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#REDIRECT [[L-2015-189, Turkey Point, Units 3 and 4 - License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement]]
| number = ML15301A261
| issue date = 10/06/2015
| title = Turkey Point, Units 3 and 4 - License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement
| author name = Summers T
| author affiliation = Florida Power & Light Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000250, 05000251
| license number =
| contact person =
| case reference number = CAW-15-4156, L-2015-189
| package number = ML15301A248
| document type = Legal-Affidavit, Letter, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Response to Request for Additional Information (RAI), Technical Specifications
| page count = 39
}}
 
=Text=
{{#Wiki_filter:Attachment 4 Contains Proprietary Information Withhold Attachment 4 from Public Disclosure in Accordance with 10 CFR 2.3900FP:FL_L-201 5-18910 CFR 50.90October 6, 2015U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4Docket Nos. 50-250 and 50-251License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement Pursuant to 10 CFR 50.90, Florida Power & Light Company (FPL) hereby requests a licenseamendment to revise the technical specifications (TS) for Turkey Point Units 3 and 4. Theproposed change revises the end-of-life moderator temperature coefficient (MTC) surveillance requirement 4.1.1.3.b for Turkey Point Units 3 and 4 by placing a set of conditions on reactorcore operation, which if met, would allow exemption from the required MTC measurement.
The Enclosure to this letter provides FPL's evaluation of the proposed changes and contains sixattachments.
Attachment 1 to the enclosure provides a markup of the TS showing the proposedchange, and the clean TS page containing the proposed change is included in Attachment 2.Included in Attachment 3 for information only is a proposed change to the Core Operating LimitsReport.Beaver Valley Power Station (BVPS), Farley Nuclear Plant (FNP), and Vogtle ElectricGenerating Plant (VEGP) previously submitted similar license amendment requests (LARs) andreceived requests for additional information (RAI) from the NRC regarding the LARs. Therefore, FPL has included responses to the RAI questions as they relate to the Turkey Point LAR inAttachment 4, FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary),
andAttachment 5, FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary).
Attachment 4 contains information proprietary to Westinghouse Electric
: Company, LLC and issupported by an affidavit in Attachment 6 signed by Westinghouse, the owner of the information.
The affidavit sets forth the basis on which the information may be withheld from publicdisclosure and addresses with specificity the considerations listed in paragraph (b)(4) of Section2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that theinformation which is proprietary to Westinghouse be withheld from public disclosure inaccordance with 10 CFR 2.390. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference Florida Power & Light company9760 SW 344th St., Florida City, FL 33035 L-201 5-189Page 2 of 2CAW-15-4156 and should be addressed to James A. Gresham,
: Manager, Regulatory Compliance, Westinghouse Electric
: Company, 1000 Westinghouse Drive, Building 3 Suite 310,Cranberry
: Township, Pennsylvania 16066.As discussed in the evaluation, the proposed change does not involve a significant hazardsconsideration pursuant to 10 CFR 50.92, and there are no significant environmental impactsassociated with the change.The Turkey Point Plant Nuclear Safety Committee (PNSC) has reviewed the proposed licenseamendment.
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to thedesignee of the State of Florida.There are no new commitments made in this submittal.
FPL requests approval of this amendment request by October 1, 2016 and implementation within90 days.Should you have any questions regarding this submittal, please contact Mr. Mitch Guth,Licensing
: Manager, at 305-246-6698.
I declare under penalty of perjury that the foregoing is true and correct.Executed on October 6, 2015Sincerely, Th'omas Su~mmersSite Vice President Turkey Point Nuclear PlantEnclosure cc: NRC Regional Administrator, Region IINRC Senior Resident Inspector NRC Project ManagerMs. Cindy Becker, Florida Department of Health L-201 5-1 89Enclosure ENCLOSURE Evaluation of the Proposed Change
 
==SUBJECT:==
License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement 1.0 SUMMARY DESCRIPTION 2.0 DETAILED DESCRIPTION 3.0 TECHNICAL EVALUATION 4.0 REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria
 
