Text

Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
	ML040500693
Person / Time
Site:	Wolf Creek
Issue date:	02/09/2004
From:	Mckinney B; Wolf Creek
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	WO 04-0003
	Download: ML040500693 (100)
	v • d • e

WOLF CREEK NUCLEAR OPERATING CORPORATION Britt T. McKinney Site Vice President FEB 92004 WO 04-0003 U. S. Nuclear Regulatory Commission ATTN: DocumentControlDesk Washington, DC 20555

Subject:

Docket No. 50-482: Application for Technical Specification Change Regarding MODE Change Limitations Using the Consolidated Line Item Improvement Process Gentlemen:

Wolf Creek Nuclear Operating Corporation (WCNOC) hereby transmits an application for amendment to Facility Operating License No. NPF-42 for the Wolf Creek Generating Station (WCGS) in accordance with the provisions of 10 CFR 50.90. The proposed amendment would modify technical specification (TS) requirements for MODE change limitations in Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4. In addition, several other changes are also submitted to various TS requirements.

Attachment I contains a description of the proposed changes, the requested confirmation of applicability, and plant-specific verifications. As discussed in Attachment I, this amendment application is consistent with the NRC-approved Industry/Technical Specification Task Force (TSTF) Standard TS (STS) Change Traveler TSTF-359, Revision 9, "Increase Flexibility in MODE Restraints." Attachments II and IlIl contain marked-up and revised TS pages, respectively. Attachment IV contains the TS Bases changes (for information only) to assist the staff in its review of the proposed changes. Revision to the TS Bases will be implemented pursuant to the TS Bases Control Program, TS 5.5.14, upon implementation of this license amendment. Attachment V contains a list of commitments.

This amendment application was reviewed by the Plant Safety Review Committee and the Nuclear Safety Review Committee for WCNOC. In accordance with 10 CFR 50.91, a copy of this amendment application is being provided to the designated Kansas State official.

P.O. Box 411 Burlington, KS 66839 Phone: (620) 364-8831 An Equal Opportunty Employer MIF/HCVET

WO 04-0003 Page 2of 2 WONOC requests approval of the proposed amendment by December 2004. The changes

- proposed are not required to address an immediate safety concern. It is anticipated that the license amendment, as approved, will be effective upon issuance, to be implemented Within 90-days from the date of issuance. Please contact me at (620) 364-4112 or Mr. Kevin Moles at (620) 364-4126 for any questions you may-have regarding this application.

Sincerely, Britt T. McKinney BTM/rlg Attachments: I -. Evaluation II - Marked-U Technical Specifications III Proposed/Revis bd Technical Specifications IV -TS Bases Changes (For Information Only)

V -List of Commitments cc. V. L. Cooper (KDHE), w/a --

J. N. Donohew (NRC), w/a D. N. Graves (NRC), wfa B. S. Mallett (NRC), w/a -

Senior Resident Inspector (NRC), wla

STATE OF KANSAS )

)SS COUNTY OF COFFEY )

Britt T. McKinney, of lawful age, being first duly sworn upon oath says that he is. Site Vice President of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By Britt T. McKinney

-'Site Vice President SUBSCRIBED and sworn to before me this 9 day of FOB, 2004.

jf. MARY E. GIFFORD Notary Public Nctary Public - State of Kansas My Apt. Expires P_10c91aoE7

.Expiration Date tO lzc7

Attachment Ito WO 04-0003 Attachment I to WO 04-0003 Page 1 of 8 EVALUATION

1.0 DESCRIPTION

The proposed amendment would modify technical specifications (TS) requirements for MODE change limitations in Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4. The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry/Technical Specification Task Force (TSTF) Standard TS (STS) change TSTF-359 Revision 8, as modified by the notice in the Federal Register published on April 4, 2003 (68 FR 16579). That Federal Register Notice (FRN) announced the availability of this TS improvement through the Consolidated Line Item Improvement Process (CLIIP). TSTF-359, Revision 8, was subsequently revised to incorporate the modifications discussed in the April 4, 2003, FRN and other minor changes, and was submitted to the NRC on April 28, 2003 as TSTF-359, Revision 9.

2.0 PROPOSED CHANGE

S A description of the TS and TS Bases changes is provided below for the TS/TS Bases changes that directly adopt TSTF-359, Revision 9, with no variations. Section 4.2 provides a description of the TSITS Bases changes where minor variances are required to accommodate differences between the Wolf Creek Generating Station (WCGS) TS and the STS.

LCO 3.0.4 is revised to allow entry into a MODE or other specified condition in the Applicability while relying on the associated ACTIONS, provided the ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time, that there is a risk assessment performed which justifies the use of LCO 3.0.4, or an NRC approved allowance is provided in the Specification to be entered. The Applicability of LCO 3.0.4 is expanded to include transition into all MODES or other specified conditions in the Applicability, except when required to comply with ACTIONS or that are part of a shutdown of the unit. The associated Bases are likewise being modified in accordance with TSTF-359, Revision 9.

The bracketed provisions in the TSTF-359 Revision 9 Bases mark-ups have been removed for consistency with NUREG-1431, Revision 2, Standard Technical Specifications, Westinghouse Plants."

SR 3.0.4 is revised to reflect the concepts of the change to LCO 3.0.4. The Applicability of LCO 3.0.4 and SR 3.0.4 is expanded to include transition into all MODES or other specified conditions in the Applicability, except when required to comply with ACTIONS or that are part of a shutdown of the unit. The associated Bases likewise are being modified in accordance with TSTF-359, Revision 9. The bracketed provisions in the TSTF-359 Revision 9 Bases mark-ups have been removed for consistency with NUREG-1431, Revision 2, Standard Technical Specifications, "Westinghouse Plants."

In TS 3.3.3, Post Accident Monitoring (PAM) Instrumentation," the Note stating LCO 3.0.4 is not applicable is deleted.

In TS 3.3.4, "Remote Shutdown System," the Note stating LCO 3.0.4 is not applicable is deleted.

Attachment I to WO 04-0003 Page 2 of 8

In TS 3.4.11, "Pressurizer Power Operated Relief Valves (PORVs)," the Note stating LCO 3.0.4 is not applicable is deleted.

In TS 3.4.15, RCS Leakage Detection Instrumentation," the Note stating LCO 3.0.4 is not applicable is deleted.

In TS 3.4.16, "RCS Specific Activity," a Note permitting the use of the new LCO 3.0.4c.

provision is substituted for the existing LCO 3.0.4 non-applicability Note in Required Action A.

In TS 3.6.8, "Hydrogen Recombiners," the Note in Required Action A.1 stating LCO 3.0.4 is not applicable is deleted.

. In TS 3.7.5, Auxiliary Feedwater (AFW) System," an ACTIONS Note is added to indicate that the new LCO 3.0.4b. provisions are not applicable when entering MODE 1.

The bracketed provisions around MODE 1 in the TSTF-359 Revision 9 TS and TS Bases mark-ups have been removed since WCGS does not depend upon AFW for plant startup, although the AFW System may be used during startup if the motor-driven startup feedwater pump is unavailable.

In TS 3.8.1, "AC Sources - Operating," an ACTIONS Note is added to indicate that the new LCO 3.0.4b. provisions are not applicable to diesel generators.

3.0 BACKGROUND

The early standard Technical Specifications contained Specifications 3.0.4 and 4.0.4 that prohibited entering the Applicability of an LCO with the LCO or Surveillances not met unless a specific exception was provided. NRC Generic Letter 87-09, "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions For Operation and Surveillance Requirements," June 4, 1987, modified Specifications 3.0.4 and 4.0.4 to allow entering the Applicability of a Specification with the LCO not met when the Actions to be entered allow operation within the Applicability for an unlimited period of time. It stated:

"With respect to unnecessary MODE changes, Specification 3.0.4 unduly restricts facility operation when conformance with Action Requirements provides an acceptable level of safety for continued operation. For an LCO that has Action Requirements permitting continued operation for an unlimited period of time, entry into an operation MODE or other specified condition of operation should be permitted in accordance with the Action Requirements. The solution also resolves the problem of inconsistent application of exceptions to Specification 3.0.4: (a) which delays startup under conditions in which conformance to the Action Requirements establishes an acceptable level of safety for unlimited continued operation of the facility; and (b) which delays a return to power operation when the facility is required to be in a lower MODE of operation as a consequence of other Action Requirements."

Attachment I to WO 04-0003 Page 3 of 8 In the development of Improved Standard Technical Specifications (ISTS), many improvements were made to Specifications 3.0.4 and 4.0.4 (editorially becoming LCO 3.0.4 and SR 3.0.4) including clarification of its applicability regarding normal shutdown and Required Action shutdowns, and MODE changes during Cold Shutdown and Refueling Operations. Despite these changes, ISTS LCO 3.0.4 and SR 3.0.4 were still overly restrictive. The startup of a unit may be unnecessarily delayed due to the current restrictions of LCO 3.0.4. For example, a single maintenance activity that is almost complete can cause significant delays and changes in the previously well thought out plans for returning the unit to service. In such situations, allowing the unit to enter the MODE or other specified condition in the Applicability would allow the work to be completed while reducing the likelihood of human error caused by expediting the completion of required Surveillances and maintenance activities.

While the inoperabilities permitted by the Completion Times of Technical Specification Required Actions take into consideration the safety significance and redundancy of the system or components within the scope of an LCO, the Completion Times generally do not address or consider concurrent system or component inoperabilities in multiple LCOs. Therefore, the performance of the 10 CFR 50.65(a)(4) risk assessment which looks at the entire plant configuration is essential (and required) prior to changing operational MODE. The 10 CFR 50.65(a)(4) based risk assessment will be used to confirm (or reject) the appropriateness of transitioning up in MODE given the actual status of plant safety equipment.

TSTF-359, Revision 8 was approved by the NRC, with changes, and a Notice of Availability was published in the Federal Register on April 4, 2003. TSTF-359, Revision 9 was created to incorporate the changes made in the NRC's approval and was approved by the NRC on May 9, 2003.

4.0 TECHNICAL ANALYSES 4.1 Applicability of Published Safety Evaluation WCNOC has reviewed the NRC safety evaluation dated April 4, 2003, as part of the CLIIP.

This review included a review of the NRC staff's evaluation as well as the supporting information provided to support TSTF-359, Revision 8, and included the consideration of the updates made in TSTF-359, Revision 9. WCNOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to WCGS and justify this amendment for the incorporation of the changes to the WCGS TS.

4.2 Optional Changes and Variations WCNOC is not proposing any variations or deviations from the model TS and TS Bases changes for LCO 3.0.4 and SR 3.0.4 described in the modified TSTF-359, Revision 8 (as updated by Revision 9).

