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License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1.
	ML24213A335
Person / Time
Site:	Wolf Creek
Issue date:	07/31/2024
From:	Boyce M; Wolf Creek
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	000269
	Download: ML24213A335 (1)
	v • d • e

Michael T. Boyce Vice President Engineering

July 31, 2024 000269

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC FQ Surveillance Technical Specifications

Commissioners and Staff:

In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Wolf Creek Nuclear Operating Corporation (WCNOC) requests an amendment to Renewed Facility Operating License No. NPF-42 to revise the Technical Specifications (TS) for the Wolf Creek Generating Station (WCGS), Unit 1. The proposed amendment modifies the WCGS TS 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology), to implement the methodology in WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC FQ Surveillance Technical Specifications. Additionally, the proposed amendment modifies TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR), to include WCAP-17661, Revision 1, in the list of the Nuclear Regulatory Commission (NRC) approved methodologies used to develop the COLR.

Westinghouse Nuclear Safety Advisory Letter (NSAL) 09-5, Relaxed Axial Offset Control FQ Technical Specification Actions, and NSAL-15-1, Heat Flux Hot Channel Factor Technical Specification Surveillance, recommended that conservative interim actions be administratively implemented in accordance with NRC Administrative Letter 98-10, Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety. Administrative controls were implemented at WCGS to address the issues identified in NSAL-09-5 and NSAL-15-1. Therefore, in accordance with the guidance in NRC Administrative Letter 98-10, the proposed amendment addresses the non-conservatisms identified by the NSALs.

Attachment I provides the evaluation of the proposed change. Attachment II provides the existing TS pages marked up to show the proposed change. Attachment III provides revised (clean) TS pages. Attachment IV provides the proposed TS Bases changes for information only.

P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 000269 Page 2 of 3

The changes in this LAR are not required to address an immediate safety concern. WCNOC requests approval of this proposed amendment within 12 months from the date of this submittal.

Once approved, the amendment will be implemented prior to MODE 4 entry from Refueling Outage 27 (Fall 2025).

It has been determined that this amendment application does not involve a significant hazard consideration per 10 CFR 50.92, Issuance of amendment. Pursuant to 10 CFR 51.22, Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review, Section (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of this amendment.

The amendment application was reviewed by the Plant Safety Review Committee. In accordance with 10 CFR 50.91, Notice for public comment; State consultation, Section (b)(1), a copy of this amendment application, with Attachments, is being provided to the designated Kansas State official.

There are no regulatory commitments contained in this submittal. If you have any questions concerning this matter, please contact me at (620) 364-8831 x8687, or Dustin Hamman at (620) 364-4204.

Sincerely,

Michael T. Boyce

MTB/

Attachments: I Evaluation of the Proposed Change II Proposed Technical Specification Changes (Mark-up)

III Revised Technical Specification Pages IV Proposed TS Bases Changes (for information only)

cc: S. S. Lee (NRC), w/a J. Meinholdt (KDHE), w/a J. D. Monninger (NRC), w/a G. E. Werner (NRC), w/a Senior Resident Inspector (NRC), w/a Licensing Correspondence - ET 24-000269, w/a

Attachment I to 000269 Page 1 of 18

EVALUATION OF THE PROPOSED CHANGE

Subject:

License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC FQ Surveillance Technical Specifications 1.0

SUMMARY

DESCRIPTION

2.0 DETAILED DESCRIPTION

2.1 Background

2.2 System Design and Operation

2.3 Current Technical Specification Requirements

2.4 Reason for the Proposed Changes

2.5 Description of the Proposed Changes

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements

4.2 Precedent

4.3 No Significant Hazards Consideration Determination

4.4 Conclusions

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

Attachment I to 000269 Page 2 of 18

1.0

SUMMARY

DESCRIPTION

Wolf Creek Nuclear Operating Corporation (WCNOC) requests an amendment to Renewed Facility Operating License No. NPF-42 to revise the Technical Specifications (TS) for the Wolf Creek Generating Station (WCGS), Unit 1. The proposed amendment modifies the WCGS TS 3.2.1, Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology), to implement the methodology in WCAP-17661-P-A, Revision 1 (Reference 6.1), Improved RAOC and CAOC F Q Surveillance Technical Specifications. Additionally, the proposed amendment modifies TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR), to include WCAP-17661-P-A, Revision 1, in the list of the Nuclear Regulatory Commission (NRC) approved methodologies used to develop the COLR.

2.0 DETAILED DESCRIPTION

2.1 Background

Westinghouse Electric Company LLC (Westinghouse) Nuclear Safety Advisory Letter (NSAL) 09-05, Revision 0, Relaxed Axial Offset Control F Q Technical Specification Actions, (Reference 6.2) notified Westinghouse customers of an issue associated with the Required Actions for Condition B of NUREG-1431 (Reference 6.3) TS 3.2.1B, Heat Flux Hot Channel Factor (FQ(Z) (RAOC-W(Z) Methodology), for plants that have implemented the relaxed axial offset control (RAOC) methodology. In certain situations where transient FQ, FQW(Z), is not within its limit, the existing Required Actions may be insufficient to restore FQW(Z) to within the limit. NSAL 5, Revision 1 (Reference 6.4), provided clarification regarding the applicability of the recommended interim actions to address this issue. On August 7, 2009, administrative controls were established in association with Condition B of TS 3.2.1 to address NSAL- 09-5.

Westinghouse NSAL-15-1, Heat Flux Hot Channel Factor Technical Specification Surveillance, (Reference 6.5), notified Westinghouse customers of an issue associated with TS Surveillance Requirement (SR) 3.2.1.2. Specifically, one aspect of the SR may not be sufficient to assure that the peaking factor assumed in the licensing basis analysis remains valid under all conditions between the instances of performance of SR 3.2.1.2. On May 14, 2015, administrative controls were implemented to address NSAL-15-1.

WCNOC participated in an industry Pressurized Water Reactor Owners Group (PWROG) project to correct the TSs. The PWROG submitted (Reference 6.6) the approved proprietary and non-proprietary version of WCAP-17661, Revision 1, to the Nuclear Regulatory Commission (NRC) with TS corrections and associated TS Bases. The NRC issued a verification letter of approval (Reference 6.7) for WCAP-17661-P-A, Revision 1, specifying acceptability for referencing in licensing applications with limitations.

2.2 System Design and Operation

Heat Flux Hot Channel Factor (FQ(Z))

FQ(Z) is defined as the maximum local fuel rod linear power density divided by the average fuel rod linear power density, assuming nominal fuel pellet and fuel rod dimensions. Therefore, FQ( Z) is a measure of the peak fuel pellet power within the reactor core.

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Reduce THERMAL POWER by a certain amount within 15 minutes after each FQC(Z) determination, and

Reduce both the Power Range Neutron Flux - High and the Overpower T trip setpoints by a certain amount within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each FQC(Z) determination, and

Perform SR 3.2.1.1 prior to increasing THERMAL POWER above the limit in Required Action A.1.

TS 3.2.1 Condition B specifies that when F QW(Z) is not within limit, the Required Action/Completion Time is to reduce AFD limits by a certain amount within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

TS 3.2.1 Condition C specifies that when the Required Action and associated Completion Time is not met, place the plant in at least MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SR 3.2.1.1 and SR 3.2.1.2 verify that FQC(Z) and FQW(Z), respectively, are within limit:

Once after each refueling prior to THERMAL POWER exceeding 75% RTP, and

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding by 10%

RTP, the THERMAL POWER at which FQC(Z) and FQW(Z) were last verified, and

In accordance with the Surveillance Frequency Control Program.

The Surveillances are preceded by a Note stating that during power escalation at the beginning of each cycle, thermal power may be increased until an equilibrium power level has been achieved, at which a power distribution measurement is obtained. SR 3.2.1.2 has another Note directing additional action if the maximum over Z of FQC(Z) divided by K(Z), where K(Z) is the normalized FQ(Z) as a function of core height and provided in the COLR, has increased since the previous FQC(Z) evaluation.

2.4 Reason for the Proposed Changes

As described above in Section 2.1, the NRC staff has approved WCAP-17661-P-A /NP-A, Revision 1 for use with limitations to address the issues associated with TS 3.2.1 described in Westinghouse NSAL- 09-5 and NSAL-15-1. WCNOC is proposing to change WCGS TS 3.2.1 to be consistent with the revised TS 3.2.1B provided in Appendix A of WCAP-17661-P-A, Revision

1. The WCGS TS Bases for TS 3.2.1 will be revised to address the proposed changes to TS 3.2.1 consistent with the TS Bases markups provided in Appendix B of WCAP-17661-P-A, Revision 1. Implementing the changes to TS 3.2.1 consistent with the NRC staff -approved WCAP will provide a series of more restrictive core operating spaces if the LCO is not met and a more clearly defined set of Surveillance Requirements and Required Actions.

Attachment I to 000269 Page 6 of 18

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5HGXFH 3RZHU 5DQJH 1HXWURQ )OX[ +LJK WULS VHWSRLQWV 1% for each 1% FQC(Z) exceeds limit.

To:

Reduce Power Range Neutron Flux - High trip setpoints 1% for each 1% that THERMAL POWER is limited below RTP by Required Action A.1.

Attachment I to 000269 Page 7 of 18

6LPLODUO\\ 5HTXLUHG$FWLRQ$ ZRXOGEHFKDQJHGIURP

5HGXFH2YHUSRZHU T trip setpoints 1% for each 1% FQC(Z) exceeds limit.

To:

Reduce Overpower T trip setpoints 1% for each 1% that THERMAL POWER is limited below RTP by Required Action A.1.

5. Required Action A.4 would be change from:

Perform SR 3.2.1.1.

To:

Perform SR 3.2.1.1 and SR 3.2.1.2.

These changes are evaluated in Section 4.2 of the NRC Final Safety Evaluationincluded in Reference 6.1.

TS 3.2.1 Condition B

6. Existing Required Action B.1 would be deleted and new Required Actions B.1.1, B.1.2, B.2.2, B.2.3, and B.2.4 would be added as follows:

REQUIRED ACTION COMPLETION TIME

B.1.1 Implement a RAOC operating space specified in the COLR that 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months restores FQW(Z) to within its limits.