===4.2 Precedent===
4.3 Significant Hazards Consideration
 
===4.4 Conclusions===
5.0 ENVIRONMENTAL CONSIDERATION
 
==6.0 REFERENCES==
 
Attachment 1 -Markup of Technical Specification PageAttachment 2 -Clean Revised Technical Specification PageAttachment 3 -Change to Core Operating Limits Report (Information Only)Attachment 4 -FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary)
Attachment 5 -FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary)
Attachment 6 -Application for Withholding Proprietary Information from Public Disclosure L-201 5-189Enclosure Page 1 of 91.0 SUMMARY DESCRIPTION The proposed change revises the near-end of iife (EOL) Moderator Temperature Coefficient (MTC) Surveillance Requirement (SR) 4.1.1.3.b for Turkey Point Units 3 and 4 by placing a setof conditions on reactor core operation, which if met, would allow exemption from the requiredMTC measurement.
The conditional exemption will be determined on a cycle-specific basis byconsidering the margin predicted to the SR MTC limit and by the performance of other reactorcore parameters, such as beginning of life (BOL) MTC measurements and the critical boronconcentration as a function of cycle length. The conditional exemption will improve plantavailability and minimize disruptions to normal plant operation with no compromise in plantsafety. No changes to the Technical Specification (TS) Bases will be required as a result of theproposed amendment.
2.0 DETAILED DESCRIPTION WCAP-1 3749-P-A, Safety Evaluation Supporting the Conditional Exemption of the MostNegative EOL Moderator Temperature Coefficient Measurement
[Reference 1], includedsuggested TS markups.
The proposed TS changes are consistent with the WCAP's revisions.
The notation added to the SR references the WCAP. This provides the necessary linkage toensure the MTC prediction satisfies the requisite criteria of WCAP-1 3749-P-A.
The following Note is proposed to be added to SR 4.1.1.3.b:
"Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b may besuspended provided that the benchmark criteria in WCAP-1 3749-P-A and the RevisedPrediction specified in the COLR are satisfied."
3.0 TECHNICAL EVALUATION One of the controlling parameters for power and reactivity increases is the MTC. Therequirements of TS 3.1.1.3, Moderator Temperature Coefficient, ensure that the MTC remainswithin the bounds used in the applicable Updated Final Safety Analysis Report (UFSAR)accident analysis (Chapter 14). This, in turn, ensures inherently stable power operations duringnormal operation and accident conditions.
TS 3.1.1.3 places limits on the MTC, based on the accident analysis assumptions for themoderator density coefficient (MDC). A positive MDC corresponds to a negative MTC. TS3.1.1.3 requires that the MTC be less negative than the specified limit for the all rods withdrawn, EOL, Rated Thermal Power condition.
To demonstrate compliance with the Limiting Condition for Operation (LCO) for the most negative MTC LCO, SR 4.1.1 .3.b requires verification of theMTC after a 300 parts per million (ppm) equilibrium boron concentration is reached.
Becausethe Hot Full Power (HFP) MTC value will gradually become more negative with additional coreburnup and reduction in boron concentration, a 300 ppm MTC surveillance value should be lessnegative than the EOL LCO limit. To account for this effect, the 300 ppm MTC surveillance value is sufficiently less negative than the EOL LCO limit value, to provide assurance that theLCO limit will be met as long as the 300 ppm MTC surveillance criterion is met.
L-201 5-189Enclosure Page 2 of 9Currently, the TS require measurements of MTC at BOL to verify the most positive MTC limit issatisfied and near EOL to verify the most negative MTC limit is satisfied.
At BOL, themeasurement of the isothermal temperature coefficient is relatively simple to perform since it isdone at hot zero power isothermal conditions and is not complicated by changes in the reactorcoolant enthalpy rise or the presence of xenon. The measurement made near-EOL is performed at or near HFP conditions.
MTC measurements at HFP are more difficult to perform due tosmall variations in soluble boron concentration, changes in xenon concentration and distribution, changes in fuel temperature, and changes in reactor coolant enthalpy rise created by smallchanges in the core average power during the measurement.
Changes in each of theseparameters must be accurately accounted for when reducing the measurement data, oradditional measurement uncertainties will be introduced.
Even though these additional uncertainties may be small, the total reactivity change associated with the swing in moderator temperature is also relatively small. The resulting MTC measurement uncertainty created byeven a small change in power level can then become significant and, if improperly accounted for, can yield misleading measurement results.The MTC measurement typically includes time at reduced power as a result of themeasurement procedures.
This measurement introduces a perturbation to normal reactoroperation and increases the potential for a human performance error involving a reactivity manipulation.
An alternate method is proposed to improve availability and minimizeperturbations on normal reactor operation.
The MTC measurement is replaced by a designcalculation of the core MTC if predefined requirements are met.The proposed change would modify the EOL MTC SR by placing a set of conditions on coreoperations.
If these conditions are met, i.e., the specified revised prediction of the MTC andseveral core parameters measured during the cycle are within specified bounds, thesurveillance measurement would not be required to be performed.
The proposed conditional exemption from the HFP near-EOL 300 ppm MTC measurement doesnot impact the safe operation of Turkey Point Units 3 and 4. The safety analysis assumption ofa constant MDC and the actual value assumed will not change. The proposed change uses arevised prediction to determine if the MTC surveillance limit is met. The proposed method forcalculating the revised prediction is consistent with the approved algorithm contained in WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOLModerator Temperature Coefficient Measurement."
The methodology associated with the proposed change was submitted to the NRC inWestinghouse topical report WCAP-13749-P in June 1993. In October 1996, the NRCdetermined the report to be acceptable for referencing in license applications to the extentspecified and under the limitations stated in the Brookhaven Technical Evaluation Report (TER)and the NRC staff's Safety Evaluation Report.The NRC approved WCAP-13749-P-A with two conditions:
"(1) only PHOENIX(/ANC calculation methods are used for the individual plant analysesrelevant to determinations for the EOL MTC plant methodology, and(2) the predictive correction is reexamined if changes in core fuel designs or continued MTCcalculation/measurement data show significant effect on the predictive correction."
L-201 5-189Enclosure Page 3 of 9The FPL resolution to both of these conditions is discussed below.Condition 1Only PHOENIX/ANC calculation methods are used for the individual plant analyses relevantto determinations for the EOL MTC plant methodology.
'FPL Disposition to Condition 1The Turkey Point core design calculations currently are performed with the PHOENIX-P lattice code to generate cross-section data; however, the calculations may eventually transition to those that use the PARAGON lattice code.In Section 4.0, Conditions and Limitations of the NRC's Safety Evaluation (SE) for WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"
(Reference 2), the NRC stated:"1. The PARAGON code can be used as a replacement for the PHOENIX-P latticecode, whenever the PHOENIX-P code is used in NRC approved methodologies."
The NEXUS methodology is a re-parameterization of the PARAGON nuclear data outputand a new reconstruction approach within thecANC core simulator code to simplify the useof this code system for design use. NEXUS has been implemented in the PARAGON/ANC code system for design use. Specifically, the NEXUS methodology has been implemented in the parameterization of PARAGON cross sections for input to ANC and also in ANC toreconstruct those cross sections at specific nodal conditions.
The NEXUS methodology provides a linkage between PARAGON and ANC, establishing a new code system, whilestill using PARAGON.In Section 5.0, Conclusion, of the NRC's SE for WCAP-1 6045-P-A, Addendum 1-A,"Qualification of the NEXUS Nuclear Data Methodology,"
(Reference 3), the NRC stated:"The NRC staff has reviewed the TR submitted by Westinghouse and determined that the NEXUS/ANC code system is adequate to replace the PARAGON/ANC codesystem wherever the latter is used in NRC-approved methodologies."
As discussed above, future core design calculations that are performed using thePARAGON/ANC or NEXUS/ANC system will be equivalent to those performed with thoseusing the PHOENIX/ANC system. The use of PARAGON is consistent with condition (1)above in the NRC SER for WCAP-1 3749-P-A, since it was benchmarked against PHOENIX-P. Similarly, the use of NEXUS is consistent with condition (1) above in the SER for WCAP-13749-P-A, since it was benchmarked against PARAGON (which was benchmarked againstPHOENIX-P).
Therefore the PARAGON and NEXUS codes satisfy the TER requirement todemonstrate the uncertainty limits assumed in WCAP-13749-P-A, as discussed on page 5of the TER. The NRC used this TER as the basis for their SER.
L-201 5-189Enclosure Page 4 of 9For additional information regarding how FPL will meet this Condition, see Attachment 4(proprietary) or Attachment 5 (non-proprietary),
FPL Response to BVPS, FNP and VEGPRAI Questions.
Condition 2The predictive correction is reexamined if changes in core fuel designs or continued MTCcalculation/measurement data show significant effect on the predictive correction.
FPL Disposition to Condition 2Prior to the use of the conditional elimination technique, FPL will confirm that core designchanges and MTC calculation and measurement data do not show a significant effect on thepredictive correction.
The administrative controls for this confirmation will reside in theTurkey Point procedure that controls the EOL MTC surveillance.
If a significant effect isfound, the use of the predictive correction will be re-examined.
All of the core performance benchmark criteria confirmed from startup physics test results,from routine HFP boron concentration measurements, and from flux map surveillances performed during the cycle must be met before the Revised Predicted MTC can becalculated in accordance with the prescribed algorithm contained in Reference
: 1. Anillustration of the benchmark criteria is contained in Table D-1, "Benchmark Criteria forApplication of the 300 PPM MTC Conditional Exemption Methodology,"
in WCAP-13749-P-A.For additional information regarding how FPL will meet this Condition, see Attachment 4(proprietary) or Attachment 5 (non-proprietary).
FPL is using NRC-approved WCAP-1 3749-P-A as the basis for this license amendment request.
FPL will meet all of the technical requirements in the approved WCAP-13749-P-A, butproposes an enhancement to reduce regulatory burden for both the NRC and the licensee.
FPLproposes not to submit a "Most-Negative Moderator Temperature Coefficient Limit Report" tothe NRC, for two reasons.
First, there is an inconsistency in WCAP-1 3749-P-A regarding thetime frame of data collection and the submittal of the Most Negative Moderator Temperature Coefficient Limit Report to the NRC. Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves no apparent technical purpose.
Each of these reasons isdiscussed below.Section 3.3.3 of WCAP-13749-P-A states:"The Technical Specification Bases of the most negative MTC LCO and SR and the valuesof these limits are not altered.
: Instead, a revised prediction is compared to the SR MTC todetermine if the SR limit is met. The revised prediction is simply the sum of the predicted HEP 300 ppm SR MTC plus an AFD correction factor plus a predictive correction term. Thisalgorithm is summarized in Table 3-3."Appendix A of WCAP-13749-P-A requires a new Specification 6.9.1.7 to be added as statedbelow.
L-201 5-189Enclosure Page 5 of 9"6.9.1.7 The most negative MTC limits shall be provided to the NRC RegionalAdministrator with a copy to the Director of Nuclear Reactor Regulation, Attention:
Chief,Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, D. C.20555, at least 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter. This report will include the data required for thedetermination of the Revised Prediction of the 300 ppm/ARO/RTP MTC per WCAP-1 3749,"Safety Evaluation Supporting the Conditional Elimination of the Most Negative EOLModerator Temperature Coefficient Measurement",
May, 1993 (Westinghouse Proprietary)."
Since the Most Negative Moderator Temperature Coefficient Limit Report would have to besubmitted at least 60 days before reaching 300 ppm boron concentration, it cannot include the300 ppm data required for determining the Revised Prediction.
To satisfy the Most NegativeModerator Temperature Coefficient Limit Report submittal requirement, the data to be used forcalculating the revised predicted MTC may have to be taken 60 to 90 days prior to reaching 300ppm boron. WCAP-13749-P-A does not provide any method for adjusting the revised predicted MTC to account for data collected 60 to 90 days prior to reaching 300 ppm boron, nor does itprovide justification for using such early data in the calculation.
Therefore, the requirement tosubmit the Most Negative Moderator Temperature Coefficient Limit Report and the requirements for the data that go into the report are inconsistent.
Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves noapparent technical requirement.
The benchmark criteria and the algorithm in WCAP-1 3749-P-Afor determining the revised predicted MTC will be incorporated into the applicable procedures.
There is no compelling reason that this particular surveillance should require notifying the NRCprior to performing the surveillance procedure.
The exception of not including a "Most Negative Moderator Temperature Coefficient LimitReport" that is contained in WCAP-13749-P-A was approved by the NRC for South Texas Units1 and 2 in Amendment 144 to Facility Operating License No. NPF-76 and Amendment 132 toFacility Operating License No. NPF-80 dated November 26, 2002.The fourth paragraph in Section 3.2.1 of WCAP-1 3749-P-A states:"As part of determining the applicability of a conditional exemption from the near-EOC MTCmeasurement, a cycle-specific figure similar to Figure 3-1 will be provided as part of thatcycle's Technical Specifications or Core Operating Limits Report (COLR)."However, the COLR changes contained in Appendix B, "COLR Revision,"
of WCAP-1 3749-P-Ado not include a reference to Figure 3-1, Example of Predicted HFP ARO 300 ppm MTC VersusCycle Burnup. As a result, FPL proposes referencing the appropriate cycle-specific Figure 3-1,Predicted HFP ARO 300 ppm MTC Versus Cycle Burnup, for Turkey Point and the benchmark criteria in the surveillance procedure associated with the EOL MTC measurement.
The COLRwill contain the algorithm for the Revised Predicted MTC similar to the draft change to the COLRshown in Attachment
: 3.
L-2015-189 Enclosure Page 6 of 94.0 REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria
*10 CFR 50.36(c),
"Technical specifications,"
requires Technical Specifications tobe included for the following categories:
(1) Safety limits,/limiting safety system settings, and limiting controlsettings.
(2) Limiting conditions for operation.
(3) Surveillance requirements.
(4) Design features.
(5) Administrative controls.
10 CER 50.36(c)
(3) Surveillance requirements, states:"Surveillance requirements are requirements relating to test, calibration, orinspection to assure that the necessary quality of systems and components ismaintained, that facility operation will be within safety limits, and that the limitingconditions for operation will be met."None of the TS categories are impacted by the proposed TS changes, and SR4.1.1.3.b is not being deleted.
The Bases for and values of the most negativeMTC Limiting Condition for Operation and for the Surveillance Requirement arenot altered.
: Instead, a revised prediction is compared to the MTC Surveillance limit to determine if the limit is met.Therefore, 10 CFR 50.36(c) continues to be met.4.2 Precedent Several license amendments have been approved allowing an alternative to an EOLMTC surveillance test measuring the MTC. The following are approved licenseamendments similar to Turkey Point's request:* NRC letter to FPL Energy Seabrook, LLC, "Seabrook
: Station, Unit No. 1 -Issuance of Amendment RE: Removal of Requirement to Perform End-of-Life Moderator Temperature Coefficient Measurement (TAC No. MC 6566)," February17, 2006, Accession No. ML060040160.
* NRC letter to FirstEnergy Nuclear Operating
: Company, "Beaver Valley PowerStation, Unit Nos. 1 and 2 -Issuance of Amendments Regarding Technical Specification 3.1.3, 'Moderator Temperature Coefficient Measurement' (TACNos. ME9144 and ME9145),"
September 17, 2014, Accession No.ML14245A1 51.* NRC letter to STP Nuclear Operating
: Company,
'South Texas Project, Units 1and 2 -Issuance of Amendments Approving Technical Specification ChangesRevising the End of Life Moderator Temperature Coefficient Surveillance L-201 5-189Enclosure Page 7 of 9Requirements (TAC Nos. MB5160 and MB5161),"
November 26, 2002,Accession No. ML023400252.
Turkey Point's request varies from these amendments because it does not add areference to WCAP-13749-P-A in TS 6.9.1.7, Core Operating Limits Report. Consistent with GL 88-16, WCAP-13749-P-A does not establish a core operating limit. The footnotethat modifies SR 4.1.1 .3.b refers to WCAP-1 3749-P-A, so adding the reference to TS6.9.1.7 would be redundant.
In addition, the TS changes provided in WCAP-1 3749-P-Ado not include a revision to the TS requirements for the COLR. Therefore, FPLdetermined that adding to TS 6.9.1.7 a reference to WCAP 13749-P-A would beredundant and unnecessary.
4.3 Significant Hazards Consideration The proposed changes revise the near-end of life (EOL) Moderator Temperature Coefficient (MTC) Surveillance Requirement (SR) 4.1.1.3.b by placing a set of conditions on reactor core operation, which if met, would allow exemption from the required MTCmeasurement.
The conditional exemption will be determined on a cycle-specific basisby considering the margin predicted to the surveillance requirement MTC limit and theperformance of other reactor core parameters, such as beginning of life (BOL) MTCmeasurements and the critical boron concentration as a function of cycle length.As required by 10 CFR 50.91(a),
FPL has evaluated the proposed changes to theTurkey Point TS using the criteria in 10 CFR 50.92 and has determined that theproposed changes do not involve a significant hazards consideration.
An analysis of theissue of no significant hazards consideration is presented below:1: Does the proposed amendment involve a significant increase in the probability orconsequences of an accident previously evaluated?
Response:
NoThe safety analysis assumption of a constant moderator density coefficient andthe actual value assumed are not changing.
The Bases for and values of themost negative MTC Limiting Condition for Operation and for the Surveillance Requirement are not changing.
: Instead, a revised prediction is compared to theMTC Surveillance limit to determine if the limit is met.The proposed changes to the TS do not affect the initiators of any analyzedaccident.
In addition, operation in accordance with the proposed TS changesensures that the previously evaluated accidents will continue to be mitigated asanalyzed.
The proposed changes do not adversely affect the design function oroperation of any structures,
: systems, and components important to safety.The probability or consequences of accidents previously evaluated in the UFSARare unaffected by this proposed change because there is no change to any L-201 5-1 89Enclosure Page 8 of 9equipment response or accident mitigation scenario.
There are no new oradditional challenges to fission product barrier integrity.
Therefore, it is concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2: Does the proposed amendment create the possibility of a new or different kind ofaccident from any accident previously evaluated?
Response:
NoThe proposed changes do not involve a physical alteration of the plant (no newor different type of equipment will be installed).
The proposed changes do notcreate any new failure modes for existing equipment or any new limiting singlefailures.
Additionally the proposed changes do not involve a change in themethods governing normal plant operation and all safety functions will continueto perform as previously assumed in accident analyses.
Thus, the proposedchanges do not adversely affect the design function or operation of anystructures,
: systems, and components important to safety.No new accident scenarios, failure mechanisms, or limiting single failures areintroduced as a result of the proposed changes.
The proposed changes do notchallenge the performance or integrity of any safety-related system.Therefore, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
3: Does the proposed amendment involve a significant reduction in a margin ofsafety?Response:
NoThe margin of safety associated with the acceptance criteria of any accident isunchanged.
The proposed change will have no affect on the availability, operability, or performance of the safety-related systems and components.
Achange to a surveillance requirement is proposed based on an alternate methodof confirming that the surveillance is met. The Technical Specification LimitingCondition for Operation limits are not being changed.The proposed change will not adversely affect the operation of plant equipment or the function of equipment assumed in the accident analysis.
Therefore, it is concluded that the proposed change does not involve a significant reduction in a margin of safety.Based upon the above analysis, FPL concludes that the proposed amendment does notinvolve a significant hazards consideration',
under the standards set forth in 10 CFR L-201 5-189Enclosure Page 9 of 950.92(c),
"Issuance of Amendment,"
and accordingly, a finding of "no significant hazardsconsideration" is justified.
 