Attachment I to WO 04-0003 Page 4 of 8 Due to differences between WCGS TS and TS Bases and the model STS in NUREG-1431, Revision 2, "Standard Technical Specifications, Westinghouse Plants," in several cases variances from the TSTF mark-up changes are made. These variances are discussed below and do not invalidate the NRC staffs model safety evaluation supporting the adoption of TSTF-359, Revision 9.

Special LCO 3.0.4 Notes Added during ITS Conversion Prior to approval of TSTF-359 Revision 9, ISTS LCO 3.0.4 and SR 3.0.4 contained a Reviewer's Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on MODE changes or Required Actions in individual LCOs. The Federal Register Notice of Availability (68 FR 16586 dated 4/4/2003) states:

"The notes limiting the applicability of LCO 3.0.4 and SR 3.0.4 are no longer needed and are removed by TSTF-359, Revision 8. The industry owners group analyses would subsequently support adding notes to various TS, as defined by the tables of higher-risk systems, precluding entry into Modes 5 and 6 for PWRs, and Modes 4 and 5 for BWRs.

However, the addition of notes in these cases is made unnecessary by action statements that require immediate completion times, which means that entry into the Mode or other specified condition in the Applicability is not allowed and the notes would be superfluous."

The Federal Register Notice (68 FR 16588) further states:

"in addition, mode transitions for Modes 5 and 6 for PWRs, and Modes 4 and 5 for BWRs, will be addressed by administrative controls."

NEI 03-10, Risk-Informed Technical Specifications Initiative 3, Increased Flexibility in Mode Restraints (TSTF-359), Industry Implementation Guidance," August 2003 (page A-9) and TSTF-359, Revision 9 (Proposed Change section of the traveler justification) both indicate that any plant-specific Notes restricting MODE changes added as a result of the evaluation required by the STS Reviewer's Note are to be deleted.

WCNOC added five special LCO 3.0.4 Notes to the TS during our Improved TS conversion (Amendment No. 123). The following discussions provide additional justification for deleting these Notes:

In TS 3.1.1, "SHUTDOWN MARGIN (SDM)," the Applicability Note is deleted. This Note requires that while the LCO is not met, entry into MODE 5 from MODE 6 is not permitted. Inadvertent boron dilution events are precluded in MODE 6 via the administrative controls of TS 3.9.2. Inadvertent dilution events are not subject to the same administrative controls in MODE 5 when mitigation via the Boron Dilution Mitigation System (BDMS) must be credited along with analysis assumptions on SDM.

The NRC's model safety evaluation (68 FR 16586) states that LCO 3.0.4 allowances related to values and parameters of TS are not typically addressed by LCO 3.0.4(b) risk assessments, and are therefore addressed by a new LCO 3.0.4(c)." In addition, NEI 03-10 (page 5) states:

"...unless a note is provided specifically exempting an individual value and parameter specification, the LCO 3.0.4.c guidance is not applicable."

Attachment I to WO 04-0003 Page 5 of 8 NEI 03-10 further states (pages 5 and 6) that LCO 3.0.4a. and LCO 3.0.4b. may still be applicable for value or parameters used to demonstrate system or component OPERABILITY. However, since SDM does not demonstrate system or component OPERABILITY, LCO 3.0.4a. and LCO 3.0.4b. are not applicable.

Therefore, since WCNOC does not propose to add an LCO 3.0.4c. Note to TS 3.1.1, and LCO 3.0.4a. and LCO 3.0.4b. are not applicable, this plant-specific Applicability Note prohibiting entry into MODE 5 from MODE 6 while the LCO is not met is superfluous and is therefore deleted.

In TS 3.3.1, "Reactor Trip System (RTS) Instrumentation," the Note in Condition C is deleted. The Note requires that while the LCO is not met for Function 19, 20, or 21 in MODE 5, making the Rod Control System capable of rod withdrawal is not permitted.

Prior to enabling the Rod Control System and withdrawing any control or shutdown banks, i.e., the MODE or other specified condition in the Applicability in question, plant procedures provide controls to either 1) maintain RCS boron concentration sufficient to preclude criticality with all control rods fully withdrawn, or 2) require that the power range neutron flux instrumentation is OPERABLE when RCS temperature is above 510 0F.

This plant-specific Condition C Note is superfluous and is therefore deleted.

In TS 3.4.8, RCS Loops - MODE 5, Loops Not Filled," the Applicability Note is deleted.

This Note requires that while the LCO is not met, entry into MODE 5 Loops Not Filled from MODE 5 Loops Filled is not permitted. The intent of this Note is to retain the heat removal path afforded by the steam generators when the Residual Heat Removal System is degraded. Since LCO 3.4.8 contains Required Actions with immediate Completion Times, this plant-specific Note is unnecessary given that entry into the LCO is not allowed with the LCO requirements not met. This plant-specific Applicability Note is superfluous and is therefore deleted.

In TS 3.9.1, Boron Concentration," the Applicability Note is deleted. This Note requires that while the LCO is not met, entry into MODE 6 from MODE 5 is not permitted. This Specification has no LCO 3.0.4c. exception and LCO 3.0.4 places no restrictions on MODE changes that are part of the shutdown of the unit. However, since LCO 3.9.1 contains Required Actions with immediate Completion Times, this plant-specific Note is unnecessary since entry into the LCO is not allowed with the LCO requirements not met.

This will assure that the core reactivity limits are maintained during fuel handling operations. This plant-specific Note is superfluous and is therefore deleted.

In TS 3.9.6, Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level," the Applicability Note is deleted. This Note requires that while the LCO is not met, entry into this LCO is not permitted. Since LCO 3.9.6 contains Required Actions with immediate Completion Times related to the restoration of the degraded decay heat removal function, this plant-specific Note is unnecessary since entry into the LCO is not allowed with the LCO requirements not met. This plant-specific Note is superfluous and is therefore deleted.

Attachment I to WO 04-0003 Page 6 of 8 Mark-ups Required for Consistency with WCGS TS In addition to the deletion of the five special LCO 3.0.4 Notes, the following changes are required to the WCGS TS in order to fully satisfy the intent of the TSTF-359 Revision 9 changes:

In TS 3.3.2, Engineered Safety Features Actuation System (ESFAS) Instrumentation,"

the Note in the Required Actions of Condition M stating LCO 3.0.4 is not applicable is deleted. The LCO 3.0.4 Note was maintained during the conversion to the Improved TS in Amendment No. 123 based on our current licensing basis. Future MODE changes with an inoperable channel in this trip function (AFW Suction Transfer on Low Suction Pressure) will be evaluated pursuant to the new LCO 3.0.4b. Since this is a more restrictive change, it should be acceptable.

In the TSTF mark-ups, STS 3.4.12, "Low Temperature Overpressure Protection (LTOP)

System," an ACTIONS Note is added to indicate that the new LCO 3.0.4b. provision is not applicable when entering MODE 4. In the WCGS TS, the existing LCO 3.0.4 non-applicability ACTIONS Note is modified consistent with the TSTF and the Applicability of TS 3.4.12 to indicate that the new LCO 3.0.4b. provisions are not applicable when entering MODE 4 or MODE 3.

In the TSTF mark-ups, STS 3.5.3, ECCS - Shutdown," an ACTIONS Note is added to indicate that the new LCO 3.0.4b. provision is not applicable to ECCS high head subsystem. In the WCGS TS, an ACTIONS Note is added using WCGS specific terminology of ECCS centrifugal charging pump subsystem. This is strictly an editorial change reflecting plant-specific terminology and should be acceptable.

In the TSTF mark-ups, STS 3.6.9, "Hydrogen Mixing System (HMS)," is modified.

WCGS TS do not have this TS, so no changes are needed.

In the TSTF mark-ups, STS 3.7.4, Atmospheric Dump Valves (ADVs)," is revised to delete the Note in Required Action A.1. The equivalent WCGS TS is titled, 3.7.4, "Atmospheric Relief Valves (ARVs)," and the same change is made. Additionally, in Required Actions of Condition D, the Note stating LCO 3.0.4 is not applicable is deleted.

Future MODE changes with one or more ARVs inoperable because of excessive seat leakage will be evaluated pursuant to LCO 3.0.4b. Since this is a more restrictive change, it should be acceptable.

5.0 REGULATORY ANALYSIS

5.1 NO SIGNIFICANT HAZARDS CONSIDERATION WCNOC has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the CLIIP. WCNOC has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to WCGS and is, hereby, incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

Attachment I to WO 04-0003 Page 7 of 8 5.2 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:

WCNOC has established TS Bases for LCO 3.0.4 and SR 3.0.4 which state that use of the TS MODE change limitation flexibility established by LCO 3.0.4 and SR 3.0.4 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 modification also includes changes to the Bases for LCO 3.0.4 and SR 3.0.4 that provide details on how to implement the new requirements. The Bases changes provide guidance for changing MODES or other specified conditions in the Applicability when an LCO is not met.

The Bases changes describe in detail how:

LCO 3.0.4a. 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; LCO 3.0.4b. 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; and LCO 3.0.4c. allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification, which is typically applied to Specifications which 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 Bases also state 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. In addition, the Bases state that upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the condition is resolved or until the LCO is met or the unit is not within the Applicability of the TS. The Bases also state that SR 3.0.4 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 SR 3.0.3.

The TS Bases will be revised to reflect the changes to the affected TS and will be implemented in accordance with TS 5.5.14, "Technical Specification (TS) Bases Control Program," as part of the implementation of this amendment, upon NRC approval of this amendment application.

Attachment I to WO 04-0003 Page 8 of 8

6.0 ENVIRONMENTAL CONSIDERATION

WCNOC has reviewed the environmental evaluation included in the model safety evaluation dated April 4, 2003, as part of the CLIIP. WCNOC has concluded that the staffs findings presented in that evaluation are applicable to WCGS and the evaluation is hereby incorporated by reference for this application.