AND

B.1.2 Perform SR 3.2.1.1 and SR 3.2.1.2 if control rod motion is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months required to comply with the new operating space.

OR

B.2.1 ---------------------------------------NOTE ------------------------------------

Required Action B.2.4 shall be completed whenever Required Action B.2.1 is performed prior to increasing THERMAL POWER above the limit of Required Action B.2.1.

Limit THERMAL POWER to less than RTP and reduce AFD 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after each limits as specified in the COLR. FQW(Z) determination

AND

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above the limit of Required Action B.2.1

These changes are evaluated in Section 4.3 of the NRC Final Safety Evaluation included in Reference 6.1.

Deviation from Appendix A WCAP-17661-P-A TS Markups

The Completion Times for Required Actions B.2.1, B.2.2, and B.2.3 contain a deviation from those contained in Appendix A of WCAP-17661-P-A. The Completion Time for these Required Actions include the phrase after each FQW(Z) determination. This additional phrase has been included to these Completion Times since the THERMAL POWER initially determined by Required Action B.2.1 may be affected by subsequent determinations of FQW(Z) that are not within limit when Required Action B.2.4 is performed and could require additional power reductions within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the subsequent FQW(Z) determination, if necessary, to comply with the decreased THERMAL POWER limit. The addition of the phrase after each FQW(Z) determination to the Completion Times for Required Action B.2.1, B.2.2, and B.2.3 ensures they apply after each subsequent determination FQW(Z) during performance of Required Action B.2.4, similar to the phrase after each FQC(Z) determination that is contained in the Completion Times for Required Actions A.1, A.2, and A.3 associated with FQC(Z). The TS Bases for Required Actions B.2.1, B.2.2, and B.2.3 have been updated to include the reason for the inclusionof the phrase after each FQW(Z) determination.

Attachment I to 000269 Page 9 of 18

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3.0 TECHNICAL EVALUATION

The proposed changes to TS 3.2.1 address the issues described in Section 2.1 by reformulating the transient FQ surveillance and defining new Required A ctions that ensure adequate margin recovery. As part of this reformulation, the FQ surveillance W(Z) factors are redefined to mitigate the sensitivity to differences between the measured and predicted steady-state power shapes.

The new factors, called T(Z) factors, primarily characterize the maximum transient P(Z), that is, the maximum expected values of the normalized core average axial power shape resulting from nonequilibrium operation. With the proposed changes, the radial F XY(Z) peaking factors would be measured and multiplied by the T(Z) factors to obtain the measured F QW(Z), which is the transient FQ(Z). The measured steady-state axial power shape would not be used in the surveillance, nor would the predicted surveillance axial power shape. This proposed change will also improve the accuracy of part-power surveillances since the surveillance axial power shape is not used to determine the measured transient FQ(Z). Use of the surveillance axial power shape in the part-power transient FQ(Z) measurement is a major source of the over-measurement that can lead to anomalous reductions in transient FQ margin for part-power surveillances.

To address the non-conservatism in the current Required Action B.1, the proposed changes would permit multiple RAOC operating spaces to be defined in the COLR. The COLR will include T(Z) functions for each RAOC operating space, which is defined as a unique combination of AFD limits and bank insertion limits. If there is a measured transient F Q violation, then a more restrictive RAOC operating space can be selected from the COLR that provides the required margin for future non-equilibrium operation. This retains the feature of using an AFD reduction to gain margin but in a manner that ensures that appropriate margin is recovered. If none of the RAOC operating spaces included in the COLR provides the required margin, then limits on thermal power and AFD must be implemented. These limits are specified in the COLR. The analysis methods used to determine the T(Z) values and the limits on thermal power and AFD are described in WCAP-17661-P-A, Revision 1.

The existing SR 3.2.1.1 and SR 3.2.1.2 are modified by a Note that could create confusion:

During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution measurement is obtained.

The proposed Amendment would delete the Note in its entirety. The proposed Surveillance Frequency of FQC(Z) and FQW(Z) are unambiguous. It is sufficient to confirm FQC(Z) once prior to exceeding 75% RTP following a refueling. It is sufficient to confirm FQW(Z) once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Attachment I to 000269 Page 11 of 18

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Limitation 1: Use of AXY and AQ

The use of Methods 1 and 2 are acceptable for calculating AXY and AQ when performing RAOC and COAC W(Z) Surveillances, subject to the following limitations:

1. The NRC-approved methods provided in the response to RAI 15.b must be used to perform the surveillance-specific AXY or AQ calculations. Newer methods with similar capabilities may be considered acceptable provided the NRC staff specifically approves them for calculating AXY and AQ factors.

2. The depletion calculation used to determine the numerator and denominator of the AXY or AQ factor must be performed similarly to the original design calculation, as described in the response to RAI 15.c.

3. The use of Method 1 for calculating AQ is only acceptable subject to the constraints discussed in the response to RAI 15.a. The surveillance Axial Offset must be within 1.5-percent of the target AO, and there must be assurance that the limiting FQW(Z) location does not lie within a rodded elevation at the time of surveillance. Note that the use of Method 1 remains acceptable when surveillance-specific W(Z) functions are used.

Attachment I to 000269 Page 13 of 18

WCNOC Response

The TS Bases were revised to limit the methods to calculate AXY to Methods 1 and 2. Method 1 sets AXY(Z) to 1.0. Method 2 calculates AXY(Z) for the conditions existing at the time of the Surveillance. The NRC approved methods provided in the response to Request for Additional Information 15.b are ANC and BEACON, which uses the same neutronic methodology as the design ANC model that was used as the base model for calculating the FQ Surveillance factors.

There are no plans at this time to add an additional method to calculate the AXY(Z) values but doing so would require a revision to the TS, which would require NRC approval.

When BEACON is used to calculate Surveillance condition specific AXY(Z) values, the calculation will be performed without using nodal calibration factors and the core depletion assumptions will be the same as used in the original core model to generate the T(Z) factors.

When ANC is used to calculate the surveillance condition specific AXY(Z) values, the calculation will use the same nuclear model and depletion basis that was used to generate the original T(Z) factors.

Item 3 of the limitation is not applicable because AQ is applicable to the CAOC methodology, whereas WCNOC uses the RAOC methodology.

Limitation 2: Power Level Reduction to 50% RTP

The use of 50% as the final power level reduction in the event of failed FQ surveillance is not included in the TS, but rather in the BASES and in the COLR. As such, this final power level, 50%, must be implemented on a plant-specific basis and included in COLR input generated, using this methodology, in order to use this TR.

WCNOC Response

The TS Bases were revised to use 50% as the final power level reduction in the event of a failed FQ Surveillance. Appendix C of WCAP-17661-P-A, Revision 1, provides sample COLR input for a RAOC plant, which specifies 50% RTP as the final power level reduction in the event of a failed FQ Surveillance. The COLR input for WCGS fuel cycles will also specify 50% RTP as the final power level reduction in the event of a failed FQ Surveillance as part of implementation of the WCAP-17661-P-A, Revision 1, methodology.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements

The proposed change has been evaluated to determine whether the applicable regulations and requirements, noted below, continue to be met.

10 CFR 50.36, Technical Specifications

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensures the operational capability of SSCs that are required to protect the health and safety of the public. The NRC's requirements related

Attachment I to 000269 Page 14 of 18

WR WKH FRQWHQW RI WKH 76V DUH FRQWDLQHG LQ 6HFWLRQ RI 7LWOH RI WKHCode of Federal Regulations (10 CFR 50.36) which requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements per 10 C FR 50.36(c)(3); (4) design features; and (5) administrative controls. The proposed change does not affect WCGSs compliance with the intent of 10 CFR 50.36.

NRC Generic Letter (GL) 88-16, Removal of Cycle-Specific Parameter Limits From Technical Specifications, (Accession No. ML031200485), established the NRC position that licensees could remove cycle-specific values of certain operating limits from the technical specifications and maintain them in a COLR, provided that the following requirements were met.

1. Use NRC-approved methodology to determine the operating limits,

2. Include a list, in the technical specification administrative controls section, of the references used to determine the operating limits, and

3. Maintain the limits in a COLR, which must be submitted to the NRC for information.

The proposed change does not affect WCGSs compliance with the intent of 10 CFR 50.36 and GL 88-16 would be met with NRC approval of the proposed changes and submittal of the COLR in accordance with TS 5.6.5d.

10 CFR 50, Appendix A, General Design Criteria for Nuclear Power Plants

10 CFR 50, Appendix A, General Design Criterion (GDC) 10, Reactor design, states, The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any conditions of normal operation, including the effects of anticipated operational occurrences.

Conformance with GDC 10 is described in Section 3.1.4 of the Wolf Creek Updated Safety Analysis Report (USAR). The proposed change does not affect WCGSs conformance with the intent of GDC 10.

10 CFR 50, Appendix A, GDC 20, Protection system functions, states, The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. Conformance with GDC 20 is described in Section 3.1.5 of the Wolf Creek USAR. The proposed change does not affect WCGSs conformance with the intent of GDC 20.

10 CFR 50, Appendix A, GDC 26, Reactivity control system redundancy and capability, states, Two independent reactivity control systems of different design principles shall be provided. One of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding

Attachment I to 000269 Page 15 of 18

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5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant c hange in the types or significant increase in the amount of effluent that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environment impact statement environmental assessment need be prepared in connection with the proposed amendment.

6.0 REFERENCES

6.1 WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC FQ Surveillance Technical Specifications, dated February 2019. (ADAMS Accession No. ML19225C079)

6.2 Westinghouse Nuclear Safety Advisory Letter (NSAL- 09- 05), Relaxed Axial Offset Control FQ Technical Specification Actions, dated August 4, 2009.