===4.4 Conclusions===
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation inthe proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical tothe common defense and security or to the health and safety of the public.5.0 ENVIRONMENTAL CONSIDERATIONS A review has determined that the proposed amendment would change a requirement withrespect to installation or use of a facility component located within the restricted area, as definedin 10 CER Part 20, or would change an inspection or surveillance requirement.
: However, theproposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be releasedoffsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion setforth in 10 CFR 51 .22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b),
no environmental impactstatement or environmental assessment need be prepared in connection with the proposedamendment.
 
==6.0 REFERENCES==
: 1. WCAP-1 3749-P-A, "Safety Evaluation Supporting the Conditional Exemption of theMost Negative EOL Moderator Temperature Coefficient Measurement,"
March 1997.2. WCAP-1 6045-P-A, "Qualification of the Two-Dimensional Transport CodePARAGON,"
August 2004.3. WCAP-1 6045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear DataMethodology,"
August 2007.
L-2015-1 89Attachment 1Attachment 1Markup of Technical Specification Page REACTIVIT CONDTROL SYSTOEMSIO LIMITING CONDITION FOR OPERATION ACTION:(Continued)
: b. With the MTC more negative than the EOL limit specified in the COLR, be in HOT SHUTDOWNwithin 12 hours.SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior toinitial operation above 5% of RATED THERMAL POWER, after each fuel loading; andrlb. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppmlsurveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppmZ In theevent this comparison indicates the MTC is more negative than the 300 ppm surveillance limitspecified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limitspecified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.* Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b mayIbe suspended provided that the benchmark criteria in WCAP-13749-P-A and theRevised Prediction specified in the COLR are satisfied.
TURKEY POINT-UNITS3&4 314 1-5TUREYPIN-UNTS34
/4 -5AMENDMENT NOS. 260 AND 2-6 1' L-2015-189 Attachment 2Attachment 2Clean Revised Technical Specification Page REACTIVIT CONDTROL SYSTOEMSIO LIMITING CONDITION FOR OPERATION ACTION:(Continued)
: b. With the MTC more negative than the EOL limit specified in the COLR, be in HOT SHUTDOWNwithin 12 hours.SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior toinitial operation above 5% of RATED THERMAL POWER, after each fuel loading; andb. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppmsurveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWERcondition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm*. In theevent this comparison indicates the MTC is more negative than the 300 ppm surveillance limitspecified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limitspecified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.* Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b may be suspended providedthat the benchmark criteria in WCAP-13749-P-A and the Revised Prediction specified in the COLR are satisfied.
TURKEY POINT -UNITS 3 & 4 3415AEDETNS N3/4 1-5AMENDMENTNOS.
AND L-201 5-1 89Attachment 3Attachment 3Change to Core Operating Limits Report(Information Only)
EC 279407PTN-3F.JF-13-080 Rev. 02.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)<+ 5.0 x 10"5 Ak/k/&deg;FBOL, HZP, ARO and,from HZP to 70% Rated Thermal Power (RTP)From 70% RTP to 100% RTP the MTCdecreasing linearly from _< + 5.0 x 10s Ak/k/&deg;Fto _< 0.0 x 10"s Ak/k/0FLess negative than -41.0 x 1 0. Ak/k/&deg;FEOL, RTP, ARO2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)-Less negative than -35.0 x 1 0" Ak/k/&deg;FWithin 7 EFPD of reachingequilibrium boron concentration of300 ppm.2.7 Analog Rod Position Indication System (TS 3.1.3.2)-Figure A3 (page 14A-A9)The All Rods Out (ARO) position for all shutdown Banks andControl Banks is defined to be 230 steps withdrawn.
2.8 Control Rod Insertion Limits (TS 3.1.3.6)-Figure A3 (page 14A-A9)The control rod banks shall be limited in physical insertion asspecified in Figure A3 for ARO = 230 steps withdrawn.
2.9 Axial Flux Difference (TS 3.2.1)-Figure A4 (page 14A-A10)2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)-[Fo]L= 2.30-K~) =1.0Fo 1'4A-A1'wer5 i oe egt nf14A-A5 Insert 1The Revised Predicted near -EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP-1 3749-P-A:
Revised Predicted MTC = Predicted MTC + AFD Correction
-3 PCM/degree FIf the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limitand all the benchmark data contained in the surveillance procedure are met, then an MTCmeasurement in accordance with SR 4.1.1.3.b is not required to be performed.
L-201 5-189Attachment 5Attachment 5FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary)
L-201 5-189Attachment 5Page 1 of 10BVPS RAI Question 1:In accordance with the second condition in the NRC staff's safety evaluation for WCAP-13749-P-A, the licensee proposed to confirm, on a cycle-specific basis, that core fueldesign changes or data from MTC predictions and measurements do not show asignificant effect on the predictive correction.
Please clarify the process and criteria formaking this determination and justify their adequacy (e.g., statistical
: testing, engineering
: judgment, etc.).Response:
As described in WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption ofthe Most Negative EOL Moderator Temperature Coefficient Measurement,"
approved in March1997, the HFP predictive correction accounts for the observed differences between themeasured and predictive (M-P) MTCs. "The hot full power (HFP) predictive correction
([]o)was "derived by summing the hot zero power (HZP) predictive correction, the xenonsensitivity and the burnup sensitivity."
The HZP predictive correction is provided in WCAP-13749-P-A.
As long as the beginning of life (BOL) HZP MTC (M-P) is less negative than theHZP predictive correction, the HFP predictive correction is valid for use during the cycle.*Tables 1 and 2 provide Beginning-of-Life (BOL) HZP Isothermal Temperature Coefficient (ITC)measured values (ITC M), predicted values (ITC P), and the measured minus the predicted values (M-P) for each cycle listed for Turkey Point Unit 3 and Unit 4. The ITC M for both units isconsistently more positive than ITC P, and therefore is conservative for evaluating the continued use of the HFP predictive correction value of [ ]ac Note that the BOL HZP ITC datawas included instead of BOL HZP MTC data as the measured BOL HZP MTC is just thepredicted BOL HZP Doppler Temperature Coefficient (DTC) subtracted from the measured BOLHZP ITC. Therefore, the same M-P value will be calculated for the BOL HZP MTC and BOLHZP ITC data sets. Thus, the conclusion that the HFP predictive correction is valid for useduring the Turkey Point Unit 3 and Unit 4 cycles is still valid.Table 1: Turkey Point Unit 3 BOL HZP ITC Data (all values in pcm/&deg;F)
L-201 5-189Attachment 5Page 2 of 10Table 2: Turkey Point Unit 4 BOL HZP ITC Data (all values in pcm/&deg;F)Cycle ITC M ITC P (M-P)26 -0.337 [ ]a,c [ ]a,c27 -1.456 [ ]a,c [ ]a,c28 -0.821 [ ]a~c [ ]a,cWCAP-13749-P-A states, "...the (HFP) predictive correction is reexamined if changes in corefuel designs or continued MTC calculation/measurement data show significant effect on thepredictive correction."
Duping the Turkey Point core design process for each cycle, FPL wouldverify that the predictive correction remains valid for the applicable fuel cycle by performing thefollowing two qualitative assessments.
: 1. FPL would identify fuel and core design methodology changes as part of the fueldesign process.
Prior to each reload, a reload risk evaluation checklist is used toidentify and determine the risk of major fuel design changes or core designmethodology changes.
This checklist would identify whether the reload will use*revised or different methodologies, and assesses the impact of these changes on theexisting analyses.
This evaluation would provide initial indication of a possiblechange in the BOL HZP MTC (M-P) relationship prior to startup of the fuel cycle.2. Per TS 3.1 .1.3, each cycle during low power physics testing, FPL measures the BOLHZP MTC. Prior to each conditional exemption of the end of life (EOL) HFP MTCmeasurement test, FPL would compare Turkey Point specific MTC (M-P) data eachcycle against previous cycles to determine if there is a change to the measured vs.predicted MTC relationship.
If the value of the BOL HZP MTC (M-P) approaches the HZP predictive correction given inWCAP-1 3749-P-A then FPL would evaluate the use of the HFP MTC predictive correction toshow that the value of [ ja,c is conservative or measure the EOL HFP MTC inaccordance with the Technical Specifications.
The above tools and assessments would beused each cycle during and after a transition to NEXUS/ANC9 (PARAGON) to verify continued consistency and validity of the BOL HZP MTC (M-P) relationship as it pertains to the predictive correction of WCAP-1 3749-P-A.
BVPS RAI Question 2:The predictive correction term defined in WCAP-1 3749-P-A is based, in part, on atolerance limit that Westinghouse derived from differences between a set of measuredand predicted values of the MTC at the beginning of an operating cycle at hot, zero-power conditions.
Specifically, the predicted MTC values in WCAP-1 3749-P-A weredetermined from calculations using the PHOENIX-P/ANC code package for a variety ofpressurized-water reactor (PWR) core designs prior to 1995. Although the NRC staff hasapproved the PARAGON lattice physics code as a replacement to PHOENIX-P, it cannot L-201 5-189Attachment 5Page 3 of 10not be concluded that the statistical
: database, and hence the predictive correction terms,for the two codes will be equivalent.
Therefore, if approval for the use of the predictive correction term derived for the PHOENIX-P code for calculations with the PARAGONcode is sought under this license amendment
: request, please provide unbiased andstatistically significant data analogous to that reported in Table 3-1 of WCAP-13749-P-A for calculations performed with the PARAGON code for contemporary PWR coredesigns, along with: (1) justification that this data belongs to the same population as thepre-1995 data in WCAP-1 3749-P-A, generated with the PHOENIX-P code; or (2) a newpredictive correction term for the PARAGON code for contemporary cores that is basedon a 95195 tolerance limit appropriate for modifying end-of-cycle MTC predictions madewith this code.Response:
A database of plants is used for regression testing and continued qualification of core designsystem code releases.
This database consists of multiple cycles of plants chosen to encompass the variety of plant, fuel lattice types, and fuel management strategies that the code will be usedto analyze.
Comparison of the results for any release with those of previous releases assurescontinued compliance of the code with its licensing basis.This set of contemporary PWR cores has been selected as representative of the statistical database used in WCAP-13749-P-A.
These cores have been modeled using both PHOENIX-P/ANC and NEXUS/ANC (the NEXUS cross-section generation system uses PARAGON as thelattice transport code).Table I below lists data analogous to that reported in Table 3-1 of WCAP-1 3749-P-A forcalculations performed with NEXUS/ANC.
Benchmarks for both PHOENIX-P/ANC andNEXUS/ANC are listed in the table to show a comparison between the two code sets. MeasuredEnd-Of-Cycle (EOC) Hot Full Power (HEP) Moderator Temperature Coefficient (MTC) data isnot readily available for most of the benchmark cores, and therefore, for this parameter, measured-minus-predicted data was only provided for Turkey Point for PHOENIX-P/ANC.
Additionally, Beginning-of-Cycle (BOC) Hot Zero Power (HZP) Isothermal Temperature Coefficient (ITC) data was included instead of BOC HZP MTC data as the measured BOC HZPMTC is just the predicted BOC HZP Doppler Temperature Coefficient (DTC) subtracted from themeasured BOC HZP ITC.The results in Table 1 show that[]a,c Using the measured-minus-predicted values in Table 1, the predictive correction term fromWCAP-1 3749-P-A[
]aCUsing commercial statistics
: software, the BOC HZP ITC M-P data points in Table 1 have beendemonstrated to fall within a normal distribution per the Anderson-Darling and Ryan-Joiner tests, with a M-P mean of [ ]a~c pcm/OF and a standard deviation of [ ]a~ pcm/OF. Fromthis data, a 95/95 one-sided tolerance limit for the HZP predictive correction of [ ]a'c pcm/OFcan be calculated using a K-value of []~
L-201 5-189Attachment 5Page 4 of 10Applying[
]a.c from WCAP-1 3749-P-A
[ ]a.C yields a HFP predictive correction of [ ]a,c pcm/OF.[]a,cAdditionally, the predictive correction term for PHOENIX-P/ANC was recalculated forcomparison (for contemporary cores). [ ]a,cusing the K-value of [ ]a~C a HZP Predictive'correction of [ ]a,c pcm/OF wascalculated.[
