.

f. All safety injection cross-tie valves open.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With a safety injection cross-tie valve closed, restore the cross-tie valve to the open position or reduce the core power level to less than or equal to 3304 MW within one hour. Speeification 3.0.4 does not-apply

c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 5-3 AMENDMENT447,259

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ECCS SUBSYSTEMS - T. < 350 0 F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump,"

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Ta.V less than 350'F by use of alternate heat removal methods.

c. With more than one charging pump OPERABLE or with a safety injection pump(s) OPERABLE when the temperature of any RCS cold leg is less than or equal to 1520F, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within I hour.

d. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

A maximum of one centrifugal charging pump shall be OPERABLE and both safety injection pumps shall be inoperable whenever the temperature of one or more of the RCS cold legs is less than or equal to 1520 F.

COOK NUCLEAR PLANT-UNIT 2 Page 314 5-7 AMENDMENT 39

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities. No more than one purge supply path and one purge exhaust path shall be open at a time.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , either:

1) Restore the inoperable valve to OPERABLE status, or,

2) Deactivate the automatic valve secured in the closed position.

b. Operation may then continue until performance of the next required valve test provided that the automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 31 days.

c. Otherwise, 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. The provisicns of Spvcification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The surveillance requirements of Technical Specifications 3/4.6.1.2 and 3/4.6.3.1 apply.

COOK NUCLEAR PLANT-UNIT 2 Page 314 6-9a AMENDMENT4-7,484,193

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE. Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control. The ACTION statement of Technical Specification 3/4.6.3.1 is not applicable to the containment purge and exhaust isolation valves. The Limiting Condition for Operation and its associated ACTION statement for these valves are given in Technical Specification 3/4.6.1.7.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the containment isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or

d. 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The provisions of Specification 3.0.1 arce not applicable.

SURVEILLANCE REOUIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 6-13 AMENDMENT 4-7,4-53,165

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. MODES I & 2: With 4 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and comply with action statement b.

b. MODE 3: With a minimum of 3 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves associated with an operating loop inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the reactor trip breakers are opened; otherwise, be in HOT SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. The provisions of Specification 3.0.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with lift settings as shown in Table 4.7-1. The safety valve shall be reset to the nominal value +/-1% whenever found outside the +/-1% tolerance. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

COOK NUCLEAR PLANT-UNIT 2 Page 314 7-1 AMENDMENT82,447,195

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2

a. At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

1. Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and

2. One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.

b. At least one auxiliary feedwater flow path in support of Unit I shutdown function shall be available.

APPLICABILITY: Specification 3.7.1.2.a - MODES 1, 2, 3.

Specification 3.7.1.2.b - At all times when Unit I is in MODES 1, 2, or 3.

ACTIONS:

When Specification 3.7.1.2.a is applicable:

a. With one auxiliary feedwater pump -inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in HOT Shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

When Specification 3.7.1.2.b is applicable:

With no flow path to Unit I available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit I and return at least one flow path to available status within the next 60 days, or have Unit 1 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The renuirements ofSoecification 3.0.4 are not abolicable.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-5 AMENDMENT 82,446,151

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator stop valve shall be OPERABLE.

APPLICABILITY: MODES I, 2 and 3.

ACTION:

MODE I - With one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I MODES 2 - With one or more steam generator stop valves inoperable, close the inoperable valve(s) within and3 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and verify the inoperable valves are closed at least once per 7 days. Otherwise, be in at least MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , with the unit in at least MODE 3 within the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The nrevisions of Sneciflcation 3.0.4 arc not amolicable.

SURVEILLANCE REOUIREMENTS 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.

I 4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-10 AMENDMENTS2,435,170

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1

a. At least two independent component cooling water loops shall be OPERABLE.

b. At least one component cooling water flow path in support of Unit I shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.I.a. - MODES 1, 2, 3, 4.

Specification 3.7.3. I.b. - At all times when Unit I is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.7.3.I.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

When Specification 3.7.3.l.b is applicable:

With no flowpath to Unit I available, return at least one flowpath to available status within 7 days, or provide equivalent shutdown capability in Unit I and return at least one flow path to available status within the next 60 days, or have Unit I in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The requirements of Specification 3.0.1 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

c. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per 18 months, verify that the unit cross-tie valves can cycle full travel.

Following cycling, the valves will be verified to be in their closed positions.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-12 AMENDMENT 97, 446,4-, .58, ZU, 257,

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 a. At least two independent essential service water loops shall be OPERABLE.

b. At least one essential service water flowpath associated with support of Unit I shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.1.a - Either Unit in MODES 1, 2, 3, and 4.

Specification 3.7.4.1.b - At all times when Unit I is in MODES 1, 2, 3, or 4.

ACTION:

a. When Unit 2 is in MODES 1, 2, 3, and 4:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. When Unit I is in MODES 1, 2, 3 and 4:

1. With any Unit 2 essential service water pump not OPERABLE, within one hour close at least one crosstie valve on the associated header or have Unit I enter ACTION a for Unit I Specification 3.7.4.1 for the Unit I essential service water pump sharing the same header with the inoperable Unit 2 essential service water pump.

2. With no essential service water flow path available in support of Unit I shutdown functions, return at least one flow path to available status within 7 days, or have Unit I in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The requirements of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.At least once per 18 months by verifying that each automatic valve servicing safety related I equipment actuates to its correct position on a Safety Injection test signal.

c. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per.92 days by verifying that each closed crosstie valve, in the available essential service water flowpath associated with support of Unit I shutdown functions, can be cycled from the control room.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-13 AMENDMENT 9, 446, 43, 458, 459, 24, 235,257

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system (CREVS) shall be OPERABLE with:

a. Two independent pressurization trains, and

b. One charcoal adsorber/HEPA filter unit.

_____ -N~~~OTE-----------

The control room envelope/pressure boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, and during the movement of irradiated fuel assemblies.

ACTION:

MODES 1, 2, 3, and 4:

a. With one pressurization train inoperable, restore the inoperable train to OPERABLE status within 7 days 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the filter unit inoperable, restore the filter unit to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With two CREVS pressurization trains inoperable due to an inoperable control room envelope/pressure boundary, restore the control room envelope/pressure boundary to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

During the movement of irradiated fuel assemblies:

d. With one pressurization train inoperable, restore the inoperable pressurization train to OPERABLE status within 7 days, or initiate and maintain operation of the remaining OPERABLE train in the pressurization/cleanup alignment. -

e. With any of the following: (1) both pressurization trains inoperable; (2) the filter unit inoperable; or (3) the control room envelope/pressure boundary inoperable, immediately suspend all operations involving the movement of irradiated fuel assemblies.

f. The provisions of Specification 3.0.4 are not applicable to movement of irradiated fuel assemblies.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-14 AMENDMENT443,2S2,258

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 314.7.8 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.8.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of 2 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

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

I. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.8.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

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

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

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

a. Sources in use (excluding startuR sources and fission detectors previously subjected to core flux) - At least once per six months for all sealed sources containing radioactive materials.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-25 AMENDMENT 156

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.8 ELECTRICAL POWER SYSTEMS ACTION (Continued)

c. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. offsite source by performing Surveillance Requirement 4.8.1.1. .a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and if the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirement 4.8.1.1 2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With the diesel generator restored to OPERABLE status, follow ACTION Statement a.* With the offsite circuit restored to OPERABLE status, follow ACTION Statement b.*

d. With two of the above required offsite A.C. circuits inoperable, restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 . With only one offsite source restored, follow ACTION Statement a.*

e. With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.I.1.a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one diesel generator unit restored, follow ACTION Statement b* or c.*

L~~it~cation>3. A4.b i7i lcll tisiitr~

The ACTION statement time shall be based upon the time associated with the component inoperability, and is not reset when exiting this ACTION statement.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class I E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and

b. Demonstrated OPERABLE at least once per 18 months by transferring the unit power source automatically from the normal auxiliary source to the preferred reserve source and by transferring manually to the alternate reserve source.

COOK NUCLEAR PLANT-UNIT 2 Page 314 8-2 AMENDMENT44-2,168

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM**

LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool+ until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted.

2. Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm i 10%.

The crane bay roll-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

- Shared system with D. C. COOK - UNIT 1.

+ This does not include the main load block. For purposes of this specification, a de-energized main load block need not be considered a load.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 9-12 AMENDMENT444,224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS I

LIOUID HOLDUP TANKS*

LIMITING CONDITION FOR OPERATION 3.11.1 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. I

a. Outside temporary tanks.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay 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.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 I days when radioactive materials are being added to the tank.

Tanks include in this Specificatiosn are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents and that do not have tank over flows and surrounding area drains connected to the liquid radwaste treatment system.