6.3 NUREG-1431, Volume 1, Revision 4.0, Standard Technical Specifications Westinghouse Plants, USNRC, April 2012.

Attachment I to 000269 Page 18 of 18

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Attachment II to 000269 Page 1 of 9

ATTACHMENT II

PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)

mage=O=of=V FQ(Z) (FQ Methodology) (Z) (F=)=)=)=)=)=)=)=)=)Q Methodology) 3.2.1 RAOC - T(Z)

3.2 POW ER DISTRIBUTION LIMITS

3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) (FQ Methodology) (Z)) (F=)=)=)=)=)=)=)=)

LCO 3.2.1 F Q(Z), as approximated by F QC(Z) and F QW (Z), shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. FQC(Z) not within limit. A.1 Reduce THERMAL A. FA. FA. FA. FA. F15 minutes after POW ER 1% RTP for each FQC(Z) each 1% F QC(Z) exceeds determination JJJJJJJJJJJJJJJJJJJJJJJJJklqbJJJJJJJJJJJJJJJJJJJJJJJJJJJ=limit.

oequired=Action=AKQ=shall=be=completed==

whenever=this=Condition=is=entered=prior=to= AND increasing=

required=to=be=performed=if=this=Condition= A.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after is=entered=prior=to=qebojAi=mltbo= Neutron Flux - High trip each FQC(Z)

TRB=oqm=after=a=refuelingK= determination setpoints 1% for each

)1% FQC(Z) exceeds limit. 4=H[FHHGVOLPLW (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. that THERMAL POWER is limited below RTP by AND Required Action A.1.

A.3 Reduce Overpower ' T trip T trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after setpoints 1% for each 1% for each each FQC(Z)

)1% FQC(Z) exceeds limit. 4=H[FHHGVOLPLW (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. (Z) exceeds limit. determination

AND

A.4 Perform SR 3.2.1.1. A.4 Perform SR 3.2.1.1. A.4 Perform SR 3.2.1.1. A.4 Perform SR 3.2.1.1. A.4 Perform SR 3.2.1.1. Prior to increasing THERMAL POW ER above the limit of Required Action A.1

(continued)

W olf Creek - Unit 1 3.2-1 Amendment No. 123, 159, 188, 188 Attachment II to 000269 Page 3 of 9 FQ(Z) (FQ Methodology)=)=)=)=)=)=)=)=)=)0HWKRGRORJ\\

444 3.2.1

RAOC - T(Z)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. FQW(Z) not within limits. B.1 Reduce AFD limits 1%B. F(Z) not within limits. B.1 Reduce AFD limits (Z) not within limits. B.1 Reduce AFD limits KRXUV4 hours

IRUHDFK )for each 1% FQW(Z): =

INSERT 3.2-2 exceeds limit.H[FHHGVOLPLW

C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

ROI&UHHN 8QLW W olf Creek - Unit 1 3.2-2 Amendment No. 123 $PHQGPHQW1R

CONDITION REQUIRED ACTION COMPLETION TIME

INSERT 3.2-2

B. FQW(Z) not within limits.B.1.1 Implement a RAOC 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months operating space specified in the COLR that restores FQW(Z) to within limits.

AND

B.1.2 Perform SR 3.2.1.1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.2.1.2 if control rod motion is required to comply with the new operating space.

OR

B.2.1 ---------------NOTE------------

Required Action B.2.4 shall be completed whenever Required Action B.2.1 is performed prior to increasing THERMAL POWER above the limit of Required Action B.2.1.

Limit THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after to less than RTP and each FQW(Z) reduce AFD limits as determination specified in the COLR.

AND

B.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Neutron Flux - High trip each FQW(Z) setpoints 1% for each determination 1% that THERMAL POWER is limited below RTP by Required Action B.2.1.

AND

(continued)

CONDITION REQUIRED ACTION COMPLETION TIME

INSERT 3.2-2 (continued)

B. (continued)B.2.3 Reduce Overpower T 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after trip setpoints 1% for each FQW(Z) each 1% that THERMAL determination POWER is limited below RTP by Required Action B.2.1.

AND

B.2.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action B.2.1 Attachment II to 000269 Page 6 of 9 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQQ 3.2.1

RAOC-T(Z)

SURVEILLANCE REQUIREMENTS

NOTE ------------------------------------------------------------ NOTE During power escalation following shutdown, THERMAL POWER may be increased until an During power escalation following shutdown, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution equilibrium power level has been achieved, at which a power distribution measurement is measurement is obtained.obtained.

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Ve rify FQC(Z) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP

AND

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQC(Z) was last verified

AND

In accordance with the Surveillance Frequency Control Program

(continued)

Wolf Creek - Unit 1 3.2-3 Amendment No. 123, 188, 227 Attachment II to 000269 Page 7 of 9 FQ(Z) (FQ Methodology) =)=)=)=)0HWKRGRORJ\\0HWKRGRORJ\\0HWKRGRORJ\\

4444 3.2.1

RAOC-T(Z)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.2.1.2 -------------------------------NOTE---------------------------------.2.1.2 -------------------------------NOTE---------------------------------

If FIf FQC(Z) measurements indicate Q(Z) measurements indicate

)FQ4C=(Z) maximum over zmaximum over z K(Z).=.=

has increased since the previous evaluation of KDVLQFUHDVHGVLQFHWKHSUHYLRXVHYDOXDWLRQRI

FQC(Z): )4=

a. Increase F QW (Z) by the appropriate factorD,QFUHDVH)4=E\\WKHDSSURSULDWHIDFWRU specified in the COLR and reverify FQW (Z) isVSHFLILHGLQWKH&2/5DQGUHYHULI\\)4=LV ZLWKLQOLPLWV RUwithin limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD until twoE 5HSHDW65 RQFHSHU ()3'XQWLOWZR VXFFHVVLYHSRZHUGLVWULEXWLRQPHDVXUHPHQWVsuccessive power distribution measurements indicateLQGLFDWH

)FC=(Z)

PD[LPXPRYHU]maximum over z Q4 K(Z).=.=

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER exceeds 75% RTP has not increased. KDVQRWLQFUHDVHG

Verify FQW (Z) is within limit. Once after each 2QFHDIWHUHDFK

UHIXHOLQJSULRUWRUHIXHOLQJSULRUWRUHIXHOLQJSULRUWRUHIXHOLQJSULRUWRUHIXHOLQJSULRUWRUHIXHOLQJSULRUWRrefueling prior to 7+(50$/THERMAL 32: (5POW ER H[FHHGLQJexceeding

57375% RTP

AND (continued)

W olf Creek - Unit 1 3.2-4 Amendment No. 123, 188

Attachment II to 000269 Page 8 of 9 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F QQ 3.2.1

RAOC-T(Z)

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.2.1.2 (continued) Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQW(Z) was last verified

AND

In accordance with the Surveillance Frequency Control Program

Wolf Creek - Unit 1 3.2-5 Amendment No. 123, 227 Attachment II to 000269 Page 9 of 9 Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. W CAP-16009-P-A, Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM).

5. W CAP-16045-P-A, Qualification of the Two -Dimensional Transport Code PARAGON.

6. W CAP-16045-P-A, Addendum 1 -A, Qualification of the NEXUS Nuclear Data Methodology.

7. W CAP 10965 -P-A, ANC: A W estinghouse Advanced Nodal Computer Code.

8. W CAP-12610-P-A, VANTAGE+ Fuel Assembly Reference C ore Report.

9. W CAP-12610-P-A & CENPD -404-P-A, Addendum 1 -A, Optimized TM.

ZIRLO

10. W CAP-8745-P-A, Design Bases for the Thermal Power T and Thermal Overtemperature T Trip Functions.

c. The core operating limits shall be determined such that all applicableThe core operating limits shall be determined such that all limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

&$3 3 $ ,PSURYHG 5$2& DQG &$2& ) 4 6XUYHLOODQFH 7HFKQLFDO 6SHFLILFDWLRQs

(continued)

W olf Creek - Unit 1 5.0-26 Amendment No. 123, 142, 144, 158,

164, 179, 209, 21 3, 216, 221, 216, 221 Attachment III to 000269 Page 1 of 7

ATTACHMENT III

REVISED TECHNICAL SPECIFICATION PAGES

FQ(Z) (RAOC - T(Z) Methodology) 3.2.1

3.2 POWER DISTRIBUTION LIMITS

3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) (RAOC - T(Z) Methodology)

LCO 3.2.1 FQ(Z), as approximated by F QC(Z) and FQW(Z), shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. -------------NOTE--------------A.1 Reduce THERMAL 15 minutes after Required Action A.4 shall POWER 1% RTP for each FQC(Z) be completed whenever each 1% FQC(Z) exceeds determination this Condition is entered limit.

prior to increasing THERMAL POWER above AND the limit of Required Action A.1. SR 3.2.1.2 is not A.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after required to be performed if Neutron Flux - High trip each FQC(Z) this Condition is entered setpoints 1% for each determination prior to THERMAL 1% that THERMAL POWER exceeding 75% POWER is limited below RTP after a refueling. RTP by Required Action

A.1.

FQC(Z) not within limit. AND

A.3 Reduce Overpower T trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after setpoints 1% for each each FQC(Z) 1% that THERMAL determination POWER is limited below RTP by Required Action A.1.

AND

A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A.1 (continued)

Wolf Creek - Unit 1 3.2-1 Amendment No. 123, 159, 188, FQ(Z) (RAOC - T(Z) Methodology) 3.2.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. FQW(Z) not within limits.B.1.1 Implement a RAOC 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months operating space specified in the COLR that restores FQW(Z) to within limits.

AND

B.1.2 Perform SR 3.2.1.1 and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.2.1.2 if control rod motion is required to comply with the new operating space.

OR

B.2.1 ---------------NOTE------------

Required Action B.2.4 shall be completed whenever Required Action B.2.1 is performed prior to increasing THERMAL POWER above the limit of Required Action B.2.1.

Limit THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after to less than RTP and each FQW(Z) reduce AFD limits as determination specified in the COLR.

AND

B.2.2 Reduce Power Range 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after Neutron Flux - High trip each FQW(Z) setpoints 1% for each determination 1% that THERMAL POWER is limited below RTP by Required Action B.2.1.