]a.c yields a HFP predictive correction of [ ]a~c pcm/OF.[]a~c This shows that: (1) the PHOENIX-P/ANC results inWCAP-13749-P-A are reproducible with the contemporary PWR cores and latest code versions, and (2) the set of cores chosen represents a good unbiased sample of the larger data set usedin WCAP-1 3749-P-A.
L-201 5-189Attachment 5Page 5 of 10Table 2: Summary of Statistics for Measured Minus Predicted Differences of Criticalboron, ITC, MTC, and Rod Worths for Westinghouse CoresPHOENIX-PIANC NEXUSIANC Mean Std. 0ev. Mean Std. Dev.NO.Pts. -a,cParameter Farlev and Vogitle RAI Question 1:On December 28, 2012, the NRC issued requests for additional information (RAIs) for asimilar license amendment request (LAR) at Beaver Valley Power Station (BVPS). InEnclosure 9, SNC provided their responses to. these RAIs. Table I of Enclosure 9provides a summary of statistics to compare PHOENIX-PIANC and NEXUSIANC results.Though the PHOENIX-PIANC and NEXUSIANC results compare favorably to each other,they appear to differ significantly from the values found in Table 3-1 of WCAP-1 3749-P-A.
Please discuss this discrepancy.
In this discussion, emphasis should be placed on the differences in the means andstandard deviations between the two tables, particularly for the end-of-cycle (EOC) hotfull power (HFP) moderator temperature coefficient (MTC). The discussion shouldpresent a statistical analysis of the datasets used to generate the two tables to explainwhether or not the results presented belong to the same population.
"The discussion should also address the deviation between measured and predicted critical boron throughout the cycle. Based on the statistics
: provided, many of thecalculated values would apparently violate the generally-used acceptance criterion of +50 ppm for comparison to measurements (as discussed in ANSI/ ANS-19.6.1, thePARAGON topical report WCAP-1 6045-P-A, and others).
L-201 5-189Attachment 5Page 6 of 10ResponseResponse to Paragraphs 1 and 2The plants and cycles used for benchmarking Westinghouse PWR nuclear analysis methodsare continuously updated to reflect the changes that occur in fuel management and operations.
Westinghouse does not use one single consistent set of plant/cycles for code qualification, because that would restrict the validation basis to include only old operating cycles that do notreflect today's modern fuel designs, power uprates, increased fuel burnups, and longer cycleswith higher operating capacity factors.Table 3-1 in WCAP-13749-P-A compares the measured to predicted EOL HFP MTC. The Table3-1 results show a mean difference of [ ]a~ pcm/OF and a standard deviation of [ ]a,cpcm/&deg;F based on [ ]a~c data points. Based on RAls received for the EOL MTC topical report,additional data was also provided in Section G, Table 2 of that topical report. The EOC HFPMTC data is expanded to include [ ]a~c data points with a mean difference of [ ]a~c pcm/OFand a standard deviation of [ ]a~ pcm/OF.The response to BVPS RAl Question 2 compared recent NEXUS/ANC code system predictions to recent PHOENIX-P/ANO code system predictions to establish the similarity of predictions forMTC and ITO between the two code systems.
The data presented was from the qualification ofthe NEXUS/ANC code system, so it used the more recent plant/cycle data used in that codesystem qualification.
: However, EOL HFP MTC comparisons of measured and predicted datawere not available for this qualification effort, so only comparisons of predictions for EOL HFPMTO between the NEXUS/ANC and PHOENIX-P/ANC code systems were presented.
Thesecomparisons demonstrate the predictive capability for the NEXUS/ANC code system iscomparable to the predictive capability for the PHOENIX-P/ANC code system.Table 1 in the response to BVPS RAI Question 2 provides the ITO and MTO comparisons.
Using the more recent plant/cycle data, the BOO, HZP ITO predictions from [ ]a~c data pointsusing the PHOENIX-P/ANC code system show a mean difference of [ ]a~c pcm/OF and astandard deviation of [ ]a~c pcm/OF. This code performance is comparable to the datapresented in the EOL MTC topical report. The comparable NEXUS/ANC code system datashows a mean difference of [ ]a~c pcm/OF and a standard deviation of [ ]a,c pcm/OF. TheNEXUS/ANC code system appears to be slightly more accurate for BOO, HZP ITO predictions c'ompared to the PHOENIX-P/ANC code system, although the differences are relatively small. Absolute comparisons of predicted EOL, HFP MTC are also presented in that table forboth code systems to again demonstrate the similarity of the predictions.
These are notmeasured minus predicted comparisons, but just comparisons of absolute MTC predicted values. For the PHOENIX-P/ANC code system, the mean prediction is [ ]a~ pcm/OF with astandard deviation of [ ]a~ pcm/OF. For the NEXUS/ANO code system the mean prediction is[]a,c pcm/OF with a standard deviation of [ ]a'c pcm/OF. This comparison again demonstrates that the code systems provide comparable predictive capability, so the conclusions of the EOLMTC topical report, WCAP-1 3749-P-A would not change based on substitution of the NEXUScode system for the PHOENIX-P/ANC code system.Some comparisons of PHOENIX-P/ANC code system predictions of EOL HFP MTC tomeasurements are also provided to illustrate that data comparisons using more recentplant/cycles
.show behavior that is as good as or better than that presented in the EOL MTC L-201 5-189Attachment 5Page 7 of 10measurement elimination topical report, WCAP-13749-P-A.
The more recent PHOENIX-PIANC code system EOL, HFP MTC measured to predicted comparisons show a mean difference of[]a,c pcm/OF and a standard deviation of [ ]a,c pcm/OF. These comparisons show somewhatbetter performance compared to the EOL MTC measurement elimination topical report, WCAP-13749-P-A, but are also taken from a smaller set of plant cycles, where [ ]a.C plant cyclesare presented.
Based on the close agreement between PHOENIX-PIANO and NEXUS/ANC, asdescribed above, comparable measured to predicted statistics for the EOL HFP MTC areexpected when the predictions are based on NEXUS/ANC.
Response to Paraciraph 3Regarding the question on deviation between measured and predicted critical boronconcentrations throughout the cycle, the measured data includes the effects of boron-i10 (108)depletion in the coolant during the cycle, while the predictions assume the nominal (no 1&deg;Bdepletion) 1&deg;B fractions.
During operation, the 1&deg;B in the coolant will deplete due to exposure toneutron flux from the reactor core. As a result, the measured concentration at the middle of thecycle will be higher to maintain critical conditions than if no 1&deg;B depletion occurred.
Westinghouse chose to present the comparison data without accounting for depletion effects inthe predictions, since we do not have access to the actual measured 10B fractions for all of thecycles where we compare it to measured data. The effect of 1&deg;B depletion is largest at themiddle of cycle, where the measured concentrations are typically 50-100 ppm higher than if no108 depletion were occurring.
Based on Westinghouse's experience with modeling 1&deg;B depletion when the data is available, accounting for this effect would significantly reduce the mean error inthe presented MOO data such that it would compare with or be better than previously reportedperformance statistics.
To illustrate this point, two plant cycles were simulated to predict the effects of 1&deg;B depletion inthe coolant.
One is a three loop plant and the other is a four loop plant. The three loop plantshows that accounting for l&deg;B depletion increased the MOC boron concentration by [ ]a,c ppm,while the four loop result is a [ ]a,c ppm increase in predicted boron. These results areconsistent with the reported MOO difference in boron concentration where l&deg;B depletion effectswere not included in the predictions.
L-2015-1 89Attachment 5Page 8 of 10a.caocResponse Conclusion In conclusion, the plants/cycles chosen for code validation are always being updated as newdata from more recent, modern core and fuel design become available.
A comparison of thecode performance for MTC predictions shows a general improvement over time. TheNEXUS/ANC code system also shows slightly better performance compared to the olderPHOENIX-P/ANC code system. As such, the conclusions of the EOL MTC measurement elimination topical report, WCAP-1 3749-P-A remain applicable when either code system isused.
L-201 5-189Attachment 5Page 9 of 10Farley and Vogitle RAI Question 2"The LAR states that the 'FNP [Farley Nuclear Plant] and VEGP [Vogtle Electric Generating Plant] core design calculations are currently being transitioned from nuclear calculations that are performed with the PHOENIX-P lattice code to generate cross-section data tothose that will be performed with the PARAGON lattice code.' Farley TS 5.6.5.b, the CoreOperating Limits Report (COLR) reference list, includes references for PHOENIX-P aswell as the PARAGON and NEXUS methodologies.
Vogtle TS 5.6.5.b, on the other hand,does not include any of these references.
In both sites' TS, WCAP-9272-P-A,
'Westinghouse Reload Safety Evaluation Methodology' is referenced for calculation of the moderator temperature coefficient.
WCAP-9272 states that 'the values of all measured parameters are calculated using thedesign codes described in Table 3.1.' Table 3.1 is a list of older neutronics codes, suchas LEOPARD and TURTLE, which were in use at the time when WCAP-9272-P-A was firstpublished in 1978. While the Vogtle and Farley Final Safety Analysis Reports (FSARs)include references to these older codes as well as newer codes like PHOENIX-P andANC, they both indicate that the newer codes are used for core design.a. Please discuss how WCAP-9272-P-A is being used for calculation of the MTClimits for TS 3.1.3 when the codes being used for design are not part of theWCAP-9272-P-A methodology.
: b. Please provide a justification for why the COLR reference list for Vogtle doesnot need to be updated to include PHOENIX-P,
: PARAGON, andlor NEXUS.This is especially pertinent given that Farley submitted an LAR on August 14,2012 (ADAMS Accession No. ML 12227A884),
specifically to include NEXUS intheir COLR reference list.Response to a.WCAP-9272-P-A is currently being used at Turkey Point Units 3 and 4 for the calculation of theModerator Temperature Coefficient (MTC) limits, as is currently identified in TS 6.9.1.7 for eachof those plants. As noted in the RAl, the computer codes cited in WCAP-9272-P-A, LEOPARDand TURTLE have been superseded by newer codes, specifically PHOENIX-P and ANC, ascorrectly described in the Turkey Point Units 3 and 4 ESARs. ANC was approved by the NRCvia WCAP-1 0965-P-A, which states: "The intended usage of the Advanced Nodal Codeencompasses all applications described in the reload safety evaluation methodology topicalreport. [3]", where [3] refers to WCAP-9272-P-A.
The NRC then approved the use of PHOEN IX-P and ANC based on qualification work that was documented in WCAP-1 1596-P-A, whichincorporates WCAP-1 0965-P-A by reference.
This reference (WCAP-1 1596-P-A) thus supportsthe use of PHOENIX-P and ANC in lieu of LEOPARD and TURTLE.Similarly, Westinghouse recently developed the NEXUS/PARAGON code suite for use withANC and received NRC approval for its use in core design work via WCAP-1 6045-P-A andWCAP-16045-P-A, Addendum 1-A. These approvals support this application and provide thenecessary benchmarking data to support Turkey Point Units 3 and 4 transitioning toNEXUS/PARAGON in the future.
L-201 5-189Attachment 5Page 10 of 10The supporting Safety Evaluation Report for WCAP-9272-P-A acknowledges that "significant changes to codes and methods are extensively documented in topical reports to the NRC staffin order that generic approval be obtained."
: Likewise, as updated codes and methods areapproved and used in reactor core designs they follow the design guideline provided in WCAP-9272-P-A and incorporated into the design using 10 CFR 50.59 because they are previously approved methods.Response to b.Similarly, like Vogtle, Turkey Point also does not include PHOENIX-P in the list of COLRmethodologies.
As stated, PHOENIX-P has been generically approved.
When the PHOENIX-P method and other updated codes and methods are generically approved they can beincorporated into the plant's design using 10 CFR 50.59. Furthermore, these methods are toolsused to confirm that reload parameters are bounded by the values used in the safety analysis.
These tools are not methodologies used to calculate core operating limits. As such, TurkeyPoint does not propose to add PHOENIX-P, PARAGON,-or NEXUS to the listed COLRreferences in the technical specifications.
L-2015-1 89Attachment 6Attachment 6Application for Wi.thholding Proprietary Information from Public Disclosure We in houseWestinghouse Electric Company0 Engineering, Equipment and Major Projects1000 Westinghouse Drive, Building 3Cranberry
: Township, Pennsylvania 16066USAU.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643Document Control Desk Direct fax: (724) 940-856011555 Rockville Pike e-mail: greshaja@
westinghouse.corn Rockville, MD 20852 Proj letter: NF-NEXT-15-74 CAW- 15-4 156April 7, 2015APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
 