COOK NUCLEAR PLANT-UNIT 2 Page 314 1 11-1 AM ENDM ENT -54,4M, 175

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 3% by volume if the hydrogen in the system is greater than or equal to 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 3% by volume but less than or equal to 4% by volume and containing greater than or equal to 4% hydrogen, restore the concentration of oxygen to less than or equal to 3% or reduce the hydrogen concentration to less than 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

b. With the concentration of oxygen in the waste gas holdup system or tank greater than 4% by volume and greater than 4% hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to less than or equal to 3% or the concentration of hydrogen to less than or equal to 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months in the system or tank.

c. The provisions of Specifications 3.0.3 and.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

COOK NUCLEAR PLANT-UNIT 2 Page 314 11-2 AMENDMENT 54,4-38,175 1

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS I GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay 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.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days whenever radioactive materials are added to the tank and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary coolant system degassing operations.

I COOK NUCLEAR PLANT-UNIT 2 Page 3/4 11-3 AMENDMENT -4, 438, 468, U-S, 214 I

6.0 ADMINISTRATIVE CONTROLS E _R-Q-CEJAMS AND Pb-G-1UAM Mhe e nc r d lM a .e 5 E2e lfic Bases pegrhanationsSiifetyrtroi di~V~iiiat,

L.WFt~a-!Xhe 6.9.1 Bangs do.vtetes rp sChb In add notheapicable require entsof t.nemcto soihePecma norti Titrl K hlb:maeudrk thefollow u oniaitaii pi4dmistraive cnrl ~

laqnd ~ ln r r leioenw hs7s ti7cgarReu Eaor CrhiPio7~proa roYvdd'd OEM

, lffie~~~~~~~~~~~~~~

6.9 REPORTING reports ~all sh REQUIREMENTS besbmte toteRgoa diitao unes ohrisentd ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT-UNIT 2 Page 6-9 COOK AMENDMENT NUCLEAR PLANT-UNIT 2 54,4M,4-75,210 Page 6-9 I

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

3.0.1 This specification defines the applicability of each specification in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 The specification delineates the measures to be taken for those circumstances not directly provided for in the ACTION Statements and whose occurrence would violate the intent of a specification. For example, Specification 3.5.2 requires two independent ECCS Subsystems to be OPERABLE and provides explicit ACTION requirements if one ECCS Subsystem is inoperable. Under the requirements of Specification 3.0.3, if both the required ECCS Subsystems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further example, Specification 3.6.2.1 requires two Containment Spray Systems to be OPERABLE and provides explicit ACTION requirements if one Spray System is inoperable. Under the requirements of Specification 3.0.3 if both the required Containment Spray Systems are inoperable, within one hour measure must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.0.4 This spceification provides that entry into an OPERATIONAL MODE or other specified applicability cenditio mut nade with (a) the full eerinplement of regufred systems, equipment or components OPERABLE and (b) all other parameters as specitied in the Limiting Uendifties for Operation. beiung-met without regard for allowable deviations and out of service provisions contained in the AGTION statements.

The intent of this provision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being t mcz-d.-

Emeeptinns to this provision have been provided fer a limited number of speeifications when stadu_ ith inoperable equipment would not affcet plant safaty. These exceptions arc stated in the ACTION statRnemnts of the appropriate spcifications.

COOK NUCLEAR PLANT-UNIT 2 Page B 3/4 0-1 AMENDMENT30

INSERT I

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&kp'piic fiithh "Xhi, V.iOPERATIONA~L`MODES krbiih RthditinflintmtI ecfi';c~o"dt---~M, cndtioni~as e nta peciicaioi3.O4.aaIows entryyinto, an',PRAIOA MOEo'te- p~ecifle coiiionl Mith, JArm tn<MODel eqiiii~~~~~~~~d iiii~mtcotne prtion, ~ a iihlimi ed p , qrisdsfciate n i PEApicNa iit-j,MOE rohrseiidcniinpk &e

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.e Operations goverrningthese Esystems fand tcomponents s not applicble~

peTclfticon 3o.u.4:c allows entry into an uPE3RAT1luNAL.F1DE or other specified &6ndition'im he 3h ~mtg CApiaiiy3i ondition flor Ouperatioriqnoi iiie~base'd on a Sprovision i the peeifiuaionigwhichIstats >Specificationt3J 0 4.c is applicable Jhese .specific allowances permit

,fntr i~n~t~o OPERATI,,u,~MDES orothr secfii>ed odiinsi .,,.*the Appslcblitywhenl> the ssociatedATIOs td¢ nt d nt roid frontine oeain for an ulimited period fgl,ji e&iik,*:sasseent has not bee Thisalloanceapppgly toallthe NC1TIONs or to a specific ACTION of a unpecificationQhe .risk assessmentsE performned ,to jlustifj he use of Specification 3t04.b: usuallyiov cosarsses n opnnst4Fr hs}esn fiedcification ,30 4.c is itypically apie it pcfctos3nc dsrbvle and iparameters e~.,< eactors:Coolant Actixvitv, and Smay ^be ,pi~ledJ~ St bae 7onhrSpcfeain Nuclear tegulatory Commission plant specific a~pproal1 n'e provisions of-tis Specifiation .s ould notboe'interprete :as endorsing the5failure t6 exercise e.-good practice ;of restoring systems oireniponents to. OPERABLE' status-2befor~e etrv

_sociate2 PERAINLMOEo jecifi coditio*t.~ ~ii e

E ae Sconditions~t ther 5;specified k .h'~AppIicabilitysthatar e c~~~~~~~l, ,cw~~~a,>~en iequiied~to-

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of hEi lii us.~S@p&

j'30'4 ~ tuhcol'Iyath^AG.TIONs~$In sm @ig~i~PRAIN OuDES or other ,specified .conaiibn iziihe~zApplicbililty tnat res~uli } irom 4nyit siudon.^j] I is contexti-a unit shutdown is aefinfea 7a'~a~haneiiimOPERATIONAL MuDE'orsotlir pecified 6~iidiiiXh iithe Applicability assocatedyi~th'~initgioiinr' f~nXPR~OPEATiTO LMODE4n*t ZPETONAL :MODEs2 3OPERATIONAL8MOwDE g jo~PERIOwNAL ODEi3 bPERtATIONAL MdODE A3 to =PRAj pj4gd~PRATOAMD ZPERATIONAL MODEt5

~he Llitmgiiii nditionfoi. peratio~o&me't, S icficati&n 3.OA andSpecificati6nt3.O.2.re4uire entry ihf6 the vACTIONS' until th& ljimitig.Codition forOperajtlonhisem or ntil theuij'isno unelilla~nces do not nave .boJ.ee fer forniea oii the asciuted 'operable quipment (or on varlbles sjid, i..dh limis) 'p dbpciictiB46. :<Th~wf6#e ijjiin 'tag ificai'on u.4 s~not a violation of Specfication 4.0AV6r orSpeflication4.4 <lraySrvllne that hav t ~ofibeenperformed on inoperble~eq flow , SuvetilAnceliequiiemts-, iCbe met L itulmltS)~nd etrng c lS qytth&~ff~iiig oniiofr j

3/4 BASES 3/4.0 APPLICABILITY 3.0.6 This specification establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTION requirements. The sole purpose of this Specification is to provide an exception to the Specifications 3.0.1 and 3.0.2 (e.g., to not comply with the applicable ACTION requirements) to allow the performance of required testing to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTION is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Specification does not provide time to perform any other preventive or corrective maintenance.

An exaimple of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with ACTION requirements and must be reopened to perform the required testing.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other trip system. A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same trip system.

4.0.1 This 3occificatis prnovides that sum.eillanee activitics ncessary to insure the Limiting Conditions for Operation arc met and will be performed during the OPERATIONAL MEODES or other conditions for whielh the Limiting Conditions for Operation. are applicable. Provisir- fo ditional surveillanecc activities to be performed without regard to the applicable OPERATIONAL MIODES or other conditions are provided in the individual Sun,ecillanee Requirements.

4.0.2 This specification establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions Of other ongoing surveillance or maintenance COOK NUCLEAR PLANT-UNIT 2 Page B 3/4 0-3 AMENDMENT 30, 430,246

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3/4 BASES 3/4.0 APPLICABILITY l 4.0.4 Ins This specification ensures that the surveillanoe activities associated with a Limiting Condition for Opratien have beern performed within the specified time interval prior to entry into an OPERATIONTALn NRODE or

........... . A .. P..... .. - . . .. . ... . . ... ..

other applicable condition. The intent of this provision is to ensure that surveillaneeactivitics have been satisfactorily demonstrated on a current basis as required to meet the OPEl 0kBILITY requirements of-the Limiting Condition for Operation.

Under the terms of this speeifieation, for example, during initial plant startup or following e tn l outages, the applicable sureillannc activities must be performed within the stated suryeillanee intcrval prior to placing or returning the system or equipment into OPERABLE status.

4.0.5 This specification ensures 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 will 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. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these technical specifications.

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 consistency in surveillance intervals throughout these technical specifications and to remove any ambiguities relative to the frequencies for performing and 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. For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation.