1of WO 04-0003 Page 1 of 27 MARKED-UP TECHNICAL SPECIFICATIONS

Attachment II to WO 04-0003 LCO Applicability Page 2 of 27 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an' associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 Whe nLC not t entry o a MOD or other ece n in e Ap cability all not b made exept when t e associ ed TIO to be tered pe it contin d operati in the DE or oth speciied con ion in the pplicabili for an un ited pe od of time,'his ecificatigshall notevent ch ges in M ES or er specifi

~~~/'~~conditio, in the Applicability t t are requyd to co ply with A 1IONS (continued)

Wolf Creek - Unit 1 3.0-1 Amendment No. 123 1of WO 04-0003 Page 3 of 27 INSERT 1 When an LCO is not met, entry into a 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 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 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 Specifications; or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in 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.

Attachment II to WO 04-0003 LCO Applicability Page 4 of 27 3.0 3.0 LCO Applicabilitv LCO 3.0.4 (continued)

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.15, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required-Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8, allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

Wolf Creek - Unit 1 3.0-2 Amendment No. 123

Attachment I to WO 04-0003 SR Applicability Page 5 of 27 3.

3.0 SR Applicability SR 3.0.4 Ent into MODE/r other sp Cied conditi nrin the Ap abilit o n LS sh not be ade unles the LCO's S rveillance 4ave been et ithin eir spe fied FrequJcy. This pr ision shal ot prevent ntry into ODES r other spe ified conditio s in the Ap icability th are re, ired to mply with CTIONS or at are pa f a shutdo n of the'

{ l~~g;2 ; Sp.4 s only hpicable for try nto a D orhesci7 /

,#dition in th~~~p'AliaiiyMOE 4. J ,t 3an Wolf Creek - Unit 1 3.0-4 Amendment No. 123 1of WO 04-0003 Page 6 of 27 INSERT 2 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into 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.

Attachment II to WO 04-0003 SDM Page 7of27 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limit provided in the COLR.

APPLICABILITY: MODE 2 with kef < 1.0, MODES 3,4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Wolf Creek - Unit 1 3.1-1 WUAmendment No. 123

Attachment II to WO 04-0003 RTS Instrumentation Page 8 of 27 3.3.1 Wolf Creek - Unit 1 3.3-2 Amendment No. 123

Attachment II to WO 04-0003 ESFAS Instrumentation Page 9 of 27 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One or more required L.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel(s) inoperable. required state for existing unit condition.

OR L.2.1 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND L.2.2 Be in MODE 4. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months M. One channel inoperable. (OT M.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND M.2 Restore channel to During OPERABLE status. performance of next COT N. One train inoperable. ----------- NOTE One train 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 provided the other train is OPERABLE.

N.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND N.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Wolf Creek - Unit 3.3-27 Amendment No. 423,132

Attachment I to WO 04-0003 PAM Instrumentation Page 10 of 27 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTIONS 0 Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required channel to OPERABLE status.

inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.8.

met.

(continued)

Wolf Creek - Unit 1 3.3-37 Amendment No. 123

Attachment II to WO 04-0003 Page 11 of 27 Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 and the required auxiliary shutdown panel (ASP) controls shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

---------- ------- NOTE - --------- _______

(3 Separate Condition entry is allowed for each Function and required ASP control.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable. and required ASP controls to OPERABLE status.

OR One or more required ASP controls inoperable.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Wolf Creek - Unit 1 3.3-41 WUAmendment No. 123

Attachment II to WO 04-0003 RCS Loops - MODE 5, Loops Not Filled Page 12 of 27 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

------ --- NOTES---- a- --- a

1. All RHR pumps may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

a. The core outlet temperature is maintained at least 100 F below saturation temperature;

b. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

c. Reactor vessel water level is above the vessel flange.

2. One RHR loop may be inoperable for

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ithis O is nd me entryiioMOE 5 opsN t Fille from MzDE oops Wed i ot per itted /

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-1 7 Amendment No. 423, 131,145

Attachment II to WO 04-0003 Pressurizer PORVs Page 13 of 27 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with all RCS cold leg temperatures > 368 0F.

ACTIONS

-) - - - is NOTe ------------ --------- -

c0 Separate Condition entry is allowed for each PORV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable of to associated block valve.

being manually cycled.

B. One PORV inoperable and B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not capable of being valve.

manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-23 Amendment No. 123

Attachment II to WO 04-0003 LTOP System Page 14 of 27 3.4.12 APPLICABILITY: MODE 3, with any RCS cold leg temperature S 3680F, MODE 4, MODE 5, MODE 6 when the reactor vessel head is on.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more safety A.1 Initiate action to verify a Immediately injection pumps capable of maximum of zero safety injecting into the RCS. injection pumps are capable of injecting into the RCS.

B. Two centrifugal charging B.1 Initiate action to verify a Immediately pumps capable of injecting maximum of one into the RCS. centrifugal charging pump is capable of injecting into the RCS.

C. An accumulator not C.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

(continued)

Wolf Creek - Unit 1 3.4-27 Amendment No. 123

Attachment II to WO 04-0003 RCS Leakage Detection Instrumentation Page 15 of 27 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS)

.3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. The containment sump level and flow monitoring system;

b. One containment atmosphere particulate radioactivity monitor, and

c. One containment air cooler condensate monitoring system or one containment atmosphere (gaseous) radioactivity monitor.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME.

A. Required containment A.1 -- -- NOTE-------

sump level and flow Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months monitoring system after establishment of inoperable. steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump level and flow monitoring system to OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-37 Amendment No. 123

Attachment II to WO 04-0003 RCS Specific Activity Page 16 of 27 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES I and 2, MODE 3 with RCS average temperature (Tvg) > 5001F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 --------- -NOTE--------------

> 1.0 pCi/gm. LCO 3.0.4 sapplicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific activity of B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months the reactor coolant Tag < 5000 F.

> 10/ E PlCi/gM. (

(continued)

Wolf Creek - Unit 1 3.4-41 Amendment No. 123

Attachment II to WO 04-0003 ECCS - Shutdown Page 17 of 27 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS -Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

KI TU

_ --- - -------- I-----

'JL- I t --- __

An RHR subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

APPLICABILITY: MODE 4.

ACTIONS_

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months centrifugal charging pump CCP subsystem to (CCP) subsystem OPERABLE status.

inoperable.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

Wolf Creek - Unit 1 3.5-6 Amendment No. 123

Attachment II of WO 04-0003 Page 18 of 27 INSERT 3 isNOTE---agnpmsuyte LCO 3.0.4b. is not applicable to ECCS centrifugal charging pump subsystem.__

Attachment 11 to WO 04-0003 Hydrogen Recombiners Page 19 of27 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Recombiners LCO 3.6.8 Two hydrogen recombiners shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen recombiner A.1 -OTE-- -- E inoperable. C 3.0.is n cte.

Restore hydrogen 30 days recombiner to OPERABLE status.

B. Two hydrogen B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recombiners inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.6-22 Amendment No. 123

Attachment II to WO 04-0003 ARVs Page 20 of 27 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)

LCO 3.7.4 Four ARV lines shall be OPERABLE. I APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ARV line inoperable A.1 - -

for reasons other than .4 inot excessive leakage.

Restore required ARV line 7 days to OPERABLE status.

B. Two ARV lines inoperable B.1 Restore all but one 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for reasons other than required ARV line to excessive leakage. OPERABLE status.

C. Three or more ARV lines C.1 Restore all but two ARV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable for reasons lines to OPERABLE other than excessive status.

leakage.

(continued)

Wolf Creek - Unit 1 3.7-9 Amendment No. 423, 127

Attachment II to WO 04-0003 ARVs Page 21 of 27 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. With one or more of the T ARVs inoperable because .0. sn ap icaej/

aiCO j of excessive seat leakage. c--- -- --

D.1 Initiate action to close the Immediately associated block valve(s).

AND D.2 Restore ARV(s) to 30 days OPERABLE staus.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ARV. In accordance with the Inservice Testing Program SR 3.7.4.2 Verify one complete cycle of each ARV block valve. 18 months Wolf Creek - Unit 1 3.7-1 0 Amendment No. 423, 127

Attachment II to WO 04-0003 AFW System Page 22 of 27 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS ___

CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply to 7 days turbine driven AFW pump OPERABLE status.

inoperable. AND 10 days from discovery of failure to meet the LCO B. One AFW train inoperable B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for reasons other than OPERABLE status.

Condition A. AND 10 days from discovery of failure to meet the LCO C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two AFW trains inoperable.

(continued)

Wolf Creek - Unit I 3.7-1 1 Amendment No. 123

Attachment II of WO 04-0003 Page 23 of 27 INSERT 4 bw. sn p C -NOTE -

LCO 3.0.4b. is not applicable when entering MODE 1.

Attachment II to WO 04-0003 AC Sources-Operating Page 24 of 27 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E power distribution subsystem(s); and

c. Load shedder and emergency load sequencers for Train A and Train B.

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

VNsrr 5 )

ACTIONS_

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 ----- NOTE In MODES 1, 2, and 3, the turbine driven auxiliary feedwater pump is considered a required redundant feature.

(continued)

Wolf Creek - Unit 1 3.8-1 Amendment No. 123 1of WO 04-0003 Page 25 of 27 INSERT 5

-NOTE- _ _ _ _____ _

LCO 3.0.4b. is not applicable to DGs.

Attachment II to WO 04-0003 Boron Concentration Page 26 of 27 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of all filled portions of the Reactor Coolant System and the refueling canal, that have direct access to the reactor vessel, shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

ACTIONS' CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.

AND A.2 Suspend positive reactivity Immediately additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit specified 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the COLR.

Wolf Creek - Unit 1 3.9-1 Amendment No. 123

Attachment II to WO 04-0003 RHR and Coolant Circulation - Low Water Level Page 27 of 27 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

OR A.2 Initiate action to establish Immediately 2 23 ft of water above the top of reactor vessel flange.

B. No RHR loop in operation. B.1 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND (continued)

Wolf Creek - Unit 1 3.9-9 Amendment No. 423, 145

Attachment III of WO 04-0003 Page 1 of 23 PROPOSED/REVISED TECHNICAL SPECIFICATIONS

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a 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 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 MODE or other (continued)

Wolf Creek - Unit 1 3.0-1 Amendment No. 423,

LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 specified condition in the Applicability, and establishment of risk (continued) management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications; or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in 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.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.15, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8, allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

Wolf Creek - Unit 1 3.0-2 Amendment No. 423,

SR Applicability 3.0 3.0 SR Applicability .

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into 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.

Wolf Creek - Unit 1 3.0-4 Amendment No. 423,

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be within the limit provided in the COLR.

APPLICABILITY: MODE 2 with kff < 1.0, MODES 3,4, and 5.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Wolf Creek - Unit 3.1-1 Amendment No. 423,

RTS Instrumentation 3.3.1 ACTIONS (continued) -

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months I inoperable. OPERABLE status.

OR C.2.1 Initiate action to fully insert 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months rods.

AND C.2.2 Place Rod Control System 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months in a condition incapable of rod withdrawal.

(continued)

Wolf Creek - Unit 3.3-2 Amendment No. 423,

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One or more required L.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel(s) inoperable. required state for existing unit condition.

OR L.2.1 Be in MODE 3. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND L.2.2 Be in MODE 4. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months M. One channel inoperable. M.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months I AND M.2 Restore channel to During OPERABLE status. performance of next COT N. One train inoperable. NOTE One train 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 provided the other train is OPERABLE.

N.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND N.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Wolf Creek - Unit 3.3-27 Amendment No. 123, 132,