==Subject:==
 
Turkey Point Units 3 and 4,Docket Nos. 50-250 and 50.251,License Amendment Request 240,Conditional Exemption from End-of Life Moderator Temperature Coefficient Measurement, FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced documentis further identified in Affidavit CAW-15-4156 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The Affidavit, which accompanies this letter, sets forth the basison which the information mnay be withheld from public disclosure by the Commission and addresses withspecificity the considerations listed in paragraph (b)(4) of 10 CER Section 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Florida Power andLight Company (FPL).Correspondence with respect to the proprietary aspects of the Application for Withholding or theWestinghouse Affidavit should reference CAW-15-41 56, and should be addressed to James A. Gresham,Manager, Regulatory Compliance, Westinghouse Electric
: Company, 1000 Westinghouse Drive,Building 3 Suite 310, Cranberry
: Township, Pennsylvania 16066.Very truly yours,/James A. Gresham, ManagerRegulatory Compliance CAW-l 5-4 156April 7, 2015AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
SSCOUNTY OF BUTLER:I, James A. Gresham, am authorized to execute this Affidavit on behalf of Westinghouse ElectricCompany LLC (Westinghouse),
and that the averments of fact set forth in this Affidavit are true andcorrect to the best of my knowledge, information, and belief.
A Gr~esham, angeRegulatory Compliance 22 CAW- 15-4156(1) I am Manager, Regulatory Compliance, Westinghouse Electric Company LLC (Westinghouse),
and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plantlicensing and rule making proceedings, and am authorized to apply for its withholding on behalfof Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of theCommission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether theinformation sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been heldin confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and notcustomarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information inconfidence.
The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.
Under that system, information is held in confidence if it falls in one or more of severaltypes, the release of which might result in the loss of an existing or potential competitive advantage, as follows:(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of 33 CAW-I15-41 56Westinghouse's competitors without license from Westinghouse constitutes acompetitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (orcomponent, structure, tool, method, etc.), the application of which data secures acompetitive economic advantage, e.g., by optimization or improvedmarketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve hiscompetitive position in the design, manufacture,
: shipment, installation, assurance of quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, orcommercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer fundeddevelopment plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(iii) There are sound policy reasons behind the Westinghouse system which include thefollowing:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure toprotect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which suchinformation is available to competitors diminishes the Westinghouse ability tosell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage byreducing his expenditure of resources at our expense.
44 CAW-15-4156 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
Ifcompetitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of acompetitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence ofWestinghouse in the world market, and thereby give a market advantage to thecompetition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research anddevelopment depends iupon thle success in obtaining and maintaining acompetitive advantage.
(iv) The information is being transmitted to the Commission in confidence and, under theprovisions of 10 CFR Section 2.390, it is to be received in confidence by theCommission.
(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method tothe best of our knowledge and belief.(vi) The proprietary information sought to be withheld in this submittal is that which isappropriately marked in "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251,License Amendment Request 240, Conditional Exemption from End-of Life Moderator Temperature Coefficient Measurement, FPL Response to BIVPS, FNP and VEGP RAIQuestions" (Proprietary),
for submittal to the Commission, being transmitted by FloridaPower and Light Company (FPL) letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with FPL's request for NRCapproval of a License Amendment Request that would allow a change to the TurkeyPoint Units 3 and 4 Technical Specifications to provide a conditional exemption fromModerator Temperature Coefficient measurement, and may be used only for that purpose.
55 ~CAW- 15-4156(a) This information is part of that which will enable Westinghouse to:(i) Assist FPL with Obtaining NRC approval of' a License Amendment Request that would allow a change to the Technical Specifications toprovide a conditional exemption from Moderator Temperature Coefficient measurement.
(ii) Provide Results of customer specific calculations.
(iii) Provide licensing support for customer submittals.
(b) Further this information has substantial commercial value as follows:(i) Westinghouse plans to sell the use of similar information to its customers for the purpose of meeting NRC requirements for licensing documentation associated with End of Life Moderator Temperature Coefficient Elimination submittals.
(ii) Westinghouse can sell support and defense of industry guidelines andacceptance criteria for plant-specific applications.
(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
*Public disclosure of this proprietary information is likely to cause substantial harm to thecompetitive position of Westinghouse because it would enhance the ability ofcompetitors to provide similar technical evaluation justifications and licensing defenseservices for commercial power reactors without commensurate expenses.
Also, publicdisclosure of the information would enable others to use the information to meet NRCrequirements for licensing documentation without purchasing the right to use theinformation.
6 CAW-15-4156 The development of the technology described in part by the information is the result ofapplying the results of many years of experience in an intensive Westinghouse effort andthe expenditure of a considerable sum of money.In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower:
effort, having therequisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICETransmitted herewith are proprietary and non-proprietary versions of documents furnished to the NRCassociated with FPL' s request for NRC approval of a License Amendment Request that would allow achange to the Turkey Point Units 3 and 4 Technical Specifications to provide a conditional exemption from Moderator Temperature Coefficient measurement, and may be used only for that purposeIn order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning theprotection of proprietary information so submitted to the NRC, the information which is proprietary in theproprietary versions is contained within brackets, and where the proprietary information has been deletedin the non-proprietary
: versions, only the brackets remain (the information that was contained within thebrackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item of information beingidentified as proprietary or in the margin opposite such information.
These lower case letters refer to thetypes of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).
COPYRIGHT NOTICEThe reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted tomake the number of copies of the information contained in these reports which are necessary for itsinternal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment,
: transfer, renewal, modification, suspension, revocation, or violation of a license,permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on publicdisclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding.
With respect to the non-proprietary versions of these reports, the NRC ispermitted to make the number of copies beyond those necessary for its internal use which are necessary inorder to have one copy available for public viewing in the appropriate docket files in the public documentroom in Washington, DC and in local public document rooms as may be required by NRC regulations ifthe number of copies submitted is insufficient for this purpose.
Copies made by the NRC must includethe copyright notice in all instances and the proprietary notice if the original was identified as proprietary.
Attachment 4 Contains Proprietary Information Withhold Attachment 4 from Public Disclosure in Accordance with 10 CFR 2.3900FP:FL_L-201 5-18910 CFR 50.90October 6, 2015U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, D.C. 20555-0001 Re: Turkey Point Nuclear Plant, Units 3 and 4Docket Nos. 50-250 and 50-251License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement Pursuant to 10 CFR 50.90, Florida Power & Light Company (FPL) hereby requests a licenseamendment to revise the technical specifications (TS) for Turkey Point Units 3 and 4. Theproposed change revises the end-of-life moderator temperature coefficient (MTC) surveillance requirement 4.1.1.3.b for Turkey Point Units 3 and 4 by placing a set of conditions on reactorcore operation, which if met, would allow exemption from the required MTC measurement.
The Enclosure to this letter provides FPL's evaluation of the proposed changes and contains sixattachments.
Attachment 1 to the enclosure provides a markup of the TS showing the proposedchange, and the clean TS page containing the proposed change is included in Attachment 2.Included in Attachment 3 for information only is a proposed change to the Core Operating LimitsReport.Beaver Valley Power Station (BVPS), Farley Nuclear Plant (FNP), and Vogtle ElectricGenerating Plant (VEGP) previously submitted similar license amendment requests (LARs) andreceived requests for additional information (RAI) from the NRC regarding the LARs. Therefore, FPL has included responses to the RAI questions as they relate to the Turkey Point LAR inAttachment 4, FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary),
andAttachment 5, FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary).
Attachment 4 contains information proprietary to Westinghouse Electric
: Company, LLC and issupported by an affidavit in Attachment 6 signed by Westinghouse, the owner of the information.
The affidavit sets forth the basis on which the information may be withheld from publicdisclosure and addresses with specificity the considerations listed in paragraph (b)(4) of Section2.390 of the Commission's regulations.
Accordingly, it is respectfully requested that theinformation which is proprietary to Westinghouse be withheld from public disclosure inaccordance with 10 CFR 2.390. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference Florida Power & Light company9760 SW 344th St., Florida City, FL 33035 L-201 5-189Page 2 of 2CAW-15-4156 and should be addressed to James A. Gresham,
: Manager, Regulatory Compliance, Westinghouse Electric
: Company, 1000 Westinghouse Drive, Building 3 Suite 310,Cranberry
: Township, Pennsylvania 16066.As discussed in the evaluation, the proposed change does not involve a significant hazardsconsideration pursuant to 10 CFR 50.92, and there are no significant environmental impactsassociated with the change.The Turkey Point Plant Nuclear Safety Committee (PNSC) has reviewed the proposed licenseamendment.
In accordance with 10 CFR 50.91 (b)(1), a copy of this letter is being forwarded to thedesignee of the State of Florida.There are no new commitments made in this submittal.
FPL requests approval of this amendment request by October 1, 2016 and implementation within90 days.Should you have any questions regarding this submittal, please contact Mr. Mitch Guth,Licensing
: Manager, at 305-246-6698.
I declare under penalty of perjury that the foregoing is true and correct.Executed on October 6, 2015Sincerely, Th'omas Su~mmersSite Vice President Turkey Point Nuclear PlantEnclosure cc: NRC Regional Administrator, Region IINRC Senior Resident Inspector NRC Project ManagerMs. Cindy Becker, Florida Department of Health L-201 5-1 89Enclosure ENCLOSURE Evaluation of the Proposed Change
 