AND

(continued)

Wolf Creek - Unit 1 3.2-2 Amendment No. 123, FQ(Z) (RAOC - T(Z) Methodology) 3.2.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. (continued) B.2.3 Reduce Overpower T 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after trip setpoints 1% for each FQW(Z) each 1% that THERMAL determination POWER is limited below RTP by Required Action B.2.1.

AND

B.2.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action B.2.1

C. Required Action and C.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Wolf Creek - Unit 1 3.2-3 Amendment No. 123, FQ(Z) (RAOC - T(Z) Methodology) 3.2.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify FQC(Z) is within limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP

AND

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQC(Z) was last verified

AND

In accordance with the Surveillance Frequency Control Program

(continued)

Wolf Creek - Unit 1 3.2-4 Amendment No. 123, 188, 227, FQ(Z) (RAOC - T(Z) Methodology) 3.2.1

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

SR 3.2.1.2 Verify FQW(Z) is within limit. Once after each refueling within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER exceeds 75% RTP

AND

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions after exceeding, by 10% RTP, the THERMAL POWER at which FQW(Z) was last verified

AND

In accordance with the Surveillance Frequency Control Program

Wolf Creek - Unit 1 3.2-5 Amendment No. 123, 188, Reporting Requirements 5.6

5.6 Reporting Requirements

5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. WCAP-16009-P -A, Realistic Large Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM).

5. WCAP-16045-P -A, Qualification of the Two -Dimensional Transport Code PARAGON.

6. WCAP-16045-P -A, Addendum 1-A, Qualification of the NEXUS Nuclear Data Methodology.

7. WCAP 10965 -P-A, ANC: A Westinghouse Advanced Nodal Computer Code.

8. WCAP-12610-P -A, VANTAGE+ Fuel Assembly Reference Core Report.

9. WCAP-12610-P -A & CENPD-404-P-A, Addendum 1-A, TM.

Optimized ZIRLO

10. WCAP-8745-P -A, Design Bases for the Thermal Power T and Thermal Overtemperature T Trip Functions.

11. WCAP-17661-P -A, Improved RAOC and CAOC F Q Surveillance Technical Specifications.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each relo ad cycle to the NRC.

(continued)

Wolf Creek - Unit 1 5.0-26 Amendment No. 123, 142, 144, 158, 164, 179, 209, 213, 216, 221, Attachment IV to 000269 Page 1 of 18

ATTACHMENT IV PROPOSED TS BASES CHANGES (for information only)

Attachment IV to 000269 Page 2 of 18 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQ Methodology)

B 3.2.1

RAOC - T(Z)

B 3.2 POW ER DISTRIBUTION LIMITS

B 3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) (FQ Methodology) (Z)) (F Methodology) Methodology) Methodology) Methodology)

BASES

BACKGROUND The purpose of the limits on the values of F Q(Z) is to limit the local (i.e., pellet) peak power density. The value of FQ(Z) varies along the axial height (Z) of the core.

FQ(Z) is defined as the maximum local fuel rod linear power density divided by the average fuel rod linear power density, assuming nominal fuel pellet and fuel rod dimensions. Therefore, F Q(Z) is a measure of the peak fuel pellet power within the reactor core.

During power operation, the global power distribution is limited by LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)," and LCO 3.2.4, POWER TILT "QUADRANT TILT POW ER RATIO (QPTR)," which are directly and continuously measured process variables. These LCOs, along with LCO 3.1.4, Rod Group Alignment Limits, LCO 3.1.5, Shutdown Bank Insertion Limits, and LCO 3.1.6, "Control Bank Insertion Limits," maintain the core limits on power distributions on a continuous basis.

FQ(Z) varies with fuel loading patterns, control bank insertion, fuel burnup, and changes in axial power distribution.

FQ(Z) is not directly measurable but is inferred from a power distribution WKH HOHYDWLRQ GHSHQGHQW PHDsXUHG measurement obtained with either the movable incore detector system or SODQDU UDGLDO SHDNLQJ IDFWRUs the Power Distribution Monitoring System (PDMS). The results of the

) ;< = DUH LQFUHDsHG E\\ DQ three-dimensional power distribution measurement are analyzed to derive HOHYDWLRQ GHSHQGHQW IDFWRU a measured value for F Q(Z). These measurements are generally taken

[7=] &2/5 WKDW DFFRXQWs IRU WKH with the core at or near equilibrium conditions. Howe ver, because this H[SHFWHG PD[LPXP YDOXHs RI WKH value represents an equilibrium condition, it does not include the WUDQsLHQW D[LDO SRZHU sKDSHs variations in the value of Fvariations in the value of F Q(Z) that are present during nonequilibrium SRsWXODWHG WR RFFXU GXULQJ 5$2& situations, such as load following. situations, such as load following.

RSHUDWLRQ 7KXs [7=] &2/5 DFFRXQWs IRU WKH ZRUsW FDsH QRQ To account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of FTo account for these possible variations, the steady state value of F Q(Z) is Q(Z) is HTXLOLEULXP SRZHU sKDSHs WKDW DUH adjusted by an elevation dependent factor that accounts for the calculated adjusted by an elevation dependent factor that accounts for the calculated H[SHFWHG IRU WKH DssXPHG 5$2& worst case transient conditions. worst case transient conditions.

RSHUDWLQJ sSDFH Core monitoring and control under nonsteady state conditions are accomplished by operating the core within the limits of the appropriate LCOs, including the limits on AFD, QPTR, and control rod insertion.

7KH 5$2& RSHUDWLQJ sSDFH Ls GHILQHd Ds WKH FRPELQDWLRQ RI $)' DQG &RQWURO %DQN,QsHUWLRQ /LPLWs DssXPHG LQ WKH F DOFXODWLRQ RI D SDUWLFXODU [7=] &2/5 IXQFWLRQ 7KH [7=] &2/5 IDFWRUs DUH GLUHFWO\\ GHSHQGHQW RQ WKH $)' DQG &RQWURO %DQN

,QsHUWLRQ /LPLW DssXPSWLRQs 7KH &2/5 PD\\ F RQWDLQ GLIIHUHQW [7=] &2/5 IXQFWLRQs WKDW UHIOHFW GLIIHUHQW RSHUDWLQJ sSDFH DssXPSWLRQs,I WKH OLPLW RQ ) 4 = Ls H[FHHGHG D PRUH UHsWULFWLYH RSHUDWLQJ sSDFH PD\\ EH LPSOHPHQWHG WR JDLQ PDUJLQ IRU IXWXUH QRQ HTXLOEULXP RSHUDWLRQ

W olf Creek - Unit 1 B 3.2.1-1 Revision 48 Attachment IV to 000269 Page 3 of 18 FQ(Z) (FQ Methodology)(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQQ B 3.2.1

RAOC - T(Z)

BASES

APPLICABLE This LCO precludes core power distributions that violate the following fuel SAFETY ANALYSES design criteria:

a. During a large break loss of coolant accident (LOCA), the peak cladding temperature must not exceed 2200° F (Ref. 1);

b. During a loss of forced reactor coolant flow accident, there must be at least 95% probability at the 95% confidence level (the 95/95 DNB criterion) that the hot fuel rod in the core does not experience a departure from nucleate boiling (DNB) condition;

c. During an ejected rod accident, the average fuel pellet enthalpy at the hot spot in irradiated fuel must not exceed 200 cal/gm (Ref. 2);

and

d. The control rods must be capable of shutting down the reactor with a minimum required SDM with the highest worth control rod stuck fully withdrawn (Ref. 3).

Limits on FQ(Z) ensure that the value of the initial total peaking factor assumed in the accident analyses remains valid. Other criteria must also be met (e.g., maximum cladding oxidation, maximum hydrogen generation, coolable geometry, and long term cooling). However, the LOCA peak cladding temperature is typically most limiting.

FQ(Z) limits assumed in the LOCA analysis are typically limiting relative to (i.e., lower than) the FQ(Z) limit assumed in safety analyses for other postulated accidents. Therefore, this LCO provides conservative limits for other postulated accidents.

FQ(Z) satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

LCO The Heat Flux Hot Channel Factor, FQ(Z), shall be limited by the following relationships:

F () Z CFQ K ()Z for P > 0.5 Q

P F () Z CFQ () 0.5 ZK for P Q

0.5 where

CFQ = FQRTP is the FQ(Z) limit at RTP provided in the COLR,

Wolf Creek - Unit 1 B 3.2.1-2 Revision 0 Attachment IV to 000269 Page 4 of 18 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F Methodology)

QQ B 3.2.1

limit RAOC - T(Z)

BASES

LCO K(Z) is the normalized F Q(Z) as a function of core height provided in the (Z) as a function of core height provided in the (Z) as a function of core height provided in the (Z) as a function of core height provided in the (Z) as a function of core height provided in the (continued) COLR, and

P= THERMAL POWER RTP

The actual values of CFQ and K(Z) are given in the COLR.

For Relaxed Axial Offset Control operation, F Q(Z) is approximated by FQC(Z) and F QW (Z). Thus, both FQC(Z) and F QW (Z) must meet the preceding limits on FQ(Z).

An FQC(Z) evaluation requires obtaining a power distribution measurement in MODE 1, from which we obtain the measured value (F QM(Z)) of FQ(Z).

If the power distribution measurement is obtained with the movable incore detector system,

FQC(Z) = FQM(Z) (1.03) (1.05) = FQM(Z) (1.0815) (Eq. 1) (Z) (1.0815) (Eq. 1)

where 1.03 is a factor that accounts for fuel manufacturing tolerances and 1.05 is a factor that accounts for flux map measurement uncertainty.

(Ref. 4)

If the power distribution measurement is obtained with the Power Distribution Monitoring System,

FQC(Z) = FQM(Z) (1.03) (1.00 + UQ/100)

where 1.03 is a factor that accounts for fuel manufacturing tolerances and UQ is a factor that accounts for Power Distribution Monitoring System measurement uncertainty (%), determined as described in Reference 6.