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTIONS A _~~~~~~~~~~~~~~~~~v men r-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required channel to OPERABLE status.

inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.8.

met.

(continued)

Wolf Creek - Unit 1 3.3-37 Amendment No. 423,

Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 and the required auxiliary shutdown panel (ASP) controls shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS NOTE Separate Condition entry is allowed for each Function and required ASP control.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable. and required ASP controls to OPERABLE status.

OR One or more required ASP controls inoperable.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Wolf Creek - Unit 1 3.3-41 Amendment No. 4-23,

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

NOTES

1. All RHR pumps may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

a. The core outlet temperature is maintained at least 10F below saturation temperature;

b. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

c. Reactor vessel water level is above the vessel flange.

2. One RHR loop may be inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-17 Amendment No. 123, 131, 15,

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES I and 2, MODE 3 with all RCS cold leg temperatures > 368 0F.

ACTIONS

__________-- NOTI17 Separate Condition entry is allowed for each CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable of to associated block valve.

being manually cycled.

B. One PORV inoperable and B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not capable of being valve.

manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-23 Amendment No. 423,

LTOP System 3.4.12 APPLICABILITY: MODE 3, with any RCS cold leg temperature < 3681F, MODE 4, MODE 5, 1 MODE 6 when the reactor vessel head is on.

ACTIONS I,¶ Li r- --

LCO 3.0.4b is not applicable when entering MODE 4 or MODE 3. I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more safety A.1 Initiate action to verify a Immediately injection pumps capable of maximum of zero safety injecting into the RCS. injection pumps are capable of injecting into the RCS.

B. Two centrifugal charging B.1 Initiate action to verify a Immediately pumps capable of injecting maximum of one into the RCS. centrifugal charging pump is capable of injecting into the RCS.

C. An accumulator not C.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

(continued)

Wolf Creek - Unit 1 3.4-27 Amendment No. 4-3,

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. The containment sump level and flow monitoring system;

b. One containment atmosphere particulate radioactivity monitor; and

c. One containment air cooler condensate monitoring system or one containment atmosphere (gaseous) radioactivity monitor.

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

ACTIONS I CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 -NOTE sump level and flow Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months monitoring system after establishment of inoperable. steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump level and flow monitoring system to OPERABLE status.

(continued)

Wolf Creek - Unit 1 3.4-37 Amendment No. 123

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES I and 2, MODE 3 with RCS average temperature (Tang) Ž 500 0F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 NOTE

> 1.0 [ICi/gm. LCO 3.0.4c. is applicable. I A.1 Verify DOSE Once per4 hours EQUIVALENT 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific activity of B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months the reactor coolant Tang < 500 0F.

> 10O/ E l.Ci/grc.

(continued)

Wolf Creek - Unit 1 3.4-41 Amendment No. 123

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS -Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

NOTE An RHR subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

APPLICABILITY: MODE 4.

ACTIONS K1rr-Il I I LCO 3.0.4b. is not applicable to ECCS centrifugal charging pump subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months centrifugal charging pump CCP subsystem to (CCP) subsystem OPERABLE status.

inoperable.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

Wolf Creek - Unit 3.5-6 Amendment No. 423,

Hydrogen Recombiners 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Recombiners LCO 3.6.8 Two hydrogen recombiners shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen recombiner A.1 Restore hydrogen 30 days inoperable. recombiner to OPERABLE I status.

B. Two hydrogen B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recombiners inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.

(continued)

Wolf Creek - Unit 3.6-22 Amendment No. 423,

ARVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)

LCO 3.7.4 Four ARV lines shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ARV line inoperable A.1 Restore required ARV line 7 days for reasons other than to OPERABLE status. I excessive leakage.

B. Two ARV lines inoperable B.1 Restore all but one 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for reasons other than required ARV line to excessive leakage. OPERABLE status.

C. Three or more ARV lines C.1 Restore all but two ARV 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable for reasons lines to OPERABLE other than excessive status.

leakage.

(continued)

Wolf Creek - Unit 1 3.7-9 Amendment No. 23,-127,

ARVs 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. With one or more of the D.1 Initiate action to close the Immediately I ARVs inoperable because associated block valve(s).

of excessive seat leakage.

AND D.2 Restore ARV(s) to 30 days OPERABLE staus.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each ARV. In accordance with the Inservice Testing Program SR 3.7.4.2 Verify one complete cycle of each ARV block valve. 18 months Wolf Creek - Unit 3.7-10 Amendment No. 423, 27,

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTE-LCO 3.0.4b. is not applicable when entering MODE 1.

CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore steam supply to 7 days turbine driven AFW pump OPERABLE status.

inoperable. AND 10 days from discovery of failure to meet the LCO B. One AFW train inoperable B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for reasons other than OPERABLE status.

Condition A. AND 10 days from discovery of failure to meet the LCO (continued)

Wolf Creek - Unit 1 3.7-11 Amendment No. 423,

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR Two AFW trains inoperable.

D. Three AFW trains D.1 -NOTE inoperable. LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 NOTE Not required to be performed for the AFW flow control valves until the system is placed in standby or THERMAL POWER is > 10% RTP.

Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued)

Wolf Creek - Unit 1 3.7-1 2 Amendment No. 123,

AC Sources -Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Two diesel generators (DGs) capable of supplying the onsite Class 1E power distribution subsystem(s); and

c. Load shedder and emergency load sequencers for Train A and Train B.

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

ACTIONS I NL DTE LCO 3.0.4b. is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE offsite circuit.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 NOTE-In MODES 1, 2, and 3, the turbine driven auxiliary feedwater pump is considered a required redundant feature.

(continued)

Wolf Creek - Unit 1 3.8-1 Amendment No. 423,

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of all filled portions of the Reactor Coolant System and the refueling canal, that have direct access to the reactor vessel, shall be maintained within the limit specified in the COLR.

APPLICABILITY: MODE 6.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not A.1 Suspend CORE Immediately within limit. ALTERATIONS.

AND A.2 Suspend positive reactivity Immediately additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit specified 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in the COLR.

Wolf Creek - Unit 1 3.9-1 Amendment No. 4-3,

RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE. OPERABLE status.

OR A.2 Initiate action to establish Immediately 2 23 ft of water above the top of reactor vessel flange.

B. No RHR loop in operation. B.1 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND (continued)

Wolf Creek - Unit 1 3.9-9 Amendment No. 123,145,

Attachment IV to WO 04-0003 Page 1 of 38 TS BASES CHANGES (For Information Only)

Attachment IV to WO 04-0003 LCO Applicability Page 2 of 38 B 3.0 BASES LCO 3.0.3 The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the unit to be in (continued) MODE 5 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE is reached in less time than allowed, however, the total allowable time to reach MODE 5, or other applicable MODE, is not reduced. For example, if MODE 3 is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then the time allowed for reaching MODE 4 is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , because the total time for reaching MODE 4 is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

In MODES 1, 2, 3, and 4, LCO 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LCO 3.0.3 do not apply in MODES 5 and 6 because the unit is already in the most restrictive Condition required by LCO 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, 3, or 4) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken.

Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with LCO 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit. An example of this is in LCO 3.7.15, " Fuel Storage Pool Water Level." LCO 3.7.15 has an Applicability of "During movement of irradiated fuel assemblies in the fuel storage pool." Therefore, this LCO can be applicable in any or all MODES. If the LCO and the Required Actions of LCO 3.7.15 are not met while in MODE 1, 2, 3, or 4, there is no safety benefit to be gained by placing the unit in a shutdown condition. The Required Action of LCO 3.7.15 of "Suspend movement of irradiated fuel assemblies in the fuel storage pool" is the appropriate Required Action to complete in lieu of the actions of LCO 3.0.3. These exceptions are addressed in the individual Specifications.

LCO 3.10.4 LCO 3.0.4 establishes limitations on changes in MODES oi conditions in the Applicability when an LCO is not met. lti Gonit ni in a MODE or other specified condition atd in th

'-'--~-'(e.g.,Spplicability desired to be entered) when RtiPfKoWi Y~g nititi re su that notmet~ theA licabiF' Wolf Creek - Unit I B 3.0-4 Revision

Attachment IV of WO 04-0003 Page 3 of 38 INSERT B-1 when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4a., LCO 3.0.4b., or LCO 3.0.4c.

LCO 3.0.4a. 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.

Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a 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 MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

LCO 3.0.4b. 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.

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 LCO 3.0.4b., must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(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 11 of NUMARC 93-01, "Industry 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 MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

LCO 3.0.4b. 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 MODE or other specified condition in the Applicability, and any corresponding risk management actions. The LCO 3.0.4b. risk assessments do not have to be documented.

Attachment IV of WO 04-0003 Page 4 of 38 The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4b.

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 LCO 3.0.4b. allowance is prohibited.

The LCOs governing these system and components contain Notes prohibiting the use of LCO 3.0.4b. by stating that LCO 3.0.4b. is not applicable.

LCO 3.0.4c. allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4c. is applicable.

These specific allowances permit entry into 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 Required Action of a Specification.

The risk assessments performed to justify the use of LCO 3.0.4b usually only consider systems and components. For this reason, LCO 3.0.4c. is typically applied to Specifications which describe values and parameters (e.g., Containment Air Temperature, Containment Pressure, Moderator Temperature Coefficient), and may be applied to other Specifications based on NRC plant-specific approval.

-INSERT B-2

..S * . .. . . ..

..In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3,.-

'MODE 3 to MODE 4, and MODE 4 to MODE 5. -'.

INSERT B-3 Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.

Atahmn It O 400 Attachment IV to WO 04-0003 LCO Applicability Page 5 of 38 B 3.0 BASES unit for Hunlimfted p do i a Eptter peifd o prvide an a ept be evel of Wet3 for c ntnued 3ption. Th's wit, u regard t e status oge unit bwr or aftefhe MOD hange.

lfireor, n Mahcases, ryinto a <DE or on speci cni9

/the~~~~~~

mvbfd aodnev iplcbt in herosin f Requ /The provisions of this pcification should not be intepreed s enorsng he 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 Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.,-

.(I t-45wr 13-Z -

Wolf Creek - Unit 1 B 3.0-5 Revision 0

Attachment IV to WO 04-0003 LCO Applicability Page 6 of 38 8.

BASES LCO 3.0.4 Surveillances do not have to be performed on the associated inoperable (continued) equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, h nh ii co iti w)We nvn IOS~dH a~Xire wX L 34 (ne) noe(I excep~rnt e tgC .0. ss ed is not a violation of SR 3.0.1 or SR 3.0.4 fo uri nc have ed inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

LCO 3.0.5 LCO 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g., to not comply.

with the applicable Required Action(s)) 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 ACTIONS 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 example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions 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.

Wolf Creek - Unit 1 B 3.0-6 Revision 0

Attachment IV to WO 04-0003 SR Applicability Page 7 of 38 B3.0 BASES SR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a 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 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 component to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.

However, in certain circumstances, failing to meet an SR will not result in SR 3.0.4 restricting a 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 SR(s) are not required to be performed, per SR 3.0.1, which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes.,A GRG- _~8- N The provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are'required to comply with ACTIONS. In addition, the provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown...