==SUBJECT:==
License Amendment Request 240, Conditional Exemption from End-of-Life Moderator Temperature Coefficient Measurement 1.0 SUMMARY DESCRIPTION 2.0 DETAILED DESCRIPTION 3.0 TECHNICAL EVALUATION 4.0 REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria
 
===4.2 Precedent===
4.3 Significant Hazards Consideration
 
===4.4 Conclusions===
5.0 ENVIRONMENTAL CONSIDERATION
 
==6.0 REFERENCES==
 
Attachment 1 -Markup of Technical Specification PageAttachment 2 -Clean Revised Technical Specification PageAttachment 3 -Change to Core Operating Limits Report (Information Only)Attachment 4 -FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary)
Attachment 5 -FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary)
Attachment 6 -Application for Withholding Proprietary Information from Public Disclosure L-201 5-189Enclosure Page 1 of 91.0 SUMMARY DESCRIPTION The proposed change revises the near-end of iife (EOL) Moderator Temperature Coefficient (MTC) Surveillance Requirement (SR) 4.1.1.3.b for Turkey Point Units 3 and 4 by placing a setof conditions on reactor core operation, which if met, would allow exemption from the requiredMTC measurement.
The conditional exemption will be determined on a cycle-specific basis byconsidering the margin predicted to the SR MTC limit and by the performance of other reactorcore parameters, such as beginning of life (BOL) MTC measurements and the critical boronconcentration as a function of cycle length. The conditional exemption will improve plantavailability and minimize disruptions to normal plant operation with no compromise in plantsafety. No changes to the Technical Specification (TS) Bases will be required as a result of theproposed amendment.
2.0 DETAILED DESCRIPTION WCAP-1 3749-P-A, Safety Evaluation Supporting the Conditional Exemption of the MostNegative EOL Moderator Temperature Coefficient Measurement
[Reference 1], includedsuggested TS markups.
The proposed TS changes are consistent with the WCAP's revisions.
The notation added to the SR references the WCAP. This provides the necessary linkage toensure the MTC prediction satisfies the requisite criteria of WCAP-1 3749-P-A.
The following Note is proposed to be added to SR 4.1.1.3.b:
"Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b may besuspended provided that the benchmark criteria in WCAP-1 3749-P-A and the RevisedPrediction specified in the COLR are satisfied."
3.0 TECHNICAL EVALUATION One of the controlling parameters for power and reactivity increases is the MTC. Therequirements of TS 3.1.1.3, Moderator Temperature Coefficient, ensure that the MTC remainswithin the bounds used in the applicable Updated Final Safety Analysis Report (UFSAR)accident analysis (Chapter 14). This, in turn, ensures inherently stable power operations duringnormal operation and accident conditions.
TS 3.1.1.3 places limits on the MTC, based on the accident analysis assumptions for themoderator density coefficient (MDC). A positive MDC corresponds to a negative MTC. TS3.1.1.3 requires that the MTC be less negative than the specified limit for the all rods withdrawn, EOL, Rated Thermal Power condition.
To demonstrate compliance with the Limiting Condition for Operation (LCO) for the most negative MTC LCO, SR 4.1.1 .3.b requires verification of theMTC after a 300 parts per million (ppm) equilibrium boron concentration is reached.
Becausethe Hot Full Power (HFP) MTC value will gradually become more negative with additional coreburnup and reduction in boron concentration, a 300 ppm MTC surveillance value should be lessnegative than the EOL LCO limit. To account for this effect, the 300 ppm MTC surveillance value is sufficiently less negative than the EOL LCO limit value, to provide assurance that theLCO limit will be met as long as the 300 ppm MTC surveillance criterion is met.
L-201 5-189Enclosure Page 2 of 9Currently, the TS require measurements of MTC at BOL to verify the most positive MTC limit issatisfied and near EOL to verify the most negative MTC limit is satisfied.
At BOL, themeasurement of the isothermal temperature coefficient is relatively simple to perform since it isdone at hot zero power isothermal conditions and is not complicated by changes in the reactorcoolant enthalpy rise or the presence of xenon. The measurement made near-EOL is performed at or near HFP conditions.
MTC measurements at HFP are more difficult to perform due tosmall variations in soluble boron concentration, changes in xenon concentration and distribution, changes in fuel temperature, and changes in reactor coolant enthalpy rise created by smallchanges in the core average power during the measurement.
Changes in each of theseparameters must be accurately accounted for when reducing the measurement data, oradditional measurement uncertainties will be introduced.
Even though these additional uncertainties may be small, the total reactivity change associated with the swing in moderator temperature is also relatively small. The resulting MTC measurement uncertainty created byeven a small change in power level can then become significant and, if improperly accounted for, can yield misleading measurement results.The MTC measurement typically includes time at reduced power as a result of themeasurement procedures.
This measurement introduces a perturbation to normal reactoroperation and increases the potential for a human performance error involving a reactivity manipulation.
An alternate method is proposed to improve availability and minimizeperturbations on normal reactor operation.
The MTC measurement is replaced by a designcalculation of the core MTC if predefined requirements are met.The proposed change would modify the EOL MTC SR by placing a set of conditions on coreoperations.
If these conditions are met, i.e., the specified revised prediction of the MTC andseveral core parameters measured during the cycle are within specified bounds, thesurveillance measurement would not be required to be performed.
The proposed conditional exemption from the HFP near-EOL 300 ppm MTC measurement doesnot impact the safe operation of Turkey Point Units 3 and 4. The safety analysis assumption ofa constant MDC and the actual value assumed will not change. The proposed change uses arevised prediction to determine if the MTC surveillance limit is met. The proposed method forcalculating the revised prediction is consistent with the approved algorithm contained in WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOLModerator Temperature Coefficient Measurement."
The methodology associated with the proposed change was submitted to the NRC inWestinghouse topical report WCAP-13749-P in June 1993. In October 1996, the NRCdetermined the report to be acceptable for referencing in license applications to the extentspecified and under the limitations stated in the Brookhaven Technical Evaluation Report (TER)and the NRC staff's Safety Evaluation Report.The NRC approved WCAP-13749-P-A with two conditions:
"(1) only PHOENIX(/ANC calculation methods are used for the individual plant analysesrelevant to determinations for the EOL MTC plant methodology, and(2) the predictive correction is reexamined if changes in core fuel designs or continued MTCcalculation/measurement data show significant effect on the predictive correction."
L-201 5-189Enclosure Page 3 of 9The FPL resolution to both of these conditions is discussed below.Condition 1Only PHOENIX/ANC calculation methods are used for the individual plant analyses relevantto determinations for the EOL MTC plant methodology.
'FPL Disposition to Condition 1The Turkey Point core design calculations currently are performed with the PHOENIX-P lattice code to generate cross-section data; however, the calculations may eventually transition to those that use the PARAGON lattice code.In Section 4.0, Conditions and Limitations of the NRC's Safety Evaluation (SE) for WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"
(Reference 2), the NRC stated:"1. The PARAGON code can be used as a replacement for the PHOENIX-P latticecode, whenever the PHOENIX-P code is used in NRC approved methodologies."
The NEXUS methodology is a re-parameterization of the PARAGON nuclear data outputand a new reconstruction approach within thecANC core simulator code to simplify the useof this code system for design use. NEXUS has been implemented in the PARAGON/ANC code system for design use. Specifically, the NEXUS methodology has been implemented in the parameterization of PARAGON cross sections for input to ANC and also in ANC toreconstruct those cross sections at specific nodal conditions.
The NEXUS methodology provides a linkage between PARAGON and ANC, establishing a new code system, whilestill using PARAGON.In Section 5.0, Conclusion, of the NRC's SE for WCAP-1 6045-P-A, Addendum 1-A,"Qualification of the NEXUS Nuclear Data Methodology,"
(Reference 3), the NRC stated:"The NRC staff has reviewed the TR submitted by Westinghouse and determined that the NEXUS/ANC code system is adequate to replace the PARAGON/ANC codesystem wherever the latter is used in NRC-approved methodologies."
As discussed above, future core design calculations that are performed using thePARAGON/ANC or NEXUS/ANC system will be equivalent to those performed with thoseusing the PHOENIX/ANC system. The use of PARAGON is consistent with condition (1)above in the NRC SER for WCAP-1 3749-P-A, since it was benchmarked against PHOENIX-P. Similarly, the use of NEXUS is consistent with condition (1) above in the SER for WCAP-13749-P-A, since it was benchmarked against PARAGON (which was benchmarked againstPHOENIX-P).
Therefore the PARAGON and NEXUS codes satisfy the TER requirement todemonstrate the uncertainty limits assumed in WCAP-13749-P-A, as discussed on page 5of the TER. The NRC used this TER as the basis for their SER.
L-201 5-189Enclosure Page 4 of 9For additional information regarding how FPL will meet this Condition, see Attachment 4(proprietary) or Attachment 5 (non-proprietary),
FPL Response to BVPS, FNP and VEGPRAI Questions.
Condition 2The predictive correction is reexamined if changes in core fuel designs or continued MTCcalculation/measurement data show significant effect on the predictive correction.
FPL Disposition to Condition 2Prior to the use of the conditional elimination technique, FPL will confirm that core designchanges and MTC calculation and measurement data do not show a significant effect on thepredictive correction.
The administrative controls for this confirmation will reside in theTurkey Point procedure that controls the EOL MTC surveillance.
If a significant effect isfound, the use of the predictive correction will be re-examined.
All of the core performance benchmark criteria confirmed from startup physics test results,from routine HFP boron concentration measurements, and from flux map surveillances performed during the cycle must be met before the Revised Predicted MTC can becalculated in accordance with the prescribed algorithm contained in Reference
: 1. Anillustration of the benchmark criteria is contained in Table D-1, "Benchmark Criteria forApplication of the 300 PPM MTC Conditional Exemption Methodology,"
in WCAP-13749-P-A.For additional information regarding how FPL will meet this Condition, see Attachment 4(proprietary) or Attachment 5 (non-proprietary).
FPL is using NRC-approved WCAP-1 3749-P-A as the basis for this license amendment request.