FQC(Z) is an excellent approximation for FQ(Z) when the reactor is at the steady state power at which the power distribution measurement was taken.

) ;< 0 =[7=] &2/5 $ ;< =5M[ ]for P > 0.5 The expression for F QW (Z) is: 3 FQW(Z) = FXYM(Z) [T(Z)]COLR AXY(Z) Rj [1.0815] for P 0.5 FQW (Z) = FQC(Z) W (Z) (Z) = FQ(Z) W (Z) P 0.5

INSERT B 3.2.1-3 where FQC(Z) is per Eq. 1 and W (Z) is a cycle dependent function that where Fwhere Fwhere Fwhere Fwhere FQ(Z) is per Eq. 1 and W (Z) is a cycle dependent function that accounts for power distribution transients encountered during normal accounts for power distribution transients encountered during normal operation. W (Z) information is included in the COLR. For the PDMS, operation. W (Z) information is included in the COLR. For the PDMS, FQM(Z) reflects the measured power distribution at HFP, ARO, equilibrium FQ(Z) reflects the measured power distribution at HFP, ARO, equilibrium Xe conditions.Xe conditions.

W olf Creek - Unit 1 B 3.2.1-3 Revision 48 INSERT B 3.2.1-3

The various factors in this expression are defined below:

FXYM(Z) is the measured radial peaking factor at axial location Z and is equal to the value of FQM(Z)/PM(Z), where PM(Z) is the measured core average axial power shape.

[T(Z)]COLR is the cycle and burnup dependent function, specified in the COLR, which accounts for power distribution transients encountered during non-e quilibrium normal operation.

[T(Z)] COLR functions are specified for each analyzed RAOC operating space (i.e., each unique combination of AFD l imits and Control Bank Insertion Limits). The [T(Z)]COLR functions account for the limiting non-e quilibrium axial power shapes postulated to occur during normal operation for each RAOC operating space. Limiting power shapes at both full and reduced power operation are considered in determining the max imum values of [T(Z)] COLR. The [T(Z)]COLR functions also account for the following effects: (1) the presence of spacer grids in the fuel assembly, (2) the increase in radial peaking in rodded core planes due to the presence of control r ods during non-e quilibrium normal operation, (3) the increase in radial peaking that occurs during part-p ower operation due to reduced fuel and moderator temperatures, and (4) the increase in radial peaking due to non-e quilibrium xenon effects. The [T(Z)] COLR functions are normally calculated assuming that the Surveillance is performed at nominal RTP conditions with all shutdown and control rods full withdrawn, i.e., all rods out (ARO) Surveillance specific

[T(Z)] COLR values may be generated for a given surveillance core condition.

P i s the THERMAL POWER / RTP.

AXY(Z) is a function that adjusts the FQW(Z) Surveillance for differences between the reference core condition assumed in generating the [T(Z)] COLR function and the actual core condition that exists w hen the Surveillance is performed. Normally, this r eference core condition is 100%

RTP, all rods out, and equilibrium x enon. For s implicity, AXY(Z) m ay be assumed to be 1.0, as this w ill typically r esult in an accurate FQW(Z) S urveillance result for a Surveillance that is performed at or near the reference core condition, and an underestimation of the available margin to the FQ limit for S urveillances that are performed at core conditions di fferent fr om the reference condition. Alternately, the AXY(Z) func tion may be calculated using the NRC approved methodology i n Reference 7.

1.0815 is a factor that accounts for fu el m anufacturing tolerances and measurement uncertainty.

Rj is a cycle and burnup dependent analytical factor specified in the COLR that accounts for potential increases in FQW(Z) between Surveillances. Rj values are provided for each RAOC operating space.

Attachment IV to 000269 Page 6 of 18 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQQ 9 LRODWLQJ WKH /&2 OLPLWs IRU ) 4 = FRXOG UHsXOW LQ XQDFFHSWDEOHB 3.2.1 F RQsHTXHQFHs LI D GHsLJQ EDsLs HYHQW ZHUH WR RFFXU ZKLOH RAOC - T(Z)

BASES ) 4 = H[FHHGs LWs sSHFLILHG OLPLWs

LCO T FQ(Z) lihe mits define limiting values for core power peaking thatmits define limiting values for (continued) precludes peak cladding temperatures above 2200 qF during eitherprecludes peak cladding temperatures above 2200 a large or small break LOCA.eak LOCA.

, a more restrictive RAOC This LCO requires operation within the bounds assumed in the safetyLCO requires operation within the bounds assumed in the safetyLCO requires operation within the bounds assumed in the safety operating space must be implemented or core power analyses. Calculations are performed in the core design process to Calculations are performed in the core design process to Calculations are performed in the core design process to Calculations are performed in the core design process to Calculations are performed in the core design process to Calculations are performed in the core design process to limits and AFD limits must confirm that t he core can be controlled in such a manner during operation be reduced. that i t can stay w ithin the LOCA F Q(Z) limits. If ) 4 : = cannot be maintained within the LCO limits, r eduction of the core power i s required. equired.

Violating the LCO limits for FQ(Z) mayViolating the LCO limits forViolating the LCO limits forViolating the LCO limits for F FQ(Z) may p r oduce unacceptable p roduce unacceptable consequences ifconsequences ifconsequences ifconsequences if a design basis event occurs while FQ(Z) is outside its a a design basis event occurs while FQ(Z) is outside its specifiedspecified limits. limits

APPLICABILITY The F Q(Z) limits must be maintained in MODE 1 to prevent core power distributions from exceeding the limits assumed in the safety analyses.

Applicability in other MODES is not required because ther e is either insufficient stored energy in the fuel or insufficient energy being transferred to the reactor coolant to require a limit on the distribution of core power.

ACTIONS A.1

Reducing THERMAL POW ER by 1% RTP for each 1% by which F QC(Z) exceeds its limit, maintains an acceptable absolute power density. FQC(Z) is FQM(Z) multiplied by factors which account for manufacturing tolerances and measurement uncertainties. F QM(Z) is the measured value of FQ(Z).

The Completion Time of 15 minutes provides an acceptable time to reduce power in an orderly manner and without allowing the plant to remain in an unacceptable condition for an extended period of time. The maximum allowable power level initially determined by Required Action A.1 may be affected by subsequent determinations of F QC(Z) and would require power reductions within 15 minutes of the F QC(Z) determination, if necessary to comply with the decreased maximum allowable power level.

Decreases in F QC(Z) would allow increasing the maximum allowable power level and increasing power up to this revised limit.

Calculate the percent FCalculate the percent F QC(Z) exceeds its limit by the following expression: Q(Z) exceeds its limit by the following expression:

INSERT B 3.2.1-4 FZFZFZFZC ()()

maximum QQ over Z CFQCFQ1 X 100 for P 0.5

()Z P XK

W olf Creek - Unit 1 B 3.2.1-4 Revision 48 INSERT B 3.2.1-4

If an FQ surveillance is performed at 100% RTP conditions, and both FQC(Z) and FQW(Z) exceed their limits, the option to reduce the THERMAL POWER limit in accordance with Required Action B.2.1 instead of implementing a new oper ating space in accordance with Required Action B.1.1, will result in a further power reduction after Required Action A.1 has been completed. However, this further power reduction would be permitted to occur over the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . In the event the evaluated THERMAL POWER reduction in the COLR for Required Action B.2.1 did not result in a further power reduction (for example, if both Condition A and Condition B were entered at less than 100% RTP conditions), then the THERMAL POWER level es tablished as a result of completing Required Action A.1 will take precedence, and will establish the effective op erating power l evel limit for the unit until both Conditions A and B are exited.

Attachment IV to 000269 Page 8 of 18 FQ(Z) (FQ Methodology) =)=)=)=)44440HWKRGRORJ\\

B 3.2.1

RAOC - T(Z)

BASES

ACTIONS A.1 (continued)

FZFZC ()

maximum QQ 1 X 100 for P < 0.5 over Z CFQCFQ 0.5 XK()Z

A.2

A reduction of the Power Range Neutron Flux - High trip setpoints by 1%

IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)IRUHDFK E\\ZKLFK)for each 1% by which F QC(Z) exceeds its limit, is a conservative action for 4=H[FHHGVLWVOLPLW LVDFRQVHUYDWLYHDFWLRQIRU

protection against the consequences of severe transients with unanalyzed SURWHFWLRQDJDLQVWWKHFRQVHTXHQFHVRIVHYHUHWUDQVLHQWVZLWKXQDQDO\\]HGSURWHFWLRQDJDLQVWWKHFRQVHTXHQFHVRIVHYHUHWUDQVLHQWVZLWKXQDQDO\\]HG

power distributions. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is sufficient SRZHUGLVWULEXWLRQV 7KH&RPSOHWLRQ7LPHRI KRXUVLVVXIILFLHQW

considering the small likelihood of a severe transient in this time period FRQVLGHULQJWKHVPDOOOLNHOLKRRGRIDVHYHUHWUDQVLHQWLQWKLVWLPHSHULRG

and the preceding prompt reduction in THERMAL POW ER in accordance with Required Action A.1. The maximum allowable Power Range Neutron that THERMAL POWER is limited Flux - High trip setpoints initially determined by Required Action A.2 may below RTP by Required Action A.1 be affected by subsequent determinations of F QC(Z) and would require Power Range Neutron Flux - High trip setpoint reductions within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of FQC(Z) determination, if necessary to comply with the decreased maximum allowable Power Range Neutron Flux - High trip setpoints.

A.3

Reduction in the Overpower T trip setpoints by 1% for each 1% by IRUHDFK E\\

which FQC(Z) exceeds its limit, is a conservative action for protection ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)ZKLFK)4=H[FHHGVLWVOLPLW LVDFRQVHUYDWLYHDFWLRQIRUSURWHFWLRQ

against the consequences of severe transients with unanalyzed power distributions. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is sufficient considering the small likelihood of a severe transient in this time period, and the preceding prompt reduction in THERMAL POW ER in accordance with Required Action A.1. The maximum allowable Overpower T trip setpoints initially determined by Required Action A.3 may be affected by subsequent determinations of F QC(Z) and would require Overpower T trip setpoint reductions within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the FQC(Z) determination, if necessary to comply with the decreased maximum allowable Overpower T trip setpoints. Decreases in F QC(Z) would allow increasing the maximum Overpower T trip setpoints.