And, for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

COOK NUCLEAR PLANT-UNIT 2 Page B 314 0-4 AMENDMENT 30

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3/4 BASES 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Cook Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the reevaluation of the specific activity limits of this site. This reevaluation may result in higher limits.

Reducing T,1, to less than 500'F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analysis following power changes may be permissible ifjustified by the data obtained.

~~~ ACTIO pli~l,'b ~ Mt-b COOK NUCLEAR PLANT-UNIT 2 Page B 3/4 4-5 AMENDMENT 129

3/4 BASES 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The limitation for a maximum of one centrifuigal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps, except the required OPERABLE charging pump, to be inoperable below 1520 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analysis are met and that subsystem OPERABILITY is maintained. Surveillance requirements for removal of power to the operators of valves listed in 4.5.2a ensure the valves are single failure proof in accordance with Branch Technical Position 18, Application of the Single Failure Criterion to Manually-Controlled, Electrically-Operated Valves. The reviewed and approved methodology for removal of power to these eight valves is by locking out control power. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration,' (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analysis, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analysis.

ph>ifi6.O'Swis2iiWpp1,3*.i~iadwo ii~ijiEableocia ed ~l~tent~ih mms~ 3whti1W4--rom0PERATIONl RATQN1 ODE5'~ffi

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Observing these limits while flow balancing the SI pumps in the injection mode will ensure they are not exceeded in the recirculation mode (RHR pumps providing a suction pressure boost) due to the higher system resistance resulting from splitting of the SI trains when in the recirculation lineup.

COOK NUCLEAR PLANT-UNIT 2 Page B 3/4 5-2 AMENDMENT 39, 44, 2, Revised 03/03100

3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions in the event of a total loss of off-site power.

Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators. The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.

This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant system temperature to less than 3507F when the Residual Heat Removal System may be placed into operation.

The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 607F.

Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions.

In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation). During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.

The auxiliary feedwater flowpath, with a pump and associated water supplies and piping, will support shutdown cooling requirements of Unit 1. This capacity addresses the 10 CFR 50 Appendix R safe shutdown requirements.

Fire watches posed in the affected opposite unit areas (i.e., Unit I areas requiring use of the Unit 2 auxiliary feedwater system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specification 3.7.1.2. In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per the Administrative Technical Requirements Manual and establish hourly fire watch patrols. The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfilling its intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure. An additional plant procedure details how the above noted fire watches will be implemented.

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COOK NUCLEAR PLANT-UNIT 2 Page B 3/4 7-2 AMENDMENT 82,4U6, Revised 07/31/02

3/4 BASES 3/4.8 ELECTRICAL POWER SYSTEMS For surveillance requirements 4.8.1.1.2.e.4.b, 4.8.1.1.2.e.6.b, and 4.8.1.1.2.e.11, the requirement to verify the connection of permanent and auto-connected loads is intended to satisfactorily show the relationship of these loads to the DG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance, ECCS injection valves are not desired to be stroked open, or high pressure injection systems are not capable of being operated at full flow, or RHR systems performing a decay heat removal function are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of connection and loading of loads, testing that adequately shows the capability of the DG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified.

COOK NUCLEAR PLANT-UNIT 2 Page B 314 8-3 AMENDMENT 5/27/03

Attachment 2a to AEP:NRC:3304 UNIT 1 PROPOSED TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 1 3/4 0-1 3/4 3-21a 3/4 4-21 3/4 7-15 B 3/4 0-lb 3/4 0-2 3/4 3-21b 3/4 4-31 3/4 7-17 B 3/4 0-4 3/4 0-3 3/4 3-22 3/4 4-33 3/4 7-19 B 3/4 0-4a 3/4 1-11 3/4 3-35 3/4 4-36 3/4 7-26 B 3/4 0-4b 3/4 3-3 3/4 3-37 3/4 4-37 3/4 8-2 B 3/4 4-5 3/4 3-4 3/4 3-39 3/4 4-39 3/4 9-13 B 3/4 5-2 3/4 3-5 3/4 3-40 3/4 5-7 3/4 11-1 B 3/4 7-2 3/4 3-6 3/4 3-43 3/4 6-9a 3/4 11-2 B 3/4 8-3 3/4 3-16 3/4 3-46 3/4 6-14 3/4 11-3 3/4 3-17 3/4 3-48a 3/4 7-1 6-9 3/4 3-20 3/4 3-54 3/4 7-5 B 3/4 0-1 3/4 3-21 3/4 3-57 3/4 7-10 B 3/4 0-la

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and* ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification, except as provided in

- Specification 3.0.6.

3.0.2 Adherence to the requirements of the Limiting Condition for Operation and/or associated ACTION within the specified time interval shall constitute compliance with the specification, except as provided in Specification 3.0.6. In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

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

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

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications.

3.0.4 When a Limiting Condition for Operation is not met, entry into an OPERATIONAL MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONs to be entered permit continued operation in the OPERATIONAL MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the OPERATIONAL MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specification, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in OPERATIONAL MODES or other specified conditions in the Applicability that are required to comply with ACTIONs or that are part of a shutdown of the unit.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (I) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, COOK NUCLEAR PLANT-UNIT I Page 3/41 0-1 AMENDMENT2-64

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it as applicable in:

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

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

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

This Specification is not applicable in MODES 5 or 6.

3.0.6 Equipment removed from service or declared inoperable to comply with ACTION requirements may be returned to service under administrative controls solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Specifications 3.0.1 and 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other specified conditions in the Applicability for individual Limiting Condition for Operations, unless otherwise stated in the Surveillance Requirement. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation. Failure to perform surveillance within the specified frequency shall be failure to meet the Limiting Condition for Operation except as provided in Specification 4.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.

If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less. This delay period is permitted to allow performance of the surveillance.

If the surveillance is not performed within the delay period, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

When the surveillance is performed within the delay period and the surveillance criteria are not met, the Limiting Condition for Operation must immediately be declared not met, and the applicable ACTION requirements must be met.

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

4.0.4 Entry into an OPERATIONAL MODE or other specified condition in the Applicability of a Limited Condition for Operation shall only be made when the Limiting Condition for Operation Surveillances have been met within their specified frequency, except as provided by Specification 4.0.3. When a Limiting Condition for Operation is not met due to Surveillances not having been met, entry into an OPERATIONAL MODE or other specified condition in the Applicability shall only be made in accordance with Specification 3.0.4.

COOK NUCLEAR PLANT-UNIT I Page 3/4 0-2 AM ENDM ENT 98,443, 190,263

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

I This provision shall not prevent entry into OPERATIONAL MODES or other specified conditions in the Applicability that are required to comply with ACTIONs or that are part of a shutdown of the unit.

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 performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.

SURVEILLANCE REQUIREMENTS

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 Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and Required frequencies for performing applicable Addenda terminology for inservice inspection and testing activities inservice inspection and testing criteria 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 Yearly or annually At least once per 366 days

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

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

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the

- requirements of any Technical Specification.

4.0.6 Deleted 4.0.7 Deleted COOK NUCLEAR PLANT-UNIT 1 Page 3/4 0-3 AMENDMENT400,M,444,W

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3

a. One charging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

b. One charging flowpath associated with support of Unit 2 shutdown functions shall be available APPLICABILITY: Specification 3.1.2.3.a. - MODES 5 and 6 Specification 3.1.23.b. - At all times when Unit 2 is in MODES 1, 2, 3, or 4.

ACTION:

a. With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes except: 1) heatup or cooldown of the reactor coolant volume provided that SHUTDOWN MARGIN sufficient to accommodate the change in temperature is maintained in accordance with Specification 3.1.1.2 in MODE 5 or Specification 3.9.1 in MODE 6, and the heatup or cooldown rate is restricted to 50'F or less in any one-hour period in MODE 5, or 2) addition of water from the RWST, provided the boron concentration in the RWST is greater than or equal to the minimum required by Specification 3.1.2.7.b.2.

b. With more than one charging pump OPERABLE or with a safety injection pump(s) OPERABLE when the temperature of any RCS cold leg is less than or equal to 1520F, unless the reactor vessel head is removed, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within one hour.

c. The provisions of Specification 3.0.3 are not applicable.

d. In addition to the above, when Specification 3.1 .2.3.b is applicable and the required flow path is not available, return the required flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return the required flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REOUIREMENTS 4.1.2.3.1.1 The above required charging pump shall be demonstrated OPERABLE by verifying that the pump's developed head at the test flow point is greater than or equal to the required developed head when tested pursuant to Specification 4.0.5.

A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 1520F.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 1-11 AMENDMENT 98, 40, 4A, 44, 46, 20, 230

TABLE 3.3-1 0