FPL will meet all of the technical requirements in the approved WCAP-13749-P-A, butproposes an enhancement to reduce regulatory burden for both the NRC and the licensee.
FPLproposes not to submit a "Most-Negative Moderator Temperature Coefficient Limit Report" tothe NRC, for two reasons.
First, there is an inconsistency in WCAP-1 3749-P-A regarding thetime frame of data collection and the submittal of the Most Negative Moderator Temperature Coefficient Limit Report to the NRC. Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves no apparent technical purpose.
Each of these reasons isdiscussed below.Section 3.3.3 of WCAP-13749-P-A states:"The Technical Specification Bases of the most negative MTC LCO and SR and the valuesof these limits are not altered.
: Instead, a revised prediction is compared to the SR MTC todetermine if the SR limit is met. The revised prediction is simply the sum of the predicted HEP 300 ppm SR MTC plus an AFD correction factor plus a predictive correction term. Thisalgorithm is summarized in Table 3-3."Appendix A of WCAP-13749-P-A requires a new Specification 6.9.1.7 to be added as statedbelow.
L-201 5-189Enclosure Page 5 of 9"6.9.1.7 The most negative MTC limits shall be provided to the NRC RegionalAdministrator with a copy to the Director of Nuclear Reactor Regulation, Attention:
Chief,Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, D. C.20555, at least 60 days prior to the date the limit would become effective unless otherwise approved by the Commission by letter. This report will include the data required for thedetermination of the Revised Prediction of the 300 ppm/ARO/RTP MTC per WCAP-1 3749,"Safety Evaluation Supporting the Conditional Elimination of the Most Negative EOLModerator Temperature Coefficient Measurement",
May, 1993 (Westinghouse Proprietary)."
Since the Most Negative Moderator Temperature Coefficient Limit Report would have to besubmitted at least 60 days before reaching 300 ppm boron concentration, it cannot include the300 ppm data required for determining the Revised Prediction.
To satisfy the Most NegativeModerator Temperature Coefficient Limit Report submittal requirement, the data to be used forcalculating the revised predicted MTC may have to be taken 60 to 90 days prior to reaching 300ppm boron. WCAP-13749-P-A does not provide any method for adjusting the revised predicted MTC to account for data collected 60 to 90 days prior to reaching 300 ppm boron, nor does itprovide justification for using such early data in the calculation.
Therefore, the requirement tosubmit the Most Negative Moderator Temperature Coefficient Limit Report and the requirements for the data that go into the report are inconsistent.
Additionally, the Most Negative Moderator Temperature Coefficient Limit Report serves noapparent technical requirement.
The benchmark criteria and the algorithm in WCAP-1 3749-P-Afor determining the revised predicted MTC will be incorporated into the applicable procedures.
There is no compelling reason that this particular surveillance should require notifying the NRCprior to performing the surveillance procedure.
The exception of not including a "Most Negative Moderator Temperature Coefficient LimitReport" that is contained in WCAP-13749-P-A was approved by the NRC for South Texas Units1 and 2 in Amendment 144 to Facility Operating License No. NPF-76 and Amendment 132 toFacility Operating License No. NPF-80 dated November 26, 2002.The fourth paragraph in Section 3.2.1 of WCAP-1 3749-P-A states:"As part of determining the applicability of a conditional exemption from the near-EOC MTCmeasurement, a cycle-specific figure similar to Figure 3-1 will be provided as part of thatcycle's Technical Specifications or Core Operating Limits Report (COLR)."However, the COLR changes contained in Appendix B, "COLR Revision,"
of WCAP-1 3749-P-Ado not include a reference to Figure 3-1, Example of Predicted HFP ARO 300 ppm MTC VersusCycle Burnup. As a result, FPL proposes referencing the appropriate cycle-specific Figure 3-1,Predicted HFP ARO 300 ppm MTC Versus Cycle Burnup, for Turkey Point and the benchmark criteria in the surveillance procedure associated with the EOL MTC measurement.
The COLRwill contain the algorithm for the Revised Predicted MTC similar to the draft change to the COLRshown in Attachment
: 3.
L-2015-189 Enclosure Page 6 of 94.0 REGULATORY EVALUATION 4.1 Applicable Regulatory Requirements/Criteria
*10 CFR 50.36(c),
"Technical specifications,"
requires Technical Specifications tobe included for the following categories:
(1) Safety limits,/limiting safety system settings, and limiting controlsettings.
(2) Limiting conditions for operation.
(3) Surveillance requirements.
(4) Design features.
(5) Administrative controls.
10 CER 50.36(c)
(3) Surveillance requirements, states:"Surveillance requirements are requirements relating to test, calibration, orinspection to assure that the necessary quality of systems and components ismaintained, that facility operation will be within safety limits, and that the limitingconditions for operation will be met."None of the TS categories are impacted by the proposed TS changes, and SR4.1.1.3.b is not being deleted.
The Bases for and values of the most negativeMTC Limiting Condition for Operation and for the Surveillance Requirement arenot altered.
: Instead, a revised prediction is compared to the MTC Surveillance limit to determine if the limit is met.Therefore, 10 CFR 50.36(c) continues to be met.4.2 Precedent Several license amendments have been approved allowing an alternative to an EOLMTC surveillance test measuring the MTC. The following are approved licenseamendments similar to Turkey Point's request:* NRC letter to FPL Energy Seabrook, LLC, "Seabrook
: Station, Unit No. 1 -Issuance of Amendment RE: Removal of Requirement to Perform End-of-Life Moderator Temperature Coefficient Measurement (TAC No. MC 6566)," February17, 2006, Accession No. ML060040160.
* NRC letter to FirstEnergy Nuclear Operating
: Company, "Beaver Valley PowerStation, Unit Nos. 1 and 2 -Issuance of Amendments Regarding Technical Specification 3.1.3, 'Moderator Temperature Coefficient Measurement' (TACNos. ME9144 and ME9145),"
September 17, 2014, Accession No.ML14245A1 51.* NRC letter to STP Nuclear Operating
: Company,
'South Texas Project, Units 1and 2 -Issuance of Amendments Approving Technical Specification ChangesRevising the End of Life Moderator Temperature Coefficient Surveillance L-201 5-189Enclosure Page 7 of 9Requirements (TAC Nos. MB5160 and MB5161),"
November 26, 2002,Accession No. ML023400252.
Turkey Point's request varies from these amendments because it does not add areference to WCAP-13749-P-A in TS 6.9.1.7, Core Operating Limits Report. Consistent with GL 88-16, WCAP-13749-P-A does not establish a core operating limit. The footnotethat modifies SR 4.1.1 .3.b refers to WCAP-1 3749-P-A, so adding the reference to TS6.9.1.7 would be redundant.
In addition, the TS changes provided in WCAP-1 3749-P-Ado not include a revision to the TS requirements for the COLR. Therefore, FPLdetermined that adding to TS 6.9.1.7 a reference to WCAP 13749-P-A would beredundant and unnecessary.
4.3 Significant Hazards Consideration The proposed changes revise the near-end of life (EOL) Moderator Temperature Coefficient (MTC) Surveillance Requirement (SR) 4.1.1.3.b by placing a set of conditions on reactor core operation, which if met, would allow exemption from the required MTCmeasurement.
The conditional exemption will be determined on a cycle-specific basisby considering the margin predicted to the surveillance requirement MTC limit and theperformance of other reactor core parameters, such as beginning of life (BOL) MTCmeasurements and the critical boron concentration as a function of cycle length.As required by 10 CFR 50.91(a),
FPL has evaluated the proposed changes to theTurkey Point TS using the criteria in 10 CFR 50.92 and has determined that theproposed changes do not involve a significant hazards consideration.
An analysis of theissue of no significant hazards consideration is presented below:1: Does the proposed amendment involve a significant increase in the probability orconsequences of an accident previously evaluated?
Response:
NoThe safety analysis assumption of a constant moderator density coefficient andthe actual value assumed are not changing.
The Bases for and values of themost negative MTC Limiting Condition for Operation and for the Surveillance Requirement are not changing.
: Instead, a revised prediction is compared to theMTC Surveillance limit to determine if the limit is met.The proposed changes to the TS do not affect the initiators of any analyzedaccident.
In addition, operation in accordance with the proposed TS changesensures that the previously evaluated accidents will continue to be mitigated asanalyzed.
The proposed changes do not adversely affect the design function oroperation of any structures,
: systems, and components important to safety.The probability or consequences of accidents previously evaluated in the UFSARare unaffected by this proposed change because there is no change to any L-201 5-1 89Enclosure Page 8 of 9equipment response or accident mitigation scenario.
There are no new oradditional challenges to fission product barrier integrity.
Therefore, it is concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2: Does the proposed amendment create the possibility of a new or different kind ofaccident from any accident previously evaluated?
Response:
NoThe proposed changes do not involve a physical alteration of the plant (no newor different type of equipment will be installed).
The proposed changes do notcreate any new failure modes for existing equipment or any new limiting singlefailures.
Additionally the proposed changes do not involve a change in themethods governing normal plant operation and all safety functions will continueto perform as previously assumed in accident analyses.
Thus, the proposedchanges do not adversely affect the design function or operation of anystructures,
: systems, and components important to safety.No new accident scenarios, failure mechanisms, or limiting single failures areintroduced as a result of the proposed changes.
The proposed changes do notchallenge the performance or integrity of any safety-related system.Therefore, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
3: Does the proposed amendment involve a significant reduction in a margin ofsafety?Response:
NoThe margin of safety associated with the acceptance criteria of any accident isunchanged.
The proposed change will have no affect on the availability, operability, or performance of the safety-related systems and components.
Achange to a surveillance requirement is proposed based on an alternate methodof confirming that the surveillance is met. The Technical Specification LimitingCondition for Operation limits are not being changed.The proposed change will not adversely affect the operation of plant equipment or the function of equipment assumed in the accident analysis.
Therefore, it is concluded that the proposed change does not involve a significant reduction in a margin of safety.Based upon the above analysis, FPL concludes that the proposed amendment does notinvolve a significant hazards consideration',
under the standards set forth in 10 CFR L-201 5-189Enclosure Page 9 of 950.92(c),
"Issuance of Amendment,"
and accordingly, a finding of "no significant hazardsconsideration" is justified.
 