A.4 and SR 3.2.1.2

Verification that F QC(Z) has been restored to within its limit, by performing FDWLRQWKDW)FDWLRQWKDW)

SR 3.2.1.1 prior to increasing THERMAL POW ER above the limit 65 SULRUWRLQFUHDVLQJ7+(50$/32: (5DERYHWKHOLPLW65 SULRUWRLQFUHDVLQJ7+(50$/32: (5DERYHWKHOLPLW65 SULRUWRLQFUHDVLQJ7+(50$/32: (5DERYHWKHOLPLW65 SULRUWRLQFUHDVLQJ7+(50$/32: (5DERYHWKHOLPLW65 SULRUWRLQFUHDVLQJ7+(50$/32: (5DERYHWKHOLPLW

W olf Creek - Unit 1 B 3.2.1-5 Revision 48 Attachment IV to 000269 Page 9 of 18 FQ(Z) (FQ Methodology) (Z) (FQ44444 Methodology) 0HWKRGRORJ\\

B 3.2.1

RAOC - T(Z)

BASES ACTIONS A. 4 (continued)and future operation

imposed by Required Action A.1, ensures that core conditions during LPSRVHGE\\5HTXLUHG$FWLRQ$ HQVXUHVWKDWFRUHFRQGLWLRQVGXULQJLPSRVHGE\\5HTXLUHG$FWLRQ$ HQVXUHVWKDWFRUHFRQGLWLRQVGXULQJLPSRVHGE\\5HTXLUHG$FWLRQ$ HQVXUHVWKDWFRUHFRQGLWLRQVGXULQJ

operation at higher power levels are consistent with safety analyses RSHUDWLRQDWKLJKHUSRZHUOHYHOVDUHFRQVLVWHQWZLWKVDIHW\\DQDO\\VHVRSHUDWLRQDWKLJKHUSRZHUOHYHOVDUHFRQVLVWHQWZLWKVDIHW\\DQDO\\VHVRSHUDWLRQDWKLJKHUSRZHUOHYHOVDUHFRQVLVWHQWZLWKVDIHW\\DQDO\\VHVRSHUDWLRQDWKLJKHUSRZHUOHYHOVDUHFRQVLVWHQWZLWKVDIHW\\DQDO\\VHVRSHUDWLRQDWKLJKHUSRZHUOHYHOVDUHFRQVLVWHQWZLWKVDIHW\\DQDO\\VHV

assumptions. Inherent in this action is identification of the cause of the INSERT B 3.2.1-6A out of limit condition and the correction of the cause to the extent necessary to allow safe operation at the higher power level.

B.1% B.1.1

If it is found that the maximum calculated value of F Q(Z) that can occur during normal maneuvers, F QW (Z), exceeds its specified limits, there exists a potential for F QC(Z) to become excessively high if a normal operational transient occurs. Tightening both the positive and negative AFD limits by WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\WUDQVLHQWRFFXUV 7LJKWHQLQJERWKWKHSRVLWLYHDQGQHJDWLYH$)'OLPLWVE\\

1% for each 1% by which F QW (Z) exceeds its limit within the allowed IRUHDFK E\\ZKLFK) IRUHDFK E\\ZKLFK) IRUHDFK E\\ZKLFK) IRUHDFK E\\ZKLFK) IRUHDFK E\\ZKLFK)4=H[FHHGVLWVOLPLWZLWKLQWKHDOORZHG

INSERT B 3.2.1-6B Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , restricts the axial flux distribution such that &RPSOHWLRQ7LPHRI KRXUV UHVWULFWVWKHD[LDOIOX[GLVWULEXWLRQVXFKWKDW&RPSOHWLRQ7LPHRI KRXUV UHVWULFWVWKHD[LDOIOX[GLVWULEXWLRQVXFKWKDW

even if a transient occurred, core peaking factors are not exceeded. HYHQLIDWUDQVLHQWRFFXUUHG FRUHSHDNLQJIDFWRUVDUHQRWH[FHHGHG

Calculate the percent F QW (Z) exceeds its limit by the following expression: &DOFXODWHWKHSHUFHQW)4=H[FHHGVLWVOLPLWE\\WKHIROORZLQJH[SUHVVLRQ

maximum FZ ZFZ ZFZ ZFZ ZFZ ZFZ ZFZ ZFZ ZCCC () ()() ()() ()() ()() ()XWXWXWXWXWXWXW Q 1 X 100 for P 0.5 over Z CFQCFQ

()Z P XK

FZ ZFZ ZFZ ZFZ ZC () ()() ()() ()XW maximum Q 1 X 100 for P < 0.5 over Z CFQCFQ 0.5 XK()Z

B.1.1 through B.2.4 C.1

If Required Actions A.1 through A.4 or B.1 are not met within their 5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU5HTXLUHG$FWLRQV$ WKURXJK$ RU% DUHQRWPHWZLWKLQWKHLU

associated Completion Times, the plant must be placed in a mode or condition in which the LCO requirements are not applicable. This is done by placing the plant in at least MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

This allowed Completion Time is reasonable based on operating experience regarding the amount of time it takes to reach MODE 2 from full power operation in an orderly manner and without challenging plant systems.

W olf Creek - Unit 1 B 3.2.1-6 Revision 48 INSERT B 3.2.1-6A

Condition A i s m odified by a Note that requires Required Action A.4 to be performed whenever the Condition is enter ed prior to increasing THERMAL POWER abov e the limit of Required Action A.1. The Note also states t hat SR 3.2.1.2 is not required to be performed if this Condition is entered prior to THERMAL POWER exceeding 75% R TP after a refueling. This ensures that S R 3.2.1.1 and SR 3.2.1.2 (if required) w ill be performed prior to increasing THERMAL POWER abov e the limit of Required Action A.1, even when Condition A i s ex ited prior to performing Required Action A.4. Performance of SR 3.2.1.1 and SR 3.2.1.2 are necessary t o assure FQ(Z) i s pr operly ev aluated prior to increasing THERMAL POWER.

INSERT B 3.2.1-6B

Implementing a more restrictive RAOC operating space, as specified i n the COLR, within the allowed Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months will r estrict the AFD s uch that peaking factor l imits w ill not be exceeded during non-e quilibrium normal operation. Several RAOC operating spaces, representing successively smaller AFD envelopes and, optionally, shallower Control Bank Insertion Limits, may be specified in the COLR. The corresponding T(Z) func tions f or thes e operating spaces can be used to determine which RAOC operating space will result in acceptable non-e quilibrium oper ation within the FQW(Z) limit.

B.1.2

If it is foun d that the m aximum c alculated value of FQ(Z) that can occur d uring normal maneuvers, FQW(Z), exceeds i ts specified limits, there exists a potential for F QC(Z) to become excessively high if a normal oper ational tr ansient oc curs. As discussed above, Required Action B.1.1 requires that a new R AOC op erating space be implemented to restore FQW(Z) t o within its limits. Required Action B.1.2 requires that SR 3.2.1.1 and SR 3.2.1.2 be performed if control rod motion occurs as a result of implementing the new RAOC operating space in accordance with Required Action B.1.1. The performance of SR 3.2.1.1 and SR 3.2.1.2 is necessary to assure F Q(Z) is properly evaluated after any rod motion resulting from the implementation of a new RAOC operating space in accordance with Required Action B.1.1.

B.2.1

When FQW(Z) exceeds it limit, Required Action B.2.1 may be implemented instead of Required Action B.1. Required Action B.2.1 limits TH ERMAL POWER to less than RTP by the amount specified i n the COLR. It al so requires reductions i n the AFD l imits by the amount specified in the COLR. This maintains an acceptable absolute power dens ity r elative to the maximum power density v alue assumed in the safety anal yses.

If the required FQW(Z) m argin improvement exceeds the margin improvement available from the pre-analyzed THERMAL POWER a nd AFD r eductions provided in the COLR, then THERMAL POWER m ust be further r educed to less than or equal to 50% R TP. In this c ase, reducing THERMAL POWER to less than or equal to 50% R TP w ill provide additional m argin in the transient FQ by the required change in THERMAL POWER a nd the increase in the FQ limit. This will ensure that the FQ limit is m et during transient operation that may oc cur at or below 50%

RTP.

INSERT B 3.2.1-6B (continued)

The Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provides an acceptable time to reduce the THERMAL POWER and AFD l imits i n an orderly m anner to preclude entering an u nacceptable condition during future non-e quilibrium o peration. The limit on THERMAL POWER i nitially determined by Required Action B.2.1 may be affected by s ubsequent determinations of F QW(Z) that are not within limit and could require power reductions w ithin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the of the subsequent FQW(Z) determination, if necessary, to comply w ith the decreased THERMAL POWER l imit. In short, the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C ompletion Time for R equired Action B.2.1 applies after eac h FQW(Z) determination.

Decreases i n subsequent FQW(Z) m easurements while in Conditi on B w ould allow increasing the THERMAL POWER l imit and increasing THERMAL POWER up to this re vised l imit.

Required Action B.2.1 is modified by a Note that states R equired Action B.2.4 shall be completed whenever Required Action B.2.1 is p erformed prior to increasing THERMAL POWER above the limit of Required Action B.2.1. Required Action B.2.4 requires the performance of SR 3.2.1.1 and SR 3.2.1.2 prior to increasing THERMAL POWER abov e the limit established by Required Action B.2.1. The Note ensures that the SRs w ill be performed even if Condition B may be exited prior to performing Required Action B.2.4. The performance of SR 3.2.1.1 and SR 3.2.1.2 is nec essary to ensure FQ(Z) is pr operly ev aluated prior to increasing THERMAL POWER.