X REACTOR TRIP SYSTEM INSTRUMENTATION Z

r'i

>. MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

> FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

'- 1. Manual Reactor Trip 2 1 2 1, 2 and 12 2 2. Power Range, Neutron Flux 4 2 3 1,2 and 2

3. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2 High Negative Rate

5. Intermediate Range, 2 1 2 1,2 and 3 Neutron Flux

6. Source Range, Neutron Flux A. Startup 2 1 2 2##and 4 B. Shutdown 2 0 1 3,4 and 5 5

7. Overtemperature AT 4 2 3 1, 2 6 Four Loop Operation

8. Overpower AT 4 2 3 1, 2 6 Four Loop Operation

>m 2 .

0n 5

01 TABLE 3.3-1 (Continue) 0 REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C

9. Pressurizer Pressure - Low 4 2 3 1,2 6

10. Pressurizer Pressure - High 4 2 3 1,2 6 it. Pressurizer Water Level - 3 2 2 1,2 7 High

12. Loss of Flow - Single Loop 3/loop 2/loop in any 2/loop in each 1 7 (Above P-8) operating loop operating loop

13. Loss of Flow - Two Loops 3/loop 2/loop in two 2/loop in each I 7 (Above P-7 and below P-8) operating loops operating loop

14. Steam Generator Water 3/loop 2/loop in any 2/loop in each 1,2 7 Level - Low-Low operating loop operating loop It

15. Steam/Feedwater Flow 2/loop-level and 1/loop-level 1/loop-level and 1,2 7 Mismatch and Low Steam 2/loop-flow coincident with 2/loop-flow mis-Generator Water Level mismatch in same 1/loop-flow match or 2/loop-3 loop mismatch in level and I/loop-same loop flow mismatch

.q W

-L

4

o TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

z 16. Undervoltage-Reactor Coolant 4-1/bus 2 3 1 6 Ci Pumps

17. Underfrequency-Reactor 4-1/bus 2 3 1 6 Coolant Pumps

18. Turbine Trip A. Low Fluid Oil 3 2 2 1 7 Pressure B. Turbine Stop Valve 4 4 4 1 7 Closure wP. 19. Safety Injection Input from 2 1 2 1, 2 1 le Un ESF

20. Reactor Coolant Pump breaker Position Trip Above P-7 I/breaker 2 1/breaker per 1 11

> operating loop

Z 21. Reactor Trip Breakers 2 1 2 1,2 13,15 3',4,5 14

22. Automatic Trip Logic 2 1 2 1, 2 1 3g@,4',5 ' 14

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION I TABLE 3.3-1 (Continued)

TABLE NOTATION

With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

I

1. / High voltage to detector may be de-energized above P-6.

ACTION STATEMENTS ACTION 1- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 4.3.1.1. 1.

ACTION 2- 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.

a. The inoperable channel is placed in tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable 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 of the other channels per Specification 4.3.1.1.1.

c. Either THERMAL POWER is restricted to less than or. equal to 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to less than or equal 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 QUADRANT POWER 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.c.

ACTION 3- With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

3-6 AMENDMENT 74, 440, 354 PLANT-UNIT II COOK NUCLEAR PLANT-UNIT Page 3/4 Page 3/4 3-6 AMENDMENT .74,440,154 I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Manual Initiation ---- See Functional Unit 9 -

b. Automatic Actuation 2 I 2 1,2,3,4 13 Logic

c. Containment Pressure 3 2 2 1,2,3 14 I

- High

d. Pressurizer Pressure - 3 2 2 1,2,3 14 I

Low

e. Differential Pressure Between Steam Lines -

High Four Loops Operating 3/steam line 2/steam line 2/stearn line 1,2,3" 14 any steam line Three Loops Operating 3/operating steam I/steam line, 2/operating 15 line any operating steam line steam line COOK NUCLEAR PLANT-UNIT I Page 3/4 3-16 AM ENDM ENT -90,410, 4-53

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

f. Steam Line Pressure -

Low Four Loops Operating I pressure/loop 2 pressures any I pressure any 1,2,3w 14 1 loops 3 loops Three Loops Operating I pressure/ 1"4I pressure in I pressure in 15 operating loop any operating any 2 operating loop loops COOK NUCLEAR PLANT-UNIT I Page 3/4 3-17 AMENDMENT 94-,440,4-53,244

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

4. STEAM LINE ISOLATION

a. Manual - - --- See Functional Unit 9 -

b. Automatic Actuation 2 I 2 1,2,3 13 Logic

c. Containment Pressure - 4 2 3 1,2,3 16 High-High

d. Steam Flow in Two Steam Lines -- High Four Loops Operating 2/steam line I/steam line I/steam line 1,2,3" 14 I any 2 steam lines Three Loops Operating 2/operating steam I "/any I/operating 15 line operating steam steam line line COOK NUCLEAR PLANT-UNIT I Page 3/4, 3-20 AM ENDM ENT 90, nO, 4-53

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION COINCIDENT WITH Tas- Low-Low Four Loops Operating I T,8 g/Aoop 2 T,,,g any loops I T., any 3 1,2, 3" 14 loops I m Term in any 15 Three Loops Operating I T,,/operating operating loop I T., in any 3 ##

loop two operating loops

e. Steam Line Pressure-Low Four Loops Operating I pressure/loop 2 pressures any I pressure any 1,2,3" 14 loops 3 loops Three Loops Operating I pressured ##pressure in I pressure in 3iW 15 operating loop any operating any 2 operating loop loops

5. TURBINE TRIP &

FEEDWATER ISOLATION

a. Steam Generator Water Level - High-High 3/loop 2/loop in any 2/loop in each 1,2,3 14 I operating loop operating loop COOK NUCLEAR PLANT-UNIT I Page 3/4 3-21 AMENDMENT 94,420,153,244

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 14 Level -- Low-Low any Stm. Gen.

Il

b. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3 14 Voltage Pump Start 2/bus (TI IA -

TrainB;TIID

- Train A)

Valve Actuation (Both 2/bus on (TI IA trains) & TIlB or 2/busses TI IC

&TIID)

I

c. Safety Injection 2 2 1,2,3 18

d. Loss of Main Feedwater Pumps 2 2 2 1,2 18 I

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water 3/Stm. Gen. 2/Stm. Gen. 2/Stm. Gen. 1,2,3 14 Il Level - Low-Low any 2 Stm. Gen.

2

b. Reactor Coolant Pump 4-1/Bus . 3 1,2,3 19 Bus Undervoltage

8. LOSS OF POWER

a. 4 kV Bus Loss of 3/Bus 2/Bus 2/Bus 1,2,3,4 14 Voltage

b. 4 kV Bus Degraded 3/Bus 2/Bus 2/Bus 1,2,3,4 14 Voltage (Ti IA-Train B; (TIIA- Train (TIIA -Train TIID -Train A) B;TIID- B;TIID-Train A) Train A)

COOK NUCLEAR PLANT-UNIT I Page 3/4 3-21 a AMENDMENT92,4-35,MW

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TOTAL NO. MINIMUM OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

9. MANUAL

a. Safety Injection (ECCS) 2/train I/train 2/train 1,2,3,4 18 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray I/train I/train 1/train 1,2,3,4 18 Containment Isolation -

Phase "B" Containment Purge and Exhaust Isolation

c. Containment Isolation - I/train I/train I/train 1,2,3,4 18 Phase "A" Containment Purge and Exhaust Isolation

d. Steam Line Isolation 2/steam line (I per 2/steam line (I 2/operating 1,2,3 20 train) per train) steam line (I per train)

e. Containment Air 1/train I/train 1/train 1,2,3,4 18 Recirculation Fan

10. CONTAINMENT AIR RECIRCULATION FAN

a. Manual -_See Flmctional

b. Automatic Actuation 2 2 1,2,3 13 Logic

c. Containment Pressure - 3 2 2 1,2,3 14 High I COOK NUCLEAR PLANT-UNIT I Page 3/4 3-21 b AMENDMENT4153,234

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be bypassed inthis MODE below P-11.

Trip function may be bypassed inthis MODE below P-12.

1. I# The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped mode.

1. 1. 1. Manually trip all bistables which would be automatically tripped in the event pressure in the associated active loop were less than the pressure in the inactive loop. For example, if loop I is the inactive loop then the bistables which indicate low pressure in loops 2, 3 and 4 relative to loop I should be tripped.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Total Number ofChannels, 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 ; 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 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel associated with an operating loop 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 4.3.2.1.1.

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 the 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 4.3.2.1.1.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-22 AMENDMENT 94, 40

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

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

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

c. The provisions of Specification 3.0.3 are not applicable.

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

COOK NUCLEAR PLANT-UNIT I Page 3/4 3-35 AMENDMENT 60

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per day.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels Operable requirements, comply with the ACTION requirements of Specification 3.9.9. This ACTION is not required during the performance of containment integrated leak rate test.

ACTION 22A- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements:

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. Technical Specification Section 3.0.3 isNot Applicable.

ACTION 22B- With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements.

1. either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

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

3. In the event of an accident involving radiological releases initiate the preplanned alternate method of monitoring the appropriate param~eter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4. Technical Specification Section 3.0.3 is Not Applicable. I COOK NUCLEAR PLANT-UNIT I Page 314 3-37 AMENDMENT94,434,4-68

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles,

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

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

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the axial flux difference detection system,

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of FN11 and FQ(Zj)

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 REOUIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output to be used during its use when required for

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

b. Monitoring the QUADRANT POWER TILT RATIO, or

c. Measurement of FNH and FQ (Z,e).

COOK NUCLEAR PLANT-UNIT 1 Page 3t4 3-39 AMENDMENT25

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

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

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 43-4.

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status and a CHANNEL CALIBRATION performed 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. 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.

AMENDMENT I Page 3/4 3-40 tOOK NUCLEAR PLANT-UNIT

!COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-40 AMENDMENT

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION METEOROLOGICAL LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

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

b. With one or more required meteorological monitoring channels inoperable for more than 7 days, 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 malfinction and the plans for restoring the channel(s) to OPERABLE status.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 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.

COOK NUCLEAR PLANT-UNIT I Page 314 3-43 AMENDMENT

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

COOK NUCLEAR PLANT-UNIT I Page 314 346 AMENDMENT =

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION APPENDIX R REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5.1 The Appendix R remote shutdown instrumentation channels shown in Table 3.3-9A be OPERABLE with an opposite unit power supply available and with read out capability at the LSI panels.

APPLICABILITY: MODES 1, 2, and 3 ACTION:

a. With the number of OPERABLE Appendix R remote shutdown monitoring channels less than required by Table 3.3-9A, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the opposite unit power supply not available, restore the power supply to available status within 7 days, or provide fire watches in the affected areas and restore the inoperable channel to OPERABLE status within the next 60 days, or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each Appendix R remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6A.

COOK NUCLEAR PLANT-UNIT I Page 3/4 348a AMENDMENT4W I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The post-accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTION:

a. With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-11 (except item 8), either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE post-accident monitoring channels one less than required by Table 3.3-11, item 8, Refueling Water Storage Tank Water Level:

1. Either restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and

2. Within one hour, bypass the Residual Heat Removal Pump trip function from the Refueling Water Storage Tank Water Level for the pump associated with the out-of-service instrument.

SURVEILLANCE REQUIREMENTS 4.3.3.8 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.

COOK NUCLEAR PLANT-UNIT 1 Page 314 3-54 AMENDMENT 49,4-24,444,232

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The explosive gas monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With an explosive gas monitoring instrumentation channel alarm/trip setpoint less conservative than the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-12.

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days. If unsuccessful, prepare and submit a SPECIAL REPORT to the Commission pursuant to Specification 6.92 to explain why this inoperability was not corrected in a timely manner.

c. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION. and analog CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

COOK NUCLEAR PLANT-UNIT I Page 314 3-57 AMENDMENT 69,1-54, M

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the reactor coolant shall be limited to:

a. Less than or equal to I microCurie per gram DOSE EQUIVALENT 1-131, and

b. Less than or equal to I 00/E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES I, 2, 3, 4 and 5 ACTION:

MODES I, 2 and 3*

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with TaV less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the specific activity of the reactor coolant greater than 100/ E microCuries per gram, be in HOT STANDBY with Tav less than 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. Specification 3.0.4.c is applicable.

MODES 1,2,3,4 and 5 I

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT I-131 or greater than 100/ microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.44 until the specific activity of the reactor coolant is restored to within its limits.

SURVEILLANCE REOUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.44.

With Tavg greater than or equal to 5001F.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-21 AMENDMENT44

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall be OPERABLE:

a. Two power operated relief valves (PORVs) with a lift setting of less than or equal to 435 psig, or

b. One power operated relief valve (PORV) with a lift setting of less than or equal to 435 psig and the RHR safety valve with a lift setting of less than or equal to 450 psig.

APPLICABILITY: Mode 5 When the temperature of any RCS cold leg is less than or equal to 1520 F, and Mode 6 when the head is on and fastened to the reactor vessel and the RCS is not vented through a 2-square-inch or larger vent, or through any single blocked open PORV.

ACTION:

a. With one of two PORVs required by item a above or either the PORV or RHR safety valve required by item b above inoperable, either restore the inoperable PORV or RHR safety valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within a total of 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months . Maintain the RCS in a vented condition until the inoperable PORV or RHR safety valve has been restored to OPERABLE status.

b. With both PORVs and the RHR safety valve inoperable, complete depressurization and venting of the RCS through at least a 2-square-inch vent, or through any single blocked open PORV, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Maintain the RCS in a vented condition until both PORVs or one PORV and the RHR safety valve have been restored to OPERABLE status.

c. With the RCS vented per ACTION a or b above, verify the vent pathway at least once per 31 days when the pathway is provided by a valve(s) that is locked, sealed, or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. In the event either the PORVs, the RHR safety valve or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vents on the transient, and any corrective action necessary to prevent recurrence.

rln^ tZ em~l A DA U^ lr.- 4 DOA14 Si 4 .1 A -A~KAX[lT .- ,. 00..- -a -

j irage.314 4-.31 AIVI LIN 01VI LIN I 68, +04, i i 0

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.

APPLICABILITY: ALL MODES ACTION:

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

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 2001F.

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 4.4.10.1 In addition tothe requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer ffidius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33 AMENDMENT 98,24-7

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

g. With PORVs and block valves not in the same line inoperable due to causes other than excessive seat leakage, within I hour restore the valves to OPERABLE status or close and de-energize the associated block valve and place the associated PORV in manual control in each respective line. Apply the portions of ACTION c or d above, relating to the OPERATIONAL MODE, as appropriate for two or three lines unavailable.

SURVEILLANCE REQUIREMENTS 4.4.11.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and

b. At least once per 18 months by operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

c. At least once per 18 months by operating solenoid air control valves and check valves in PORV control systems through one complete cycle of full travel, and

d. At least once per 18 months by performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, c, or d in Specification 3.4.1 1.

4.4.11.3 Deleted.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-36 AMENDMENT 444,468,4-76,-244

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM REACTOR VESSEL HEAD VENTS LIMITING CONDITION FOR OPERATION 3.4.12.1 At least one of the Reactor Vessel head vent paths, consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Reactor Vessel head vent paths inoperable, and at least one of the Pressurizer steam space vent paths OPERABLE (see Specification 3.4.12.2), operation in MODES 1, 2, 3 or 4 may continue, provided the inoperable vent paths are maintained closed with power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Reactor Vessel head vent paths within 30 days 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 .

b. With both of the Reactor Vessel head vent paths and both of the Pressurizer steam space vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-37 AMENDMENT98

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT VENT SYSTEM PRESSURIZER STEAM SPACE VENTS LIMITING CONDITION FOR OPERATION 3.4.12.2 At least one of the Pressurizer steam space vent paths, each consisting of two remotely operated valves in series, powered from Class IE DC busses, shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With both of the Pressurizer steam space vent paths inoperable, and at least one of the Reactor Vessel head vent paths OPERABLE (see Specification 3.4.12.1), operation in MODES 1, 2, 3 or 4 may dontinue, provided the inoperable vent paths are maintained closed with the power removed from the valve actuators of all the remotely operated valves in all of the inoperable vent paths; restore at least one of the Pressurizer steam space vent paths within 30 days 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 in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With both of the Pressurizer steam space vent paths and both of the Reactor Vessel head vent paths inoperable; maintain the inoperable vent paths closed with power removed from the valve actuators of all of the remotely operated valves in all of the inoperable vent paths; restore one of the inoperable vent paths from either the Reactor Vessel head vent or the Pressurizer steam space 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 .

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-39 AMENDMENT98

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

ECCS SUBSYSTEMS- T < 350TF LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a One OPERABLE centrifugal charging pump,#

b. One OPERABLE residual heat removal heat exchanger,

c. One OPERABLE residual heat removal pump, and

d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within I hour or be in COLD SH1UTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T,,g less than 350'F by use of alternate heat removal methods.

c. With more than one charging pump OPERABLE or with a safety injection pump(s)

OPERABLE when the temperature of any RCS cold leg is less than or equal to 1521F, remove the additional charging pump(s) and the safety injection pump(s) motor circuit breakers from the electrical power circuit within I hour.

d. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circurftances of the actuation and the total accumulated actuation cycles to date.

e. Specification 3.0.4.b is not applicable to the centrifugal charging pump.

A maximum of one centrifugal charging pump shall be OPERABLE and both safety injection pumps shall be inoperable whenever the temperature of one or more of the RCS cold legs is less than or equal to 1521F.

COOK NUCLEAR PLANT-UNIT I Page 3/4 5-7 AMENDMENT88,46-7

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The containment purge supply and exhaust system shall be closed except when operation of the containment purge system is required for pressure control, ALARA, and respirable air quality considerations for personnel entry, and for surveillance testing and maintenance activities. No more than one purge supply path and one purge exhaust path shall be open at a time.

APPLICABILITY: MODES 1, 2,3, and 4.

ACTION:

a. With one containment purge supply and/or one exhaust isolation valve inoperable, isolate the affected penetration by use of at least one automatic valve secured in the closed position, and, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , either:

I) Restore the inoperable valve to OPERABLE status, or,

2) Deactivate the automatic valve secured in the closed position.

b. Operation may then continue until performance of the next required valve test provided that the automatic valve secured in the closed position is verified to be deactivated in the closed position at least once per 31 days.

c. Otherwise, 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.7.1 The surveillance requirements of Technical Specifications 3/4.6.1.2 and 3/4.6.3.1 apply.

COOK NUCLEAR PLANT-UNIT I Page 314 6-9a AMENDMENT66,M,20