The precise requirements 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 Surveillanc. A Surveillance that could not be performed until after A) entering the LCO 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 Wolf Creek - Unit 1 B 3.0-13 Revision 11

Attachment IV of WO 04-0003 Page 8 of 38 INSERT B-4 A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

INSERT B-5 SR 3.0.4 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 SR 3.0.3.

INSERT B-6 In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Attachment IV to WO 04-0003 SR Applicability Page 9of38 B 3.0 BASES SR 3.0.4 required (to be met or performed) until a particular event, condition, or (continued) time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.

Wolf Creek - Unit 1 B 3.0-14 Revision 11

Attachment IV to WO 04-0003 SDM Page 10 of 38 B 3.1.1 BASES LCO SDM is a core design condition that can be ensured during operation through control rod positioning (control and shutdown banks) and through the soluble boron concentration.

The MSLB (Ref. 2) and the boron dilution (Ref. 3) accidents are the most limiting analyses that establish the SDM value of the LCO. For MSLB accidents, if the LCO is violated, there is a potential to exceed the DNBR limit and to exceed 10 CFR 100, "Reactor Site Criteria," limits (Ref. 4).

For the boron dilution accident, if the LCO is violated, the minimum required time assumed for operator action to terminate dilution may no longer be sufficient. The required SDM limit is specified in the COLR.

APPLICABILITY In MODE 2 with keff < 1.0 and in MODES 3,4, and 5, the SDM requirements are applicable to provide sufficient negative reactivity to meet the assumptions of the safety analyses discussed above. In MODE 6, the shutdown reactivity requirements are given in LCO 3.9.1, "Boron Concentration." In MODES 1 and 2, SDM is ensured by complying with LCO 3.1.5, Shutdown Bank Insertion Limits," and LCO 3.1.6, "Control Bank Insertion:Limits:"

Th ppi lity is. odified ya No ating A*/ the ansitifm (DBto MOp 5 is n permit whileLCO 3. . is et. T s (IN156t B-ll) , 'Not prohibil he tran ion w n SDM 2initsar notme.This ote sures t t the ini assu tions o post I ted bo n dilut n evtin ACTIONS A.1 If the SDM requirements are not met, boration must be initiated promptly.

A Completion Time of 15 minutes is adequate for an operator to correctly align and start the required systems and components. It is assumed that boration will be continued until the SDM requirements are met.

In the determination of the required combination of boration flow rate and boron concentration, there is no unique requirement that must be satisfied. Since it is imperative to raise the boron concentration of the RCS as soon as possible, the borated water source should be a highly concentrated solution, such as that normally found in the boric acid storage tank, or the refueling water storage tank. The operator should borate with the best source available for the plant conditions.

Wolf Creek - Unit I B 3.1.1-4 Revision 13

Attachment IV of WO 04-0003 Page 11 of 38 INSERT B-1 1 Risk assessments performed pursuant to LCO 3.0.4.b should consider the desirability of entering MODE 5 from MODE 6 while not meeting the SDM limits. The risk assessment should assure that the initial condition assumptions of an inadvertent boron dilution event in MODE 5 are met.

Attachment IV to WO 04-0003 RTS Instrumentation Page 12 of 38 B 3.3.1 BASES ACTIONS C.1, C.2.1 and C.2.2 (continued)

This action addresses the train orientation of the SSPS for these Functions. With one channel or train inoperable, the inoperable channel or train must be restored to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . If the affected Function(s) cannot be restored to OPERABLE status within the allowed 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Completion Time, the unit must be placed in a MODE in which the requirement does not apply. To achieve this status, action must be initiated within the same 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to fully insert all rods and the Rod Control System must be rendered incapable of rod withdrawal within the next hour (e.g., by de-energizing all CRDMs, by opening the RTBs, or de-energizing the motor generator (MG) sets). The additional hour for the latter provides sufficient time to accomplish'the action in an orderly manner. With the rods fully inserted and Rod Control System incapable of rod withdrawal, these Functions are no longer required.

The Completion Time is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform the safety function, and given the low probability of an event occurring during this interval.

Con ion s modif dby a N estati that wh tiLCis not tfor F ctio 9, 20, o I in M E 5, ing the od ContrpSyste apa of rod hdrawa s not p tmitfed. is Note secifies n 1w4~1B ex . ption to~C 03.0.gfor this ODE 5 nsition a avoi placin e Cant in a e~ndition ere co rol rods an be a w# draw or not fy inserte d~while thy eactor lrrip Syst is degraed.

D.1.1. D.1.2, D.2.1, D.2.2, and D.3 Condition D applies to the Power Range Neutron Flux- High Function.

The NIS power range detectors provide input to the Rod Control System and, therefore, have a two-out-of-four trip logic. A known inoperable channel must be placed in the tripped condition. This results in a partial trip condition requiring only one-out-of-three logic for actuation. The 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months allowed to place the inoperable channel in the tripped condition is justified in WCAP-1 0271-P-A (Ref. 6).

In addition to placing the inoperable channel in the tripped condition, THERMAL POWER must be reduced to < 75% RTP within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Reducing the power level prevents operation of the core with radial power distributions beyond the design limits at a power level where DNB conditions may exist. With one of the NIS power range detectors inoperable, 1/4 of the radial power distribution monitoring capability is lost.

Wolf Creek - Unit I B 3.3.1-32 Revision 0

Attachment IV of WO 04-0003 Page 13 of 38 INSERT B-12 Risk assessments performed pursuant to LCO 3.0.4.b should consider the desirability of enabling the rod control system or allowing one or more rods to be other than fully inserted in MODE 5 while one train of Function 19 (one RTB train), Function 20 (one trip mechanism for one RTB), or Function 21 (one SSPS logic train) is inoperable and the reactor trip system is degraded. The risk assessment should assure that, prior to enabling the rod control system or allowing one or more rods to be other than fully inserted in MODE 5, procedural controls have been implemented to maintain the RCS boron concentration sufficient to preclude criticality with all control rods fully withdrawn. These procedural controls would mitigate any inadvertent rod withdrawal from subcritical transient.

Attachment IV to WO 04-0003 ESFAS Instrumentation Page 14 of 38 B 3.3.2 BASES ACTIONS L.1, L.2.1. and L.2.2 (continued) conditions in an orderly manner and without challenging unit systems.

Placing the unit in MODE 4 removes all requirements for OPERABILITY of this interlock.

M.1 and M.2 Condition M applies to the Auxiliary Feedwater Pump Suction Transfer on Low Suction Pressure Function. The condensate storage tank is the highly reliable and preferred suction source for the AFW pumps. This function has a 2 out of 3 trip logic. Therefore, continued operation is allowed with one inoperable channel until the performance of the next monthly COT on one of the other channels as long as the inoperable channel is laced in trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .jConc ion is dified y a Note' staf g th CO .0.4 not plic e., ODchas es ar pervfedw fhan~h ope ble pWanney g / / /

N.1 and N.2 Condition N applies to the Auxiliary Feedwater Balance of Plant ESFAS automatic actuation logic and actuation relays. With one train inoperable, the unit must be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 4 within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Required Actions are modified by a Note that allows one train to 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 provided the other train is OPERABLE.

0.1 Condition 0 applies to the Auxiliary Feedwater Manual Initiation Function.

The associated auxiliary feedwater pump(s) must be declared inoperable immediately when one or more channel(s) is inoperable. Refer to LCO 3.7.5, "Auxiliary Feedwater (AFW) System."

P.1, P.2.1. and P.2.2 Condition P applies to the Auxiliary Feedwater Loss of Offsite Power Function. With the inoperability of one or both train(s), 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is allowed to return the train(s) to OPERABLE status. The specified Completion Time is reasonable considering the fact that this Function is associated only with the turbine driven AFW pump, the available Wolf Creek - Unit 1 B 3.3.2-42 Revision

Attachment IV to WO 04-0003 Page 15 of 38B Page15 of 38 ~~~~~~~~~PAM Instrumentation BASES LCO 18. Auxiliary Feedwater Flow Rate (continued)

to verify delivery of AFW flow to the SGs;

to determine whether to terminate Si if still in progress, in conjunction with SG water level (narrow range); and

to regulate AFW flow so that the SG tubes remain covered.

AFW flow is also used by the operator to verify that the AFW System is delivering the correct flow to each SG. However, the primary indication used by the operator to ensure an adequate inventory is SG level.

19. Refueling Water Storage Tank (RWST) Level Refueling Water Storage Tank Level is a Type A, Category 2 variable for determining switchover of containment spray to the containment recirculation sumps. This level indication is provided for the operators to assist in monitoring and ensuring an adequate supply of water for safety injection and containment spray. Table 2 of Reference 2 requires all plant-specific Type A variables to meet Category 1 design and qualification criteria; however, RWST Level is specifically identified in that same table as a Type D Category 2 variable. In this specific case, as discussed in Sections 7.A.3.1 and 7A.3.6 of Reference 1,the requirements of Category 1 are met.

APPLICABILITY The PAM instrumentation LCO is applicable in MODES 1, 2 and 3. These variables are related to the diagnosis and pre-planned actions required to mitigate DBAs. The applicable DBAs are assumed to occur in MODES 1, 2 and 3. In MODES 4, 5 and 6, unit conditions are such that the likelihood of an event that would require PAM instrumentation is low; therefore, the PAM instrumentation is not required to be OPERABLE in these MODES.

ACTIONS b de n eC S-to e de th ange r tric on of 0 3.0.4 his exc tion all s entry nto th pplica WIEwhireying sthe ACTIN ev t oug ,te AC ONS H enua rqurfi hton Thisl xeptiof I cc pable~e t tW

'pasiy~unciondf he nstffients t0p ora r's ab y rsond tn accj ent using/alternate, strumen and m ods, d the w pro bility Wolf Creek - Unit I B 3.3.3-1 0 Revision

Attachment IV to WO 04-0003 PAM Instrumentation Page 16 of 38 BIs3n B 3.3.3 BASES ACTIONS Note )has been added in the ACTIONS to clarify the application of (continued) H Completion Time rules. The Conditions of this Specification may be vT entered independently for each Function listed on Table 3.3.3-1. The Completion Time(s) of the inoperable channel(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function. When the Required Channels in Table 3.3.3-1 are specified on a per SG basis, then the Condition may be entered separately for each SG..

A.1 Condition A applies when one or more Functions have one required channel that is inoperable. Required Action A.1 requires restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channel, the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.

B.1 Condition B applies when the Required Action and associated Completion Time for Condition A are not met. This Required Action specifies initiation of actions in Specification 5.6.8, which requires a written report to be submitted to the NRC within the following 14 days. This action is appropriate in lieu of a shutdown requirement since alternative actions are identified before loss of functional capability, and given the likelihood of unit conditions that would require information provided by this instrumentation.

C.1 Condition C applies when one or more Functions have two or more inoperable required channels (i.e., two or more channels inoperable in the same Function). Required Action C.1 requires restoring all but one channel in the Function(s) to OPERABLE status within 7 days. The Completion Time of 7 days is based on the relatively low probability of an event requiring PAM instrument operation and the availability of alternate means to obtain the required information. Continuous operation with two or more required channels inoperable in a Function is not acceptable because the alternate indications may not fully meet all performance Wolf Creek - Unit 1 B 3.3.3-11 Revision 8

Attachment IV to WO 04-0003 Remote Shutdown System Page 17 of 38 B 3.3.4 BASES APPLICABILITY The Remote Shutdown System LCO is applicable in MODES 1, 2, and 3.

This is required so that the unit can be placed and maintained in MODE 3 for an extended period of time from a location other than the control room.

This LCO is not applicable in MODE 4, 5, or 6. In these MODES, the facility is already subcritical and in a condition of reduced RCS energy.

Under these conditions, considerable time is available to restore the remote shutdown instruments and required ASP controls if control room instruments or controls become unavailable.

ACTIONS N iclude hich e udes t MOD hang estri on of CO .O .4. T except allows ntry into n app cable ODE ile relg on t ACTIO even t ugh the CTIO ma eventu y r uire a it shut wn. Thi xceptio is acc table ue to e low probabi y of an ent req ing the emote utdo n Syst and bec se the e uipment n generly be re aire uring eratlo sw0uig cnt ris ksui y Note"has been added to the ACTIONS to clarify the application of

<J Completion Time rules. Separate Condition entry is allowed for each

& - 'Function listed on Table 3.3.4-1 and for each required ASP control. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

When the Required Channels in Table 3.3.4-1 are specified on a per trip breaker, per SG, or per pump basis, the Condition may be entered separately for each trip breaker, SG, or pump, as appropriate.

A.1 Condition A addresses the situation where one or more required Functions of the Remote Shutdown System in Table 3.3.4-1, or one or more required ASP controls are inoperable.

The Required Action is to restore the required Function and ASP control to OPERABLE status within 30 days. The Completion Time is based on operating experience and the low probability of an event that would require evacuation of the control room.

Wolf Creek - Unit 1 B 3.3.4-4 .Revision 1

Attachment IV to WO 04-0003 RCS Loops - MODE 5, Loops Not Filled Page 18 of 38 B 3.4.8 BASES LCO Note I permits all RHR pumps to be removed from operation for

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