If an FQ surveillance is performed at 100% RTP conditions, and both FQC(Z) and FQW(Z) exceed their limits, the option to reduce the THERMAL POWER limit in accordance with Required Action B.2.1 instead of implementing a new operating space in accordance with Required Action B.1, will r esult in a further power reduction after Required Action A.1 has been completed. However, this further power reduction would be permitted to occur over the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . In the event the evaluated THERMAL POWER reduction in the COLR for Required Action B.2.1 did not result in a further power reduction (for example, if both Condition A and Condition B were entered at less than 100% RTP conditions), then the THE RMAL POWER level es tablished as a result of completing Required Action A.1 will take precedence, and will establish the effective operating power level limit for the unit until both Conditions A and B are exited.

B.2.2

A reduction of the Power R ange Neutron Flux - High trip setpoints by 1% for each 1% by which the maximum al lowable power i s re duced is a conservative action for pr otection against the consequences of severe transients with unanalyzed power di stributions. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months i s s ufficient considering the small likelihood of a severe transient in this ti me period and the preceding prompt reduction in the THERMAL POWER l imit and AFD l imits i n accordance with Required Action B.2.1. The maximum al lowable Power R ange Neutron Flux -

High trip setpoints i nitially determined by R equired Action B.2.2 may be affected by subsequent determinations of FQW(Z) that are not w ithin limit and could require Power Range Neutron Flux -

High trip setpoint reductions within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the subsequent FQW(Z) de termination, if necessary, to comply w ith the decreased maximum al lowable Power Range Neutron Flux - High trip setpoints. In short, the 72-h our C ompletion Time for R equired Action B.2.2 applies after each FQW(Z) deter mination.

INSERT B 3.2.1-6B (continued)

B.2.3

Reduction in the Overpower T trip setpoints value of K 4 by 1% for each 1% by w hich the maximum al lowable power i s r educed is a conservative action for protection against the consequences of severe transients with unanalyzed power distributions. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months i s s ufficient considering the small likelihood of a severe transient in this time period, and the preceding prompt reduction in the THERMAL POWER l imit and AFD l imits i n accordance with the Required Action B.2.1. The maximum allowable Overpower T trip setpoints initially determined by R equired Action B.2.3 may be affected by s ubsequent determinations of FQW(Z) that are not within limit and could require Overpower T trip setpoint reductions within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the subsequent FQW(Z) deter mination, if necessary, to comply with the decreased maximum allowable Overpower T trip setpoints. In short, the 72 h our Completion Time for R equired Action B.2.3 applies after eac h FQW(Z) det ermination. Decreases in s ubsequent FQW(Z) m easurements while in Condition B would allow i ncreasing the maximum allowable Overpower T trip setpoints.

B.2.4

Verification that FQW(Z) has been restored to within its limit, by performing SR 3.2.1.1 and SR 3.2.1.2 prior to increasing THERMAL POWER above the maximum al lowable power l imit imposed by Required Action B.2.1, ensures that core conditions during operation at higher power levels and futu re operation are consistent w ith safety analyses as sumptions.

Attachment IV to 000269 Page 13 of 18 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQQ Methodology)

B 3.2.1

RAOC - T(Z)

BASES

SURVEILLANCE SR 3.2.1.1 and SR 3.2.1.2 are modified by a Note. The Note applies SURVEILLANCE SR 3.2.1.1 and SR 3.2.1.2 are modified by a Note. The Note applies REQUIREMENTS during power ascensions following a plant shutdown (leaving MODE 1). REQUIREMENTS during power ascensions following a plant shutdown (leaving MODE 1). REQUIREMENTS during power ascensions following a plant shutdown (leaving MODE 1).

The Note allows for power ascensions if the surveillances are not current. The Note allows for power ascensions if the surveillances are not current. The Note allows for power ascensions if the surveillances are not current.

It states that THERMAL POW ER may be increased until an equilibrium It states that THERMAL POW ER may be increased until an equilibrium It states that THERMAL POW ER may be increased until an equilibrium power level (i.e., equilibrium conditions) has been achieved at which a power level (i.e., equilibachieved at which a power distribution measurement can be obtained. This allowance is power distribution measurement can be obtained. This allowance is power distribution measurement can be obtained. This allowance is modified,however, by one of the Frequency conditions that requires modified,however, by one of the Frequency conditions that requires modified,however, by one of the Frequency conditions that requires verification that FQC(Z) and F QW (Z) are within their specified limits after a C(Z) and F(Z) are within their specified limits after a power rise of more than 10% RTP over the THERMAL POW ER at which power rise of more than 10% RTP over the THERMAL POW ER at which power rise of more than 10% RTP over the THERMAL POW ER at which they were last verified to be within specified limits. Because F QC(Z) and they were last verified to be within specified limits. Because Fthey were last verified to be within specified limits. Because F FQW (Z) could not have previously been measured in a reload core, there is (Z) could not have previously been measured in a reload core, there is (Z) could not have previously been measured in a reload core, there is a second Frequency condition, applicable only for reload cores, that a second Frequency condition, applicable only for reload cores, that a second Frequency condition, applicable only for reload cores, that requires determination of these parameters before exceeding 75% RTP. requires determination of these parameters before exceeding 75% RTP. requires determination of these parameters before exceeding 75% RTP.

This ensures that some determination of F QC(Z) and F QW (Z) are made at a This ensures that some determination of FThis ensures that some determination of F lower power level at which adequate margin is available before going to lower power level at which adequate margin is available before going to lower power level at which adequate margin is available before going to 100% RTP. Also, this Frequency condition, together with the Frequency 100% RTP. Also, this Frequency condition, together with the Frequency 100% RTP. Also, this Frequency condition, together with the Frequency condition requiring verification of F QC(Z) and F QW (Z) following a power condition requiring verification of F(Z) and F increase of more than 10%, ensures that they are verified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months increase of more than 10%, ensures that they are verified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months increase of more than 10%, ensures that they are verified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from when equilibrium conditions are acfrom when equilibrium conditions are ac hieved at RTP (or any other level hieved at RTP (or any other level for extended operati on). Equilibrium conditions are achieved when the on). Equilibrium conditions are achieved when the core is sufficiently stable at the intended operating conditions to perform a core is sufficiently stable at the intended operating conditions to perform a core is sufficiently stable at the intended operating conditions to perform a power distribution measurement. In the absence of these Frequency power distribution measurement. In the absence of these Frequency power distribution measurement. In the absence of these Frequency conditions, it is possible to increase power to RTP and operate for conditions, it is possible to increase power to RTP and operate for conditions, it is possible to increase power to RTP and operate for 31 days without verification of F QC(Z) and F QW (Z). The Frequency 31 days without verification of F(Z). The Frequency condition is not intended to require verification of these parameters after condition is not intended to require verification of these parameters after condition is not intended to require verification of these parameters after every 10% increase in power level above the last verification. It only every 10% increase in power level above the last verification. It only every 10% increase in power level above the last verification. It only requires verification after a power level is achieved for extended operation requires verification after a power level is achieved for extended operation requires verification after a power level is achieved for extended operation that is 10% higher than that power at which Fthat is 10% higher than that power at which F Q was last measured.

SR 3.2.1.1

Verification that F QC(Z) is within its specified limits involves increasing FQM(Z) to allow for manufacturing tolerance and measurement uncertainties in order to obtain F QC(Z), as described in the preceeding LCO section.

The limit with which FQC(Z) is compared varies inversely with power above 50% RTP and directly with a function called K(Z) provided in the COLR.

Performing this Surveillance in MODE 1 prior to exceeding 75% RTP ensures that the F QC(Z) limit is met when RTP is achieved, because ensures that the Fensures that the Fensures that the Fensures that the Fensures that the Fensures that the Fensures that the FQ(Z) limit is met when RTP is achieved, because peaking factors generally decrease as power level is increased. peaking factors generally decrease as power level is increased. peaking factors generally decrease as power level is increased. peaking factors generally decrease as power level is increased. peaking factors generally decrease as power level is increased.

following a refueling

sRPH GHWHUPLQDWLRQ RI ) 4 & = Ls PDGH SULRU WR DFKLHYLQJ D sLJQLILFDQW SRZHU OHYHO ZKHUH WKH SHDN OLQHDU KHDW UDWH FRXOG DSSURDFK WKH OLPLWs DssXPHG LQ WKH sDIHW\\ DQDO\\ sHs

W olf Creek - Unit 1 B 3.2.1-7 Revision 48 Attachment IV to 000269 FQ(Z) (FQ Methodology) (Z) (F(Z) (F(Z) (F(Z) (F(Z) (F(Z) (FQQQQQ Page 14 of 18 B 3.2.1

RAOC - T(Z)

BASES SURVEILLANCE SR 3.2.1.1 (continued) initial or most recent REQUIREMENTS If THERMAL POWER has been increased by 10% RTP since the last RTP since the last RTP since the last RTP since the last RTP since the last RTP since the last RTP since the last determination of FQC(Z), another evaluation of this factor is required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions at this higher power level (to ensure that FQC(Z) values are being reduced sufficiently with power increase to stay within the LCO limits). INSERT B 3.2.1-8A

The Surveillance Frequency is controlled under the Surveillance Frequency Control Progr am.

SR 3.2.1.2

The nuclear design process includes calculations performed to determine that the core can be operated within the F Q(Z) limits. Because power distribution measurements are taken at or near equilibrium conditions, the variations in power distribution resulting from normal operational maneuvers are not present in the measurements. These variations are, however, conservatively calculated by considering a wide range of unit maneuvers in normal operation. The maximum peaking factor increase maneuvers in normal operation. The maximum peaking factor increase over steady state values, calculated as a function of core elevation, Z, is over steady state values, calculated as a function of core elevation, Z, is INSERT B 3.2.1-8B called W(Z). Multiplying the measured total peaking factor, Fcalled W(Z). Multiplying the measured total peaking factor, F QC(Z), by Q(Z), by W(Z) gives the maximum FQ(Z) calculated to occur in normal operation, W(Z) gives the maximum F(Z) calculated to occur in normal operation, FFQW(Z). QW(Z). above 50% RTP

The limit with which FQW(Z) is compared varies inversely with power and directly with the function K(Z) provided in the COLR. directly with the function K(Z) provided in the COLR.7KH [7=] &2/5 IXQFWLRQs DUH sSHFLILHG LQ WKH &2/5 The W(Z) are provided for discrete core elevations. Flux map data are The W(Z) are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are are provided for discrete core elevations. Flux map data are typically taken for 30 to 75core elevations. F QW(Z) evaluations are not applicable for the following axial core regions, measured in percent of applicable for the following axial core regions, measured in percent of core height:

a. Lower co re region, from 0 to 15% inclusive; and15% inclusive; and15% inclusive; and15% inclusive; and15% inclusive; and15% inclusive; and15% inclusive; and15% inclusive; and,

b. Upper core region, from 85 to 100% inclusive.100% inclusive.100% inclusive.100% inclusive.100% inclusive.