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.6 CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE. Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control. The ACTION statement of T/S 3/4.6.3.1 is not applicable to the containment purge supply and exhaust isolation valves. The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the containment isolation valve(s) inoperable, either:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or

d. 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 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 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.

COOK NUCLEAR PLANT-UNIT I Page 314 6-14 AMENDMENT 9-5,4-70, M

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. MODES I & 2: With 4 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and comply with action statement b.

b. MODE 3: With a minimum of 3 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves associated with an operating loop inoperable, operation may proceed provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve(s) are restored to OPERABLE status, or the reactor trip breakers are opened; otherwise, be in HOT SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with lift settings as shown in Table 4.7-1. The safety valve shall be reset to the nominal value +/-1% whenever found outside the +/-1% tolerance. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 7-1 AMENDMENT 4-2,0,4,64,482, ZW

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2

a. At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

1. Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and

2. One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.

b. At least one auxiliary feedwater flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.1.2.a - MODES 1, 2, 3.

Specification 3.7.1.2.b - At all times when Unit 2 is in MODES 1,2, or 3.

ACTIONS:

When Specification 3.7.1.2.a is applicable:

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

d. Specification 3.0.4.b is not applicable.

When Specification 3.7.1.2.b is applicable:

With no flow path to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-5 AMENDMENT 92,44,46, 44, 4468

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5. Each steam generator stop valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE I - With one steam generator stop valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 2 - With one or more steam generator stop valves inoperable, close the inoperable valve(s) within and 3 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and verify the inoperable valves are closed at least once per 7 days. Otherwise, be in at least MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , with the unit in at least MODE 3 within the first 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.

4.7.1.52 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-10 AMENDMENT 40, 447,464,48-5

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1

a. At least two independent component cooling water loops shall be OPERABLE.

b. At least one component cooling water flowpath in support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.3.l.a - MODES 1, 2, 3 and 4.

Specification 3.7.3.1 .b - At all times when Unit 2 is in MODES 1, 2, 3, or 4.

ACTION:

When Specification 3.7.3.l.a is applicable:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

When Specification 3.7.3. .b is applicable:

With no flowpath to Unit 2 available, return at least one flow path to available status within 7 days, or provide equivalent shutdown capability in Unit 2 and return at least one flow path to available status within the next 60 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I SURVEILLANCE REOUIREMENTS 4.7.3.1 At least two component cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 18 months by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

C. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per 18 months by verifying that the unit cross-tie valves can cycle full travel. Following cycling, the valves will be verified to be in their closed positions.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-15 AMENDMENT 40i, 4-3, 444,464, 243,2;5

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 a. At least two independent essential service water loops shall be OPERABLE.

b. At least one essential service water flowpath associated with support of Unit 2 shutdown functions shall be available.

APPLICABILITY: Specification 3.7.4.l.a - Either Unit in MODES 1,2, 3, and 4.

Specification 3.7.4.1 .b - At all times when Unit 2 is in MODES 1, 2, 3 or 4.

ACTION:

a. When Unit I is in MODES 1, 2, 3, and 4:

With only one essential service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. When Unit 2 is in MODES 1, 2, 3 and 4:

1. With any Unit I essential service water pump not OPERABLE, within one hour close at least one crosstie valve on the associated header or have Unit 2 enter ACTION a for Unit 2 Specification 3.7.4.1 for the Unit 2 essential service water pump sharing the same header with the inoperable Unit I essential service water pump.

2. With no essential service water flow path available in support of Unit 2 shutdown functions, return at least one flow path to available status within 7 days, or have Unit 2 in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and HOT SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REOUIREMENTS I

4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct positiop.

b. At least once per 18 months by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.

c. By verifying pump performance pursuant to Specification 4.0.5.

d. At least once per 92 days by verifying that each closed crosstie valve, in the available essential service water flowpath associated with support of Unit 2 shutdown functions, can be cycled from the control room.

COOK NUCLEAR PLANT-UNIT I Page 3/4 7-17 AMENDMENT 40-7,4-34, 444,4(A, 2-53,2;5

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.5 CONTROL ROOM VENTILATION SYSTEM CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system (CREVS) shall be OPERABLE with:

a. Two independent pressurization trains, and

b. One charcoal adsorber/HEPA filter unit.

-- -NOTE D- -

The control room envelope/pressure boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, 4, and during the movement of irradiated fuel assemblies.

ACTION:

MODES 1, 2, 3, and 4:

a. With one pressurization train inoperable, restore the inoperable train to OPERABLE status within 7 days 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the filter unit inoperable, restore the filter unit to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With two CREVS pressurization trains inoperable due to an inoperable control room envelope/pressure boundary, restore the control room envelope/pressure boundary to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

During the movement of irradiated fuel assemblies:

d. With one pressurization train inoperable, restore the inoperable pressurization train to OPERABLE status within 7 days, or initiate and maintain operation of the remaining OPERABLE train in the pressurization/cleanup alignment.

e. With any of the following: (I) both pressurization trains inoperable; (2) the filter unit inoperable; or (3) the control room envelope/pressure boundary inoperable, immediately suspend all operations involving the movement of irradiated fuel assemblies.

COOK NUCLEAR PLANT-UNIT I Page 314 7-19 AMENDMENT 4-59,274,2-76

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of > 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

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

1. Either decontaminated and repaired, or

2. Disposed of in accordance with Commission Regulations.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.7.1.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

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

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

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

a. Sources in use (excluding startup sources and fission detectors previously subjected to core flux) -

At least once per six months for all sealed sources containing radioactive materials.

COOK NUCLEAR PLANT-UNIT I Page 314 7-26 AMENDMENT235

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.8 ELECTRICAL POWER SYSTEMS ACTION (Continued)

c. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. offsite source by performing Surveillance Requirement 4.8. .1. L.a within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and if the diesel generator became inoperable due to any cause other than an inoperable support system, an independently testable component, or preplanned preventive maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE diesel generator by performing Surveillance Requirement 4.8.1.1 .2.a.4 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , unless the absence of any potential common mode failure for the remaining diesel generator is demonstrated; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With the diesel generator restored to OPERABLE status, follow ACTION Statement a.* With the offsite circuit restored to OPERABLE status, follow ACTION Statement b.*

d. With two of the above required offsite A.C. circuits inoperable, restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 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 . With only one offsite source restored, follow ACTION Statement a.*

e. With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8. I. I.La within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . With one diesel generator unit restored, follow ACTION Statement b or c*.

f. Specification 3.0.4.b is not applicable to diesel generators.

The ACTION statement time shall be based upon the time associated with the component inoperability, and is not reset when exiting this ACTION statement.

SURVEILLANCE REOUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class I E distribution system shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability, and

b. Demonstrated OPERABLE at least once per 18 months by transferring the unit power source automatically from the normal auxiliary source to the preferred reserve source and by transferring manually to the alternate reserve source.

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.9 REFUELING OPERATIONS STORAGE POOL VENTILATION SYSTEM**

LIMITING CONDITION FOR OPERATION 3.9.12 The spent fuel storage pool exhaust ventilation system shall be OPERABLE.

APPLICABILITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a. With no fuel storage pool exhaust ventilation system OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage poolt until at least one spent fuel storage pool exhaust ventilation system is restored to OPERABLE status.*

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.9.12 The above required fuel storage pool ventilation system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system, by:

1. Deleted

2. Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1980 while operating the exhaust ventilation system at a flow rate of 30,000 cfm +/- 10%.

The crane bay roll-up door and the south door of the auxiliary building crane bay may be opened under administrative control during movement of fuel within the storage pool or crane operation with loads over the storage pool.

- Shared system with D.C. COOK - UNIT 2.

t This does not include the main load block. For purposes of this specification, a de-energized main load block need not be considered a load.

COOK NUCLEAR PLANT-UNIT 1 Page 314 9-13 AMENDMENT 424, W

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS*