(continued) The circumstances for stopping both RHR pumps are to be limited to situations when the outage time is short and core outlet temperature is maintained at least 100 F below saturation temperature. The Note prohibits boron dilution with coolant at boron concentrations less than required to assure the SDM of LCO 3.1.1 is maintained or draining operations when RHR forced flow is stopped. The Note requires reactor vessel water level be above the vessel flange to ensure the operating RHR pump will not be intentionally deenergized during mid-loop operations.

Note 2 allows one RHR loop to be inoperable for a period of

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , provided that the other loop is OPERABLE and in operation. This permits periodic surveillance tests to be performed on the inoperable loop during the only time when these tests are safe and possible.

An OPERABLE RHR loop is comprised of an OPERABLE RHR pump capable of providing forced flow to an OPERABLE RHR heat exchanger.

RHR pumps are OPERABLE if they are capable of being powered and are able to provide flow if required.

APPLICABILITY In MODE 5 with loops not filled, this LCO requires core heat removal and coolant circulation by the RHR System. One RHR loop provides sufficient capability for this purpose. However, one additional RHR loop is required to be OPERABLE to meet single failure considerations.

Operation in other MODES is covered by:

LCO 3.4.4, "RCS Loops - MODES 1 and 2";

LCO 3.4.5, "RCS Loops - MODE 3";

LCO 3.4.6, "RCS Loops - MODE 4";

LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled";

LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - High Water Level" (MODE 6); and LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level" (MODE 6).

Wolf Creek - Unit 1 B 3.4.8-2 .Revision 13

Attachment IV of WO 04-0003 Page 19 of 38 INSERT B-13 Risk assessments performed pursuant to LCO 3.0.4.b should consider the desirability of draining the RCS in MODE 5 while the requirements of this LCO are not met and this LCO is entered from LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled." The risk assessment should consider whether it is prudent to remove the heat removal path afforded by the steam generators when the RHR system is degraded.

Attachment IV to WO 04-0003 Pressurizer PORVs Page 20 of 38 B 3.4.11 BASES LCO exists when conditions dictate closure of the block valve to limit leakage (continued) Satisfying the LCO helps minimize challenges to fission product barriers.

APPLICABILITY In MODES 1, 2, and 3 (with all RCS cold leg temperatures above 3680F),

the PORVs are required to be OPERABLE to limit the potential for a small break LOCA through the flow path. The most likely cause for a PORV small break LOCA is a result of a pressure increase transient that causes the PORV to open. Imbalances in the energy output of the core and heat removal by the secondary system can cause the RCS pressure to increase to the PORV opening setpoint. The most rapid increases will occur at the higher operating power and pressure conditions of MODES I and 2. Although not a required function, the PORVs OPERABILITY in MODES 1, 2, and 3 (with all RCS cold leg temperatures above 3680F) also serves the desired function of minimizing challenges to the pressurizer safety valves. The PORVs are also required to be OPERABLE in MODES 1, 2, and 3 (with all RCS cold leg temperatures above 368 0F) for manual actuation to mitigate a Steam Generator Tube Rupture event.

Pressure increases are less prominent in MODE 3 because the core input energy is reduced, but the RCS pressure is high. Therefore, the LCO is applicable in MODES 1, 2, and 3 (with all RCS cold leg temperatures above 3681F). The LCO is not applicable in MODES 3 (with any RCS cold leg temperature S 368 0F) 4, 5, and 6 (with the reactor vessel head in place) when both pressure and core energy are decreased and the pressure surges become much less significant. LCO 3.4.12 addresses the PORV requirements in these MODES.

ACTIONS Note I has been added to clarify that all pressurizer PORVs are treated as separate entities, each with separate Comletion Times (i.e., the Coiletion Time is on a component basis. N e 2 p vide an ex ption for 0 .4w wchppmits tryint OD 1, ,and ope rm din f theOR orbbck val s tov rify thrOP BL statu n the ent at teing wX not s isfacily p orme in low MORS A.1 PORVs may be inoperable and capable of being manually cycled (e.g.,

excessive seat leakage). In this condition, either the PORVs must be

- Wolf Creek - Unit 1 B 3.4.1 1-3 Revision I I

Attachment IV to WO 04-0003 LTOP System Page 21 of 38 B 3.4.12 BASES

-LCO Each of these methods of overpressure prevention is capable of (continued) mitigating the limiting LTOP transient.

APPLICABILITY This LCO is applicable in MODE 3 when any RCS cold leg temperature is

< 368 0F, in MODE 4, in MODE 5 and in MODE 6 when the reactor vessel head is on. The pressurizer safety valves provide overpressure protection that meets the Reference I P/T limits in MODES 1, 2, and 3.

When the reactor vessel head is off, overpressurization cannot occur.

LCO 3.4.3 provides the operational PIT limits for all MODES. LCO 3.4.10, "Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3.

Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event.

A.1 and B.1 With one or more safety injection pumps or two centrifugal charging pumps capable of injecting into the RCS, RCS overpressurization is possible.

To immediately initiate action to restore restricted coolant input capability to the RCS reflects the urgency of removing the RCS from this condition.

C.1, D.1. and D.2 An unisolated accumulator requires isolation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . This is only required when the accumulator pressure is at or more than the maximum RCS pressure for the existing temperature allowed by the P/T limit curves.

Wolf Creek - Unit 1 B 3.4.12-9 Revision 0

Attachment IV of WO 04-0003 Page 22 of 38 INSERT B-7 A Note prohibits the application of LCO 3.0.4b. to an inoperable LTOP System. There is an increased risk associated with entering MODE 3 from MODE 4 and MODE 4 from MODE 5 with LTOP inoperable and the provisions of LCO 3.0.4b., which allow 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, should not be applied in this circumstance.

Attachment IV to WO 04-0003 RCS Leakage Detection Instrumentation Page 23 of 38 B 3.4.15 BASES APPLICABILITY The cti s ar odifiby a N that i cates at the ovi ns of (continued) 0 .. 4 arnot a licable s a re t, a M E ch ge i howe w theontaient Su p Level nd Flo nit ng S temi oper le. TH allowce is prded be use er inrume atio s ACTIONS A.1 and A.2 A primary system leak would result in reactor coolant flowing into the containment normal sumps or into the instrument tunnel sump. Indication of increasing sump level is transmitted to the control room by means of individual sump level transmitters. This information is used to provide measurement of low leakage by monitoring level increase versus time.

With the required Containment Sump Level and Flow Monitoring System inoperable, no other form of sampling can provide the equivalent information; however, the containment atmosphere particulate radioactivity monitor will provide indications of changes in leakage.

Together with the atmosphere monitor, the periodic surveillance for RCS water inventory balance, SR 3.4.13.1, must be performed at an increased frequency of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to provide information that is adequate to detect leakage. A Note is added allowing that SR 3.4.13.1 is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishing steady state operation (near operating rated operating pressure with stable RCS pressure, temperature, power level, pressurizer and makeup tank level, makeup and letdown, and RCP seal injection and return flows). The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ' allowance provides sufficient time to collect and process all necessary data after stable plant conditions are established.

Restoration of the required Containment Sump Level and Flow Monitoring System to OPERABLE status within a Completion Time of 30 days is required to regain the function after the system's failure. This time is acceptable, considering the Frequency and adequacy of the RCS water inventory balance required by Required Action A.1.

B.1.1. B.1.2, and B.2 With the containment atmosphere particulate radioactivity monitoring instrumentation channel inoperable, alternative action is required. Either samples of the containment atmosphere must be taken and analyzed for gaseous and particulate radioactivity or water inventory balances, in accordance with SR 3.4.13.1, must be performed to provide alternate periodic information.

Wolf Creek - Unit 1 B 3.4.15-4 Revision 9

Attachment IV to WO 04-0003 RCS Specific Activity Page 24 of 38 6 tic~c rvy-s Ye6 U!Er ad gopo rA CO 3.0.4c-TIs L> Ctilo6u30nc-B)NSES -- I - -- - - - -

A(C.TIONS 9 . nA-2 (continued)

A ote the R red on n festriion of 0 3.0, This xcepf n allos ent into cable MM ECS),ile re g on)e AC NS enth t AC NS a ventuw requirplant sfutiutdo is is acceptable du Tiesignificant conservatism incorporated into the specific activity limit, the I IbLdd nm low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient specific activity excursions while the plant remains at, or proceeds to power operation.

B.1 With the gross specific activity in excess of the allowed limit, the unit must be placed in a MODE in which the requirement does not apply.

The change within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to MODE 3 and RCS average temperature

< 500OF lowers the saturation pressure of the reactor coolant below the setpoints of the main steam safety and atmospheric relief valves and prevents venting the SG to the envir6nment in an SGTR event. The allowed Completion Time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is reasonable, based on operating experience, to reach MODE 3 below 500OF from full power conditions in an orderly manner and without challenging plant systems.

C.1 If a Required Action and the associated Completion Time of Condition A is not met or if the DOSE EQUIVALENT 1-131 is in the unacceptable region of Figure 3.4.16-1, the reactor must be brought to MODE 3 with RCS average temperature < 500 0F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Completion Time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is reasonable, based on operating experience, to reach MODE 3 below 500OF from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE

SR 3.4.16.1 REQUIREMENTS SR 3.4.16.1 requires performing a gamma isotopic analysis as a measure of the gross specific activity of the reactor coolant at least once every 7 days. While basically a quantitative measure of radionuclides with half lives longer than 15 minutes, excluding iodines, this measurement is the Wolf Creek - Unit I B 3.4.16-4 Revision

Attachment IV to WO 04-0003 ECCS - Shutdown Page 25 of 38 B 3.5.3 BASES LCO In MODE 4, an ECCS train consists of a centrifugal charging subsystem (continued) and an RHR subsystem. Each train includes the piping, instruments, and controls to ensure an OPERABLE flow path capable of taking suction from.

the RWST and transferring suction to the containment sump.

During an event requiring ECCS actuation, a flow path is required to provide an abundant supply of water from the RWST to the RCS via the ECCS pumps and their respective supply headers to two cold leg injection nozzles. I In the long term, this flow path may be switched to take its supply from the containment sump and to deliver its flow to the RCS hot and cold legs.

This LCO is modified by a Note that allows an RHR train to be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the ECCS mode of operation and not otherwise inoperable. This allows operation in the RHR mode during MODE 4.

APPLICABILITY In MODES 1, 2, and 3, the OPERABILITY requirements for ECCS are covered by LCO 3.5.2.

In MODE 4 with RCS temperature below 350 0F, one OPERABLE ECCS train is acceptable without single failure consideration, on the basis of the stable reactivity of the reactor and the limited core cooling requirements.

In MODES 5 and 6, plant conditions are such that the probability of an event I requiring ECCS injection is extremely low. Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, RCS Loops -MODE 5, Loops Filled,"

and LCO 3.4.8, "RCS Loops - MODE 5, Loops Not Filled." MODE 6 core cooling requirements are addressed by LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - High Water Level," and LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level."

ACTIONS A/.1 lN6ER;1- ~j With no ECCS RHR subsystem OPERABLE, the plant is not prepared to respond to a loss of coolant accident or to continue a cooldown using the Wolf Creek- Unit I B 3.5.3-2 Revision 16

Attachment IV of WO 04-0003 Page 26 of 38 INSERT B-8 A Note prohibits the application of LCO 3.0.4b. to an inoperable ECCS centrifugal charging pump subsystem when entering MODE 4. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS centrifugal charging pump subsystem and the provisions of LCO 3.0.4b. which allow 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, should not be applied in this circumstance.

Attachment IV to WO 04-0003 Page 27 of 38 Hydrogen Recombiners B 3.6.8 BASES APPLICABILITY In MODES 5 and 6, the probability and consequences of a LOCA are low, (continued) due to the pressure and temperature limitations in these MODES.

Therefore, hydrogen recombiners are not required in these MODES.

ACTIONS A.1 With one containment hydrogen recombiner inoperable, the inoperable recombiner must be restored to OPERABLE status within 30 days. In this condition, the remaining OPERABLE hydrogen recombiner is adequate to perform the hydrogen control function. However, the overall reliability is reduced because a single failure in the OPERABLE recombiner could result in reduced hydrogen control capability. The 30 day Completion Time is based on the availability of the other hydrogen recombiner, the low probability of a LOCA or SLB occurring (that would generate an amount of hydrogen that exceeds the flammability limit), and the amount of time available after a LOCA or SLB (should one occur) for operator action to prevent hydrogen accumulation from exceeding the flammability limit.

Re.uir, Act e a ot at sta the govis ns oCO 3. are no applic e. As result, MOD hang is a l~wed dihen on recoi er i erable This owanc s bas orithe ailabilit of the o erhydroen rec biner he low robab y of LOX or SL occurri (that w Id gen aea mou of hyd gen tha xceed he flam ability Ii it), and e am nt of e av able er OCA o LB for erator tion to event ydrog acc ulatio B.1 and B.2 With two hydrogen recombiners inoperable, the ability to perform the hydrogen control function via alternate capabilities must be verified by administrative means within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The alternate hydrogen control capabilities are provided by the containment Hydrogen Purge System.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time allows a reasonable period of time to verify that a loss of hydrogen control function does not exist. Both the initial verification and all subsequent verifications may be performed as an administrative check by examining logs or other information to determine the availability of the alternate hydrogen control system. It does not mean to perform the Surveillances needed to demonstrate OPERABILITY of the alternate hydrogen control system. If the ability to perform the hydrogen control function is maintained, continued operation is permitted with two hydrogen recombiners inoperable for up to 7 days. Seven days is a reasonable time to allow two hydrogen recombiners to be inoperable because the hydrogen control function is maintained and because of the low probability of the occurrence of a LOCA that would generate hydrogen in the amounts capable of exceeding the flammability limit.