INSERT B 3.2.1-8C The amount of The amount of The amount of The amount of The amount of The amount of the axial core region that can be excluded during the the axial core region that can be excluded during the performance of SR 3.2.1.2 shall not exceed 15% of the upper and lower performance of SR 3.2.1.2 shall not exceed 15% of the upper and lower performance of SR 3.2.1.2 shall not exceed 15% of the upper and lower core regions, and may be reduced on a cyclecore regions, and may be reduced on a cycle-specific basis as specific basis as determined during the core reload design process. The amount of the determined during the core reload design process. The amount of the determined during the core reload design process. The amount of the axial core region that can be excluded during the performance of SR axial core region that can be excluded during the performance of SR axial core region that can be excluded during the performance of SR axial core region that can be excluded during the performance of SR axial core region that can be excluded during the performance of SR axial core region that can be excluded during the performance of SR 3.2.1.2 is identified in the COLR. The axial core regions are excluded 3.2.1.2 is identified in the COLR. The axial core regions are excluded 3.2.1.2 is identified in the COLR. The axial core regions are excluded from the evaluation because of the low probability that these regions from the evaluation because of the low probability that these regions from the evaluation because of the low probability that these regions would be more limiting in the safety analyses and because of the difficwould be more limiting in the safety analyses and because of the difficwould be more limiting in the safety analyses and because of the diffic ulty of making of making

Wolf Creek - Unit 1 B 3.2.1-8 Revision 89 INSERT B 3.2.1-8A

Equilibrium conditions are achieved when the core is sufficiently stable at the intended operating conditions required to perform the S urveillance.

The allowance of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ac hieving equilibrium conditions at the increased THERMAL POWER l evel to complete the next F QC(Z) surveillance applies to situations where the FQC(Z) has already been measured at least once at a reduced THERMAL POWER l evel.

The observed margin in the previous Surveillance wi ll provi de assurance that increasing power up to the next plateau will not exceed the F Q limit, and that the core is behaving as designed.

This Frequency condition is not intended to require verification of these parameters after every 10% increase in RTP above the THERMAL POWER at which the last verification was performed. It only requires verification after a THERMAL POWER is achieved for extended operation that is 10% higher t han the THERMAL POWER at which F QC(Z) was last measured.

INSERT B 3.2.1-8B

The measured FQ(Z) can be determined through a synthesis of the measured planar radial peaking factors, FXYM(Z), and the measured core average axial power shape, P M(Z). Thus, FQC(Z) is given by the following expression:

FQC(Z) = F XYM(Z) PM(Z)[1.0815] = FQM (Z)[1.0815]

For R AOC operation, the anal ytical [ T(Z)]COLR functions, specified in the COLR for each RAOC operating space, are used together with the measured F XY(Z) values to estimate FQ(Z) for non-equilibrium operation within the RAOC oper ating space. When the FXY(Z) values are measured at HFP ARO conditions (A XY(Z) equals 1.0), F QW(Z) is given by the following expression:

FQW(Z) = FXYM(Z) [T(Z)] COLR Rj [1.0815]

Non-equilibrium operation can resul t in significant changes to the axial po wer shape. To a lesser extent, non-e quilibrium operation can increase the radial peaking f actors, F XY(Z), through control rod insertion and through reduced Doppler and moderator feedback at part-p ower conditions.

The [T(Z)]COLR functions quantify these effects for t he range of power shapes, control rod insertion, and power levels characteristic of the operating space. Multiplying [T(Z)]COLR by the measured full power, unrodded F XYM(Z) value, and the factor that account s for manufacturing and measurement uncertainties gives FQW(Z), the maximum total peaking factor postulated for non-e quilibrium RAOC operation.

INSERT B 3.2.1-8C

c. Grid plane regions, +/- 2% inclusive, and

d. Core plane regions, within +/- 2% of the bank demand position of the control banks.

These regions of the core are excluded from the evaluation because of the low probability that they would be more limiting in the safety analyses and because of the difficulty of making a INSERT B 3.2.1-8C (continued)

precise measurement in these regions. The excluded regions at the top and bottom of the core are spe cified in the COLR and are defined to ensure that the minimum margin location is adequately surveilled. A slightly smaller exclusion zone may be specified, if necessary, to include the limiting margin location in the surveilled region of the core.

SR 3.2.1.2 requires a Surveillance of FQW(Z) during the initial startup following each refueling within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding 75% RTP. THERMAL POWER levels below 75% are typically non-limiting with respect to the limit for F QW(Z). Furthermore, startup physics testing and flux symmetry measurements, also performed at low power, provide confirmation that the core is operating as expected. This Frequency ensures that verification of F QW(Z) is performed prior to extended operation at power levels where the maximum permitted peak LHR could be challenged and that the first required performance of SR 3.2.1.2 after a refueling is performed at a power level high enough to provide a high level of confidence in the accuracy of the Surveillance result.

Equilibrium conditions are achieved when the core is sufficiently stable at the intended operating conditions required to perform the Surveillance.

If a previous Surveillance of FQW(Z) was performed at part power conditions, SR 3.2.1.2 also requires the FQW(Z) be verified at power levels 10% RTP above the THERMAL POWER of its last verification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions. This ensures that F QW(Z) is within its limit using radial peaking factors measured at the higher power level.

The allowance of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions will provide a more accurate measurement of FQW(Z) by allowing sufficient time to achieve equilibrium conditions and obtain the power distribution measurement.

Attachment IV to 000269 Page 17 of 18 FQ(Z) (FQ Methodology) (Z) (FQ4444444440HWKRGRORJ\\

B 3.2.1

RAOC - T(Z)

BASES

SURVEILLANCE SR 3.2.1.2 (continued)

REQUIREMENTS a precise measurement in these regions.a precise measurement in these regions. It should be noted that while the transient Fthe transient FQ(Z) limits are not measured in these axial core regions, the (Z) limits are not measured in these axial core regions, the analytanalytical transient F Q(Z) limits in these axial core regions are ical transient F demonstrated to be satisfied during the core reload design process. demonstrated to be satisfied during the core reload design process.demonstrated to be satisfied during the core reload design process.

This Surveillance has been modified by a Note that may require more Surveillance has been modified by a Note that may require more Surveillance has been modified by a Note that may require more frequent surveillances be performed. When F QC(Z) is measured, an frequent surveillances be performed. When F(Z) is measured, an evaluation of the expression below is required to account for any increase evaluation of the expression below is required to account for any increase evaluation of the expression below is required to account for any increase to FQ(Z) that may occur and cause the F Q(Z) limit to be exceeded before (Z) that may occur and cause the F(Z) limit to be exceeded before the next required F Q(Z) evaluation. (Z) evaluation.

If the two most recent F Q(Z) evaluations show an increase in the (Z) evaluations show an increase in the (Z) evaluations show an increase in the expression

maximum over z F CQ (Z)

K(Z)

it is required to meet the FQ(Z) limit with the last FQW(Z) increased by the (Z) limit with the last F(Z) limit with the last F appropriate factor specified in the COLR, or to evaluate Fappropriate factor specified in the COLR, or to evaluate Fappropriate factor specified in the COLR, or to evaluate F Q(Z) more frequently, each 7EFPD. These alternative requirements prevent F Q(Z) EFPD. These alternative requirements prevent FEFPD. These alternative requirements prevent F from exceeding its limit for any significant period of time without detection. from exceeding its limit for any significant period of time without detection.from exceeding its limit for any significant period of time without detection.

Performing the Surveillance in MODE 1 prior to exceeding 75%orming the Surveillance in MODE1 prior to exceeding 75% RTP ensures that the FQ(Z) limit will be met when RTP is achieved, because ensures that the F(Z) limit will be met when RTP is achieved, because peaking factors are generally decreased as power level is increased. peaking factors are generally decreased as power level is increased.peaking factors are generally decreased as power level is increased.

FQ(Z) is verified at power levels (Z) is verified at power levels 10% RTP above the THERMAL POWER of its last verification, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium POWER of its last verification, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium POWER of its last verification, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions to ensure that Fconditions to ensure that F Q(Z) is within its limit at higher power levels.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Wolf Creek - Unit 1 B 3.2.1-9 Revision 89 Attachment IV to 000269 Page 18 of 18 FQ(Z) (FQ Methodology)

B 3.2.1

BASES

REFERENCES 1. 10 CFR 50.46, 1974.

2. USAR, Section 15.4.8.

3. 10 CFR 50, Appendix A, GDC 26.

4. W CAP-7308-L-P-A, "Evaluation of Nuclear Hot Channel Factor Uncertainties," June1988.

5. Performance Improvement Request 2005-3311.

6. W CAP-12472-P-A, BEACON Core Monitoring and Operations Support System, August 1994 (including Addendum 4, September 2012).

7. WCAP-17661-P-A, Revision 1, "Improved RAOC and CAOC FQ Surveillance Technical Specifications," February 2019.

W olf Creek - Unit 1 B 3.2.1-10 Revision 70

v t e Letter Sequence Request
EPID:L-2024-LLA-0105, License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. (Open)
Initiation Request Acceptance Administration Questions Answers Results Approval... Other:
MONTHYEAR2024-07-31 [Table View]

ML24213A335

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Subject:

Subject:

SUMMARY

2.1 Background

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

SUMMARY

2.1 Background

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

0.5 where

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