LIMITING CONDITION FOR OPERATION 3.11.1 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tanks.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, without delay 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.

b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Page 3/4 11-1 4~~9 AMENDMENT 69, 4-~~~~~~~~~~~~~~4, COOK NUCLEAR I PLANT-UNIT COOK NUCLEAR PLANT-UNIT 1 Page 3/4 11-1 AMENDMENT 69,4-54,4-99

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 3% by volume if the hydrogen in the system is greater than or equal to 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 3% by volume but less than or equal to 4% by volume and containing greater than or equal to 4% hydrogen, restore the concentration of oxygen to less than or equal to 3% or reduce the hydrogen concentration to less than 4%-within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months .

b. With the concentration of oxygen in the waste gas holdup system or tank greater than 4% by volume and greater than 4% hydrogen by volume without delay suspend all additions of waste gases to the system or tank and reduce the concentration of oxygen to less than or equal to 3% or the concentration of hydrogen to less than or equal to 4% within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months in the system or tank.

c. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.11.2.1 The concentration of oxygen in the waste gas holdup system shall be determined to within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9.

COOK NUCLEAR PLANT-UNIT I Page 3/4 11-2 AMENDMENT;2,4-54-,489

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to 43,800 curies noble gas (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, without delay 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.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 7 days whenever radioactive materials are added to the tank and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during primary coolant system degassing operations.

COOK NUCLEAR PLANT - UNIT I Page 314 11-3 AMENDMENT 69,4-54,4-93, M, M

6.0 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.5 Technical Specifications Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the Technical Specification shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior Nuclear Regulatory Commission approval provided the changes do not require either of the following:

1. A changes in the Technical Specification incorporated in the license or

2. A change to the Updated Final Safety Analysis Report or Bases that requires Nuclear Regulatory Commission approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the Updated Final Safety Analysis Report.

d. Proposed changes that meet the criteria of Specification 6.8.5.b above shall be reviewed and approved by the Nuclear Regulatory Commission prior to implementation. Changes to the Bases implemented without prior Nuclear Regulatory Commission approval shall be provided to the Nuclear Regulatory Commission on a frequency consistent with 10 CFR 50.7 1(e).

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (I) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

COOK NUCLEAR PLANT-UNIT I Page 6-9 AMENDMENT;L2,464,440,2U

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

3.0.1 This specification defines the applicability of each specification in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 The specification delineates the measures to be taken for those circumstances not directly provided for in the ACTION Statements and whose occurrence would violate the intent of a specification. For example, Specification 3.5.2 requires two independent ECCS Subsystems to be OPERABLE and provides explicit ACTION requirements if one ECCS Subsystem is inoperable. Under the requirements of Specification 3.0.3, if both the required ECCS Subsystems are inoperable, within one hour measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further example, Specification 3.6.2.1 requires two Containment Spray Systems to be OPERABLE and provides explicit ACTION requirements if one Spray System is inoperable. Under the requirements of Specification 3.0.3 if both the required Containment Spray Systems are inoperable, within one hour measure must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.0.4 Specification 3.0.4 establishes limitations on changes in OPERATIONAL MODES or other specified conditions in the Applicability when a Limiting Condition for Operation is not met. It allows placing the unit in an OPERATIONAL MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the Limiting Condition for Operation would not be met, in accordance with Specification 3.0.4.a, 3.0.4.b, or 3.0.4.c.

Specification 3.0.4.a allows entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met when the associated ACTIONs to be entered permit continued operation in the OPERATIONAL MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in an OPERATIONAL MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the OPERATIONAL MODE change. Therefore, in such cases, entry into an OPERATIONAL MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

Specification 3.0.4.b allows entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the OPERATIONAL MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4),

which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment, for the purposes of Specification 3.0.4(b), must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section I I of NUMARC 93-01, "Industry COOK NUCLEAR PLANT-UNIT I Page B3/4 0-1 AMENDMENT 46

3/4 BASES 3/4.0 APPLICABILITY Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed OPERATIONAL MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the Limiting Condition for Operation would be met prior to the expiration of ACTIONs Completion Times that would require exiting the Applicability.

Specification 3.0.4.b may be used with single, or multiple systems and components unavailable. NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

The results of the risk assessment shall be considered in determining the acceptability of entering the OPERATIONAL MODE or other specified condition in the Applicability, and any corresponding risk management actions. The Specification 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in OPERATIONAL MODE I for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular OPERATIONAL MODE bounds the risk of transitioning into and through the applicable OPERATIONAL MODES or other specified conditions in the Applicability of the Limiting Condition for Operation, the use of the Specification 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the Specification 3.0.4.b allowance is prohibited. The Limiting Condition for Operations governing these systems and components contain statements prohibiting the use of Specification 3.0.4.b by stating that Specification 3.0.4.b is not applicable.

Specification 3.0.4.c allows entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met based on a provision in the Specification which states Specification 3.0.4.c is applicable. These specific allowances permit entry into OPERATIONAL MODES or other specified conditions in the Applicability when the associated ACTIONs to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONs or to a specific ACTION of a Specification. The risk assessments performed to justify the use of Specification 3.0.4.b usually only consider systems and components. For this reason, Specification 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant Activity), and may be applied to other Specifications based on Nuclear Regulatory Commission plant-specific approval.

The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated OPERATIONAL MODE or other specified condition in the Applicability.

The provisions of Specification 3.0.4 shall not prevent changes in OPERATIONAL MODES or other specified conditions in the Applicability that are required to comply with ACTIONs. In addition, the provisions of Specification 3.0.4 shall not prevent changes in OPERATIONAL MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in OPERATIONAL MODE or other specified condition in the Applicability associated COOK NUCLEAR PLANT-UNIT I Page B 3/4 0-1 a AMENDMENT

3/4 BASES 3/4.0 APPLICABILITY with transitioning from OPERATIONAL MODE I to OPERATIONAL MODE 2, OPERATIONAL MODE 2 to OPERATIONAL MODE 3, OPERATIONAL MODE 3 to OPERATIONAL MODE 4, and OPERATIONAL MODE 4 to OPERATIONAL MODE 5.

Upon entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met, Specification 3.0.1 and Specification 3.0.2 require entry into the ACTION until the Limiting Condition for Operation is met, or until the unit is not within the Applicability of the Technical Specifications.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by Specification 4.0.1. Therefore, utilizing Specification 3.0.4 is not a violation of Specification 4.0.1 or Specification 4.0.4 for any Surveillances that have not been performed on inoperable equipment. However, Surveillance Requirements must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected Limiting Condition for Operation.

COOK NUCLEAR PLANT-UNIT I Page B 3/4 0-1 b AM ENDM ENT

3/4 BASES 314.0 APPLICABILITY 4.0.1 Specification 4.0.1 establishes the requirement that Surveillance Requirements must be met during the OPERATIONAL MODES or other specified conditions in the Applicability for which the requirements of the Limiting Condition for Operation apply, unless otherwise specified in the individual Surveillance Requirements. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with Specification 4.0.2, constitutes a failure to meet a Limiting Condition for Operation.

Systems and components are assumed to be OPERABLE when the associated Surveillance Requirements have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:

a. The systems or components are known to be inoperable, although still meeting the Surveillance Requirements; or

b. The requirements of the Surveillance(s) are known not to be met between required Surveillance performances.

Surveillances do not have to be performed when the unit is in an OPERATIONAL MODE or other specified condition for which the requirements of the associated Limiting Condition for Operation are not applicable, unless otherwise specified. The Surveillance Requirements associated with a test exception are only applicable when the test exception is used as an allowable exception to the requirements of a Specification.

Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given Surveillance Requirement. In this case, the unplanned event may be credited as fulfilling the performance of the Surveillance Requirement. This allowance includes those Surveillance Requirements whose performance is normally precluded in a given OPERATIONAL MODE or other specified condition.

Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONs define the remedial measures that apply. Surveillances have to be met and performed in accordance with Specification 4.0.2, prior to returning equipment to OPERABLE status.

Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with Specification 4.0.2. Post maintenance testing may not be possible in the current OPERATIONAL MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to an OPERATIONAL MODE or other specified condition where other necessary post maintenance tests can be completed.

An example of this process is:

Auxiliary feedwater (AFW) pump turbine maintenance during refueling that requires testing at steam pressures>850 psi. However, if other appropriate testing is satisfactorily completed, the AFW System can be considered OPERABLE. This allows startup and other necessary testing to proceed until the plant reaches the steam pressure required to perform the testing.