Wolf Creek - Unit 1 B 3.6.8-3 Revision 0

Attachment IV to WO 04-0003 ARVs Page 28 of 38 B 3.7.4 BASES LCO acceptance criterion, exists when conditions dictate closure of the block (continued) valve to limit leakage.

The nitrogen accumulator tanks supplying the turbine driven AFW pump control valves and the steam generator atmospheric relief valves ensure an eight hour supply for the pump and valves.

APPLICABILITY In MODES 1, 2, and 3, the ARV lines are required to be OPERABLE.

In MODE 4, the pressure and temperature limitations are such that the probability of a SGTR event requiring ARV operation is low. In addition, the RHR System is available to provide the decay heat removal function in MODE 4. Therefore, the ARV lines are not required to be OPERABLE in MODE 4.

In MODE 5 or 6, an SGTR is not a credible event.

ACTIONS A.1 With one ARV line inoperable for reasons other than excessive leakage, action must be taken to restore the ARV line to OPERABLE status within l 7 days. The 7 day Completion Time allows for the redundant capability afforded by the remaining OPERABLE ARV lines, a nonsafet grade backu in the Turbine Bypass System, and MSSVs.Ie i 7 B.1-l With two ARV lines inoperable for reasons other than excessive ARV seat leakage, action must be taken to restore all but one ARV line to OPERABLE status. Since the block valve can be closed to isolate an ARV, some repairs may be possible with the unit at power. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable to repair inoperable ARV lines, based on the availability of the Turbine Bypass System and/or MSSVs, and the low probability of an event occurring during the restoration period that would require the ARV lines.

. Wolf Creek - Unit B 3.7.4-3 Revision 1

Attachment IV to WO 04-0003 ARVs Page 29 of 38 B 3.7.4 BASES ACTIONS C.1 (continued)

With three or more ARV lines inoperable for reasons other than excessive leakage, action must be taken to restore all but two ARV lines to OPERABLE status. Since the block valve can be closed to isolate an ARV, some repairs may be possible with the unit at power. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is reasonable to repair inoperable ARV lines, based on the availability of the Turbine Bypass System and MSSVs, and the low probability of an event occurring during this period that would require the ARV lines.

D.1 and D.2 Requiring a 30 day limit for restoring an ARV valve to OPERABLE status from inoperable, due to excessive seat leakage from the valve, provides assurance that the required number of ARVs will be available for plant cooldown. This action limits the period in which a block valve is closed due to excessive seat leakage of the ARV and minimizes the delay associated with manually opening a cl d manual isolation valve due to excessive seat leakage of IhAVIJebrcAtosDladP2a¢ E.1 and E.2 If the ARV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in MODE 4 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.4.1 REQUIREMENTS To perform a controlled cooldown of the RCS, the ARVs must be able to be opened remotely and throttled through their full range. This SR ensures that the ARVs are tested through a full control cycle at least once per fuel cycle. Performance of inservice testing satisfies this requirement, and use of an ARV during a unit cooldown may satisfy this requirement.

Operating experience has shown that these components usually pass the Surveillance when performed at the required Inservice Testing Program Frequency. The Frequency is acceptable from a reliability standpoint.

Wolf Creek - Unit 1 B 3.7.4-4 .Revision 1

Attachment IV to WO 04-0003 AFW System Page 30 of 38 AFWB 3.7.5 BASES APPLICABILITY In MODE 5 or 6, the steam generators are not normally used for heat (continued) removal, and the AFW System is not required.

ACTIONS A.1 INER B' If one of the two steam supplies to the turbine driven AFW train is inoperable, action must be taken to restore OPERABLE status within 7 days.

The 7 day Completion Time is reasonable, based on the following reasons:

a. The redundant OPERABLE steam supply to the turbine driven AFW pump;

b. The availability of redundant OPERABLE motor driven AFW pumps; and

c. The low probability of an event occurring that requires the inoperable steam supply to the turbine driven AFW pump.

The second Completion Time for Required Action A.1 establishes a limit on the maximum time allowed for any combination of Conditions to be inoperable during any continuous failure to meet this LCO.

The 10 day Completion Time provides a limitation time allowed in this specified Condition after discovery of failure to meet the LCO. This limit is considered reasonable for situations in which multiple Conditions are entered concurrently. The AND connector between 7 days and 10 days dictates that both Completion Times apply simultaneously, and the more restrictive must be met.

B.1 With one of the required AFW trains (pump or flow path) inoperable for reasons other than Condition A, action must be taken to restore OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . This Condition includes the loss of two steam supply lines to the turbine driven AFW pump. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable, based on redundant capabilities afforded by the AFW System, time needed for repairs, and the low probability of a DBA occurring during this time period.

The second Completion Time for Required Action B.1 establishes a limit on the maximum time allowed for any combination of Conditions to be inoperable during any continuous failure to meet this LCO.

- Wolf Creek - Unit 1 B 3.7.5-5 Revision 16

Attachment IV of WO 04-0003 Page 31 of 38 INSERT B-9 A Note prohibits the application of LCO 3.0.4b. to an inoperable AFW train when entering MODE 1. There is an increased risk associated with entering MODE 1 with an AFW train inoperable and the provisions of LCO 3.0.4b., which allow 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, should not be applied in this circumstance.

Attachment IV to WO 04-0003 AC Sources - Operating Page 32 of 38 B 3.8.1 BASES LCO achieved. Upon failure of the DG jacket water keep warm system, the DG (continued) remains OPERABLE as long as jacket water temperature is 2 105 F (Ref. 13).

Initiating an EDG start upon a detected undervoltage or degraded voltage condition, tripping of nonessential loads, and proper sequencing of loads, is a required function of LSELS and required for DG OPERABILITY. In addition, the LSELS Automatic Test Indicator (ATI) is an installed testing aid and is not required to be OPERABLE to support the sequencer function. Absence of a functioning ATI does not render LSELS inoperable.

The AC sources in one train must be separate and independent of the AC sources in the other train. For the DGs, separation and independence are complete.

For the offsite AC source, separation and independence are to the extent practical. A circuit may be connected to more than one ESF bus provided the appropriate LCO Required Actions are entered for loss of one offsite power source.

APPLICABILITY The AC sources and LSELS are required to be OPERABLE in MODES 1, 2, 3, and 4 to ensure that:.

a. Acceptable fuel design limits and reactor coolant pressure boundary limits are not exceeded as a result of AOOs or abnormal transients; and

b. Adequate core cooling is provided and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.

The AC power requirements for MODES 5 and 6 are covered in LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS .1 (llfilg B-, To ensure a highly reliable power source remains with one offsite circuit inoperable, it is necessary to verify the OPERABILITY of the remaining required offsite circuit on a more frequent basis. Since the Required Action only specifies "perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action not met. However, if the second Wolf Creek - Unit 1 B 3.8.1-4 Revision 6

Attachment IV of WO 04-0003 Page 33 of 38 INSERT B-10 A Note prohibits the application of LCO 3.0.4b. to an inoperable DG. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable DG and the provisions of LCO 3.0.4b., which allow 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, should not be applied in this circumstance.

Attachment IV to WO 04-0003 Boron Concentration Page 34 of 38 B 3.9.1 BASES BACKGROUND Circulation - Low Water Level") to provide forced circulation in the RCS (continued) and assist in maintaining the boron concentrations in the RCS and the refueling pool above the COLR limit.

APPLICABLE The boron concentration limit specified in the COLR is based on the core SAFETY ANALYSES reactivity at the beginning of each fuel cycle (the end of refueling) and includes an uncertainty allowance.

The required boron concentration and the plant refueling procedures that verify the correct fuel loading plan (including full core mapping) ensure that the kef of the core will remain < 0.95 during the refueling operation.

Hence, at least a 5% AkIk margin of safety is established during refueling.

During refueling, the water volume in the spent fuel pool, the transfer canal, the refueling pool,-cask loading pool, and the reactor vessel form a single mass. As a result, the soluble boron concentration is relatively the same in each of these connected volumes having direct access to the reactor vessel.

Boron dilution accidents are precluded in MODE 6 by isolating potential dilution flow paths. See LCO 3.9.2, "Unborated Water Source Isolation Valves."

The RCS boron concentration satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

LCO The LCO requires that a minimum boron concentration be maintained in the filled portions of the RCS and the refueling canal, that have direct access to the reactor vessel while in MODE 6. The boron concentration limit specified in the COLR ensures that a core kff of < 0.95 is maintained during fuel handling operations. Violation of the LCO could lead to an inadvertent criticality during MODE 6.

APPLICABILITY This LCO is applicable in MODE 6 to ensure that the fuel in the reactor vessel will remain subcritical. The required boron concentration ensures a keff 0.95. Above MODE 6, LCO 3.1.1, "SHUTDOWN MARGIN (SDM),"

LCO 3.1.5, "Shutdown Bank Insertion Limits" and LCO 3.1.6, Control Bank Insertion Limits," ensure that an adequate amount of negative.

reactivity is available to shut down the reactor and maintain it subcritical.

ThAppcabilit s mnified e at at t nsit<Sn fr M9 6 E M ht i . T N p i e so Wolf Creek - Unit 1 B 3.9.1-2 Revision 13

Attachment IV to WO 04-0003 Boron Concentration Page 35 of 38 B 3.9.1 BASES APPLICABILITY o e a ov (continued) w i d i1ainin4 fuelandlip Idz u / 7'i ACTIONS A.1 and A.2 Continuation of CORE ALTERATIONS or positive reactivity additions (including actions to reduce boron concentration) is contingent upon maintaining the unit in compliance with the LCO. If the boron concentration of any coolant volume in the filled portions of the RCS, and the refueling canal, that have direct access to the reactor vessel, is less than its limit, all operations involving CORE ALTERATIONS or positive reactivity additions must be suspended immediately.

Suspension of CORE ALTERATIONS and positive reactivity additions shall not preclude moving a component to a safe position. Operations that individually add limited positive reactivity (e.g., temperature fluctuations, inventory addition, or temperature control fluctuations), but when combined with all other operations affecting core reactivity (e.g.,

intentional boration) result in overall net negative reactivity addition, are not precluded by this action.

A.3 In addition to immediately suspending CORE ALTERATIONS and positive reactivity additions, boration to restore the concentration must be initiated immediately.

In determining the required combination of boration flow rate and concentration, no unique Design Basis Event must be satisfied. The only requirement is to restore the boron concentration to its required value as soon as possible. In order to raise the boron concentration as soon as possible, the operator should begin boration with the best source available for unit conditions.

Once actions have been initiated, they must be continued until the boron concentration is restored. The restoration time depends on the amount of boron that must be injected to reach the required concentration.

SURVEILLANCE SR 3.9.1.1 REQUIREMENTS This SR ensures that the coolant boron concentration in the filled portions of the RCS and the refueling canal, that have direct access to the reactor vessel, is within the COLR limits. The boron concentration of the coolant in each required volume is determined periodically by chemical analysis.

Wolf Creek - Unit 1 B 3.9.1-3 Revision 13

Attachment IV of WO 04-0003 Page 36 of 38 INSERT B-14 Risk assessments performed pursuant to LCO 3.0.4.b should consider the desirability of entering MODE 6 from MODE 5 boron concentration limits of this LCO. The risk assessment should assure that the core reactivity limits are maintained during fuel handling operations.

Attachment IV to WO 04-0003 RHR and Coolant Circulation - Low Water Level Page 37 of 38 B 3.9.6 BASES LCO C. Indication of reactor coolant temperature.

(continued)

An OPERABLE RHR loop consists of an RHR pump, a heat exchanger, valves, piping, instruments and controls to ensure an OPERABLE flow path and to determine the RCS temperature. The flow path starts in one of the RCS hot legs and is returned to the RCS cold legs. An OPERABLE RHR loop must be capable of being realigned to provide an OPERABLE flow path.

APPLICABILITY Two RHR loops are required to be OPERABLE, and one RHR oop must be in operation in MODE 6, with the water level < 23 ft above the top of the reactor vessel flange, to provide decay heat removal.

Requirements for the RHR System in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS), and Section 3.5, Emergency Core Cooling Systems (ECCS). RHR loop requirements in MODE 6 with the water level 2 23 ft are located in LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - High Water Level."

T licA ityis dified yaN e aing at e riaOD o

,thselIeD c ition he A pica ty int p t idwle

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tI3Stf 6-15) > 'L is t methis Noe wou preent th trantion' to D 6

~~~ Xth eg than~i feet wat /b, th io ye e l'ghl ACTIONS A.1 and A.2 If less than the required number of RHR loops are OPERABLE, action shall be immediately initiated and continued until the RHR loop is restored to OPERABLE status and to operation in accordance with the LCO or until 2 23 ft of water level is established above the reactor vessel flange. When the water level is 2 23 ft above the reactor vessel flange, the Applicability changes to that of LCO 3.9.5, and only one RHR loop is required to be OPERABLE and in operation. An immediate Completion Time is necessary for an operator to initiate corrective actions.

B.1 If no RHR loop is in operation, there will be no forced circulation'to provide mixing to establish uniform boron concentrations. Suspending positive reactivity additions that could result in failure to meet the' minimum boron concentration limit of LCO 3.9.1 is required to assure Wolf Creek - Unit 1 B 3.9.6-2 Revision 13

Attachment IV of WO 04-0003 Page 38 of 38 INSERT B-15 Since LCO 3.9.6 contains Required Actions with immediate Completion Times related to the restoration of the degraded de6ay heat removal function, it is not permitted to enter this LCO from either MODE 5 or from LCO 3.9.5, RHR and Coolant Circulation - High Water Level,"

unless the requirements of LCO 3.9.6 are met. This precludes diminishing the backup decay heat removal capability when the RHR System is degraded.

Attachment V to WO 04-0003 Page 1 of 1 LIST OF COMMITMENTS The following table identifies those actions committed to by Wolf Creek Nuclear Operating Corporation (WCNOC) in this document. Any other statements in Attachment I of this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr. Kevin Moles, Manager Regulatory Affairs at Wolf Creek Generating Station, (620) 364-4126.

COMMITMENT Due Date/Event Revision to the TS Bases will be implemented pursuant to the TS Upon Bases Control Program, TS 5.5.14, upon implementation of this implementation of license amendment. amendment The license amendment, as approved, will be implemented within Within 90 days of 90 days from the date of issuance. issuance of the amendment

WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process

Contents

Text

Subject:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

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WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process

Text

Subject:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

5.0 REGULATORY ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

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