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3/4 BASES 3/4.0 APPLICABILITY 4.02 This specification establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month surveillance interval. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is 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. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

Specification 4.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a surveillance has not been completed within the specified surveillance interval. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less, applies from the point in time that it is discovered that the surveillance has not been performed in accordance with Specification 4.0.2, and not at the time that the specified surveillance interval was not met.

This delay period provides adequate time to complete surveillances that have been missed. This delay period permits the completion of a surveillance before complying with ACTION requirements or other remedial measures that might preclude completion of the surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the surveillance, the safety significance of the delay in completing the required surveillance, and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements. When a surveillance with a surveillance interval based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, Specification 4.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the surveillance. -*

Specification 4.0.3 also provides a time limit for completion of surveillances that become applicable as a consequence of MODE changes imposed by ACTION requirements.

Failure to comply with specified surveillance intervals for surveillance requirements is expected to be an infrequent occurrence. Use of the delay period established by Specification 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend surveillance intervals.

If a surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the time limits of the ACTION requirements for the applicable Limiting Condition for Operation begin immediately upon expiration of the delay period. If a surveillance is failed within the delay period, then the equipment is inoperable or the variable is outside the specified limits, and the time limits of the ACTION requirements for the applicable Limiting Condition for Operation begin immediately upon the failure of the surveillance.

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3/4 BASES 3/4.0 APPLICABILITY 4.0.3 (Continued)

Completion of the surveillance within the delay period allowed by this Specification, or within the completion time of the ACTIONS, restores compliance with the Limiting Condition for Operation requirements.

4.0.4 Specification 4.0.4 establishes the requirement that all applicable Surveillance Requirements must be met before entry into an OPERATIONAL MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into OPERATIONAL MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated OPERATIONAL MODE or other specified condition in the Applicability.

A provision is included to allow entry into an OPERATIONAL MODE or other specified condition in the Applicability when a Limiting Condition for Operation is not met due to Surveillance not being met in accordance with Specification 3.0.4.

However, in certain circumstances, failing to meet a Surveillance Requirement will not result in Specification 4.0.4 restricting an OPERATIONAL MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated Surveillance Requirement(s) are not required to be performed, per Specification 4.0.1, which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, Specification 4.0.4 does not apply to the associated Surveillance Requirement(s) since the requirement for the Surveillance Requirement(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in a Specification 4.0.4 restriction to changing OPERATIONAL MODES or other specified conditions of the Applicability. However, since the Limiting Condition for Operation is not met in this instance, Specification 3.0.4 will govern any restrictions that may (or may not) apply to OPERATIONAL MODE 4 or other specified condition changes.

Specification 4.0.4 does not restrict changing OPERATIONAL MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the Limiting Condition for Operation not met has been delayed in accordance with Specification 4.0.3.

The provisions of Specification 4.0.4 shall not prevent entry into OPERATIONAL MODES or other specified conditions in the Applicability that are required to comply with ACTIONs. In addition, the provisions of Specification 4.0.4 shall not prevent changes in OPERATIONAL MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in OPERATIONAL MODE or other specified condition in the Applicability associated with transitioning from OPERATIONAL MODE I to OPERATIONAL MODE 2, OPERATIONAL MODE 2 to OPERATIONAL MODE 3, OPERATIONAL MODE 3 to OPERATIONAL MODE 4, and OPERATIONAL MODE 4 to OPERATIONAL MODE 5.

COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 0-4b AMENDMENT

3/4 BASES 3/4.3 REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM.

The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Cook Nuclear Plant site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finalizing site specific criteria which will be used as the basis for the re-evaluation of the specific activity limits of this site. The re-evaluation may result in higher limits.

Reducing T.Vg to less than 500'F prevents the release of activity should a steam generator tube rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible ifjustified by the data obtained.

Specification 3.0.4.c is applicable. This allowance permits entry into the applicable OPERATIONAL MODE(S) while relying on the ACTIONs.

Page B 3/4 4-5 AMENDMENT 442, 4-66, 200, 238 NUCLEAR PLANT-UNIT I COOK NUCLEAR PLANT-UNIT I Page B 3/4 4-5 AM ENDM ENT 442,466, M, 2J8

3/4 BASES 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS (Continued)

With the RCS temperature below 350'F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and safety injection pumps, except the required OPERABLE charging pump, to be inoperable below 1527F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration', (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.

Specification 3.0.4.b is not applicable to an inoperable centrifugal charging pump when entering OPERATIONAL MODE 4. There is an increased risk associated with entering OPERATIONAL MODE 4 from OPERATIONAL MODE 5 with an inoperable ECCS high head subsystem and the provisions of Specification 3.0.4.b, which allow entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

Observing these limits while flow balancing the SI pumps in the injection mode will ensure they are not exceeded in the recirculation mode (RHR pumps provide a suction pressure boost) due to the higher system resistance resulting from splitting of the SI trains when in the recirculation lineup.

COOK NUCLEAR PLANT-UNIT 1 Page B 314 5-2 AM ENDM ENT 88,4S8,447, ZP

3/4 BASES 3/4.7 PLANT SYSTEMS 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant system can be cooled down to less than 3507F from normal operating conditions in the event of a total loss of off-site power.

Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 450 gpm at a pressure of 1065 psig to the entrance of the steam generators. The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 900 gpm at a pressure of 1065 psig to the entrance of the steam generators.

This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant system temperature to less than 3507F when the Residual Heat Removal system may be placed into operation.

The acceptance discharge pressures for the auxiliary feedwater pumps are based on a fluid temperature of 60 0F.

Water density corrections are permitted to allow comparison of test results which vary depending on ambient conditions.

In addition to its safety design function, the AFW system is used to maintain steam generator level during startup (including low power operation). During this time, the system design allows for automatic initiation of the auxiliary feedwater pumps and their related automatic valves in the flow path.

The auxiliary feedwater flowpath, with a pump and associated water supplies and piping, will support shutdown cooling requirements of Unit 2. This capacity addresses the 10 CFR 50 Appendix R safe shutdown requirements.

Fire watches posted in the affected opposite unit areas (i.e., Unit 2 areas requiring use of the Unit I auxiliary feedwater system in the event of a fire) may serve as the equivalent shutdown capability specified in the action statements of Specification 3.7.1.2. In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per the Administrative Technical Requirements Manual and establish hourly fire watch patrols. The required opposite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfilling its intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure. An additional procedure details how the above noted fire watches will be implemented.

Specification 3.0.4.b is not applicable to an inoperable AFW train. There is an increased risk associated with entering an OPERATIONAL MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of Specification 3.0.4.b, which allow entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 7-2 AMENDMENT 4, Revised 07/3110'

3/4 BASES 3/4.8 ELECTRICAL POWER SYSTEMS For surveillance requirements 4.8.1.1.2.e.4.b, 4.8.1.1.2.e.6.b, and 4.8.1.1.2.e.11, the requirement to verify the connection of permanent and auto-connected loads is intended to satisfactorily show the relationship of these loads to the DG loading logic. In certain circumstances, many of these loads cannot actually be connected or loaded without undue hardship or potential for undesired operation. For instance, ECCS injection valves are not desired to be stroked open, or high pressure injection systems are not capable of being operated at full flow, or RHR systems performing a decay heat removal function are not desired to be realigned to the ECCS mode of operation. In lieu of actual demonstration of connection and loading of loads, testing that adequately shows the capability of the DG system to perform these functions is acceptable. This testing may include any series of sequential, overlapping, or total steps so that the entire connection and loading sequence is verified.

Specification 3.0.4.b is not applicable to an inoperable diesel generator. There is an increased risk associated with entering an OPERATIONAL MODE or other specified condition in the Applicability with an inoperable DG and the provisions of Specification 3.0.4.b, which allow entry into an OPERATIONAL MODE or other specified condition in the Applicability with the Limiting Condition for Operation not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

COOK NUCLEAR PLANT-UNIT 1 Page B 3/4 8-3 AMENDMENT ReAsed 5/27103

Attachment 2b to AEP:NRC:3304 UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGES REVISED PAGES UNIT 2 3/4 0-1 3/4 3-20a 3/4 4-29 3/4 7-12 B 3/4 0-lb 3/4 0-2 3/4 3-21 3/4 4-31 3/4 7-13 B 3/4 0-2 3/4 0-3 3/4 3-34 3/4 4-33 3/4 7-14 B 3/4 0-3 3/4 1-11 3/4 3-36 3/4 4-34 3/4 7-25 B 3/4 0-3a 3/4 3-2 3/4 3-38 3/4 4-36 3/4 8-2 B 3/4 0-3b 3/4 3-3 3/4 3-38a 3/4 5-3 3/4 9-12 B 3/4 0-4 3/4 3-4 3/4 3-39 3/4 5-7 3/4 11-1 B 3/4 0-4a 3/4 3-5 3/4 3-42 3/4 6-9a 3/4 11-2 B 3/4 4-5 3/4 3-15 3/4 3-44a 3/4 6-13 3/4 11-3 B 3/4 5-2 3/4 3-18 3/4 3-45 3/4 7-1 6-9 B 3/4 7-2 3/4 3-19 3/4 3-53 3/4 7-5 B 3/4 0-1 B 3/4 8-3 3/4 3-20 3/4 4-20 3/4 7-10 B 3/4 0-la