===4.4 Conclusions===
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation inthe proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical tothe common defense and security or to the health and safety of the public.5.0 ENVIRONMENTAL CONSIDERATIONS A review has determined that the proposed amendment would change a requirement withrespect to installation or use of a facility component located within the restricted area, as definedin 10 CER Part 20, or would change an inspection or surveillance requirement.
: However, theproposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be releasedoffsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion setforth in 10 CFR 51 .22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b),
no environmental impactstatement or environmental assessment need be prepared in connection with the proposedamendment.
 
==6.0 REFERENCES==
: 1. WCAP-1 3749-P-A, "Safety Evaluation Supporting the Conditional Exemption of theMost Negative EOL Moderator Temperature Coefficient Measurement,"
March 1997.2. WCAP-1 6045-P-A, "Qualification of the Two-Dimensional Transport CodePARAGON,"
August 2004.3. WCAP-1 6045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear DataMethodology,"
August 2007.
L-2015-1 89Attachment 1Attachment 1Markup of Technical Specification Page REACTIVIT CONDTROL SYSTOEMSIO LIMITING CONDITION FOR OPERATION ACTION:(Continued)
: b. With the MTC more negative than the EOL limit specified in the COLR, be in HOT SHUTDOWNwithin 12 hours.SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior toinitial operation above 5% of RATED THERMAL POWER, after each fuel loading; andrlb. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppmlsurveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppmZ In theevent this comparison indicates the MTC is more negative than the 300 ppm surveillance limitspecified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limitspecified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.* Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b mayIbe suspended provided that the benchmark criteria in WCAP-13749-P-A and theRevised Prediction specified in the COLR are satisfied.
TURKEY POINT-UNITS3&4 314 1-5TUREYPIN-UNTS34
/4 -5AMENDMENT NOS. 260 AND 2-6 1' L-2015-189 Attachment 2Attachment 2Clean Revised Technical Specification Page REACTIVIT CONDTROL SYSTOEMSIO LIMITING CONDITION FOR OPERATION ACTION:(Continued)
: b. With the MTC more negative than the EOL limit specified in the COLR, be in HOT SHUTDOWNwithin 12 hours.SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:a. The MTC shall be measured and compared to the BOL limit specified in the COLR, prior toinitial operation above 5% of RATED THERMAL POWER, after each fuel loading; andb. The MTC shall be measured at any THERMAL POWER and compared to the 300 ppmsurveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWERcondition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm*. In theevent this comparison indicates the MTC is more negative than the 300 ppm surveillance limitspecified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limitspecified in the COLR, at least once per 14 EFPD during the remainder of the fuel cycle.* Measurement of the MTC in accordance with Surveillance Requirement 4.1.1.3.b may be suspended providedthat the benchmark criteria in WCAP-13749-P-A and the Revised Prediction specified in the COLR are satisfied.
TURKEY POINT -UNITS 3 & 4 3415AEDETNS N3/4 1-5AMENDMENTNOS.
AND L-201 5-1 89Attachment 3Attachment 3Change to Core Operating Limits Report(Information Only)
EC 279407PTN-3F.JF-13-080 Rev. 02.5 Moderator temperature coefficient (MTC) (TS 3.1.1.3)<+ 5.0 x 10"5 Ak/k/&deg;FBOL, HZP, ARO and,from HZP to 70% Rated Thermal Power (RTP)From 70% RTP to 100% RTP the MTCdecreasing linearly from _< + 5.0 x 10s Ak/k/&deg;Fto _< 0.0 x 10"s Ak/k/0FLess negative than -41.0 x 1 0. Ak/k/&deg;FEOL, RTP, ARO2.6 Moderator temperature coefficient (MTC) Surveillance at 300 ppm (TS 4.1.1.3)-Less negative than -35.0 x 1 0" Ak/k/&deg;FWithin 7 EFPD of reachingequilibrium boron concentration of300 ppm.2.7 Analog Rod Position Indication System (TS 3.1.3.2)-Figure A3 (page 14A-A9)The All Rods Out (ARO) position for all shutdown Banks andControl Banks is defined to be 230 steps withdrawn.
2.8 Control Rod Insertion Limits (TS 3.1.3.6)-Figure A3 (page 14A-A9)The control rod banks shall be limited in physical insertion asspecified in Figure A3 for ARO = 230 steps withdrawn.
2.9 Axial Flux Difference (TS 3.2.1)-Figure A4 (page 14A-A10)2.10 Heat Flux Hot Channel Factor FQ(Z) (TS 3.2.2)-[Fo]L= 2.30-K~) =1.0Fo 1'4A-A1'wer5 i oe egt nf14A-A5 Insert 1The Revised Predicted near -EOL 300 ppm MTC shall be calculated using the algorithm contained in WCAP-1 3749-P-A:
Revised Predicted MTC = Predicted MTC + AFD Correction
-3 PCM/degree FIf the Revised Predicted MTC is less negative than the SR 4.1.1.3.b 300 ppm surveillance limitand all the benchmark data contained in the surveillance procedure are met, then an MTCmeasurement in accordance with SR 4.1.1.3.b is not required to be performed.
L-201 5-189Attachment 5Attachment 5FPL Response to BVPS, FNP and VEGP RAI Questions (Non-Proprietary)
L-201 5-189Attachment 5Page 1 of 10BVPS RAI Question 1:In accordance with the second condition in the NRC staff's safety evaluation for WCAP-13749-P-A, the licensee proposed to confirm, on a cycle-specific basis, that core fueldesign changes or data from MTC predictions and measurements do not show asignificant effect on the predictive correction.
Please clarify the process and criteria formaking this determination and justify their adequacy (e.g., statistical
: testing, engineering
: judgment, etc.).Response:
As described in WCAP-13749-P-A, "Safety Evaluation Supporting the Conditional Exemption ofthe Most Negative EOL Moderator Temperature Coefficient Measurement,"
approved in March1997, the HFP predictive correction accounts for the observed differences between themeasured and predictive (M-P) MTCs. "The hot full power (HFP) predictive correction
([]o)was "derived by summing the hot zero power (HZP) predictive correction, the xenonsensitivity and the burnup sensitivity."
The HZP predictive correction is provided in WCAP-13749-P-A.
As long as the beginning of life (BOL) HZP MTC (M-P) is less negative than theHZP predictive correction, the HFP predictive correction is valid for use during the cycle.*Tables 1 and 2 provide Beginning-of-Life (BOL) HZP Isothermal Temperature Coefficient (ITC)measured values (ITC M), predicted values (ITC P), and the measured minus the predicted values (M-P) for each cycle listed for Turkey Point Unit 3 and Unit 4. The ITC M for both units isconsistently more positive than ITC P, and therefore is conservative for evaluating the continued use of the HFP predictive correction value of [ ]ac Note that the BOL HZP ITC datawas included instead of BOL HZP MTC data as the measured BOL HZP MTC is just thepredicted BOL HZP Doppler Temperature Coefficient (DTC) subtracted from the measured BOLHZP ITC. Therefore, the same M-P value will be calculated for the BOL HZP MTC and BOLHZP ITC data sets. Thus, the conclusion that the HFP predictive correction is valid for useduring the Turkey Point Unit 3 and Unit 4 cycles is still valid.Table 1: Turkey Point Unit 3 BOL HZP ITC Data (all values in pcm/&deg;F)
L-201 5-189Attachment 5Page 2 of 10Table 2: Turkey Point Unit 4 BOL HZP ITC Data (all values in pcm/&deg;F)Cycle ITC M ITC P (M-P)26 -0.337 [ ]a,c [ ]a,c27 -1.456 [ ]a,c [ ]a,c28 -0.821 [ ]a~c [ ]a,cWCAP-13749-P-A states, "...the (HFP) predictive correction is reexamined if changes in corefuel designs or continued MTC calculation/measurement data show significant effect on thepredictive correction."
Duping the Turkey Point core design process for each cycle, FPL wouldverify that the predictive correction remains valid for the applicable fuel cycle by performing thefollowing two qualitative assessments.
: 1. FPL would identify fuel and core design methodology changes as part of the fueldesign process.
Prior to each reload, a reload risk evaluation checklist is used toidentify and determine the risk of major fuel design changes or core designmethodology changes.
This checklist would identify whether the reload will use*revised or different methodologies, and assesses the impact of these changes on theexisting analyses.
This evaluation would provide initial indication of a possiblechange in the BOL HZP MTC (M-P) relationship prior to startup of the fuel cycle.2. Per TS 3.1 .1.3, each cycle during low power physics testing, FPL measures the BOLHZP MTC. Prior to each conditional exemption of the end of life (EOL) HFP MTCmeasurement test, FPL would compare Turkey Point specific MTC (M-P) data eachcycle against previous cycles to determine if there is a change to the measured vs.predicted MTC relationship.
If the value of the BOL HZP MTC (M-P) approaches the HZP predictive correction given inWCAP-1 3749-P-A then FPL would evaluate the use of the HFP MTC predictive correction toshow that the value of [ ja,c is conservative or measure the EOL HFP MTC inaccordance with the Technical Specifications.
The above tools and assessments would beused each cycle during and after a transition to NEXUS/ANC9 (PARAGON) to verify continued consistency and validity of the BOL HZP MTC (M-P) relationship as it pertains to the predictive correction of WCAP-1 3749-P-A.
BVPS RAI Question 2:The predictive correction term defined in WCAP-1 3749-P-A is based, in part, on atolerance limit that Westinghouse derived from differences between a set of measuredand predicted values of the MTC at the beginning of an operating cycle at hot, zero-power conditions.
Specifically, the predicted MTC values in WCAP-1 3749-P-A weredetermined from calculations using the PHOENIX-P/ANC code package for a variety ofpressurized-water reactor (PWR) core designs prior to 1995. Although the NRC staff hasapproved the PARAGON lattice physics code as a replacement to PHOENIX-P, it cannot L-201 5-189Attachment 5Page 3 of 10not be concluded that the statistical
: database, and hence the predictive correction terms,for the two codes will be equivalent.
Therefore, if approval for the use of the predictive correction term derived for the PHOENIX-P code for calculations with the PARAGONcode is sought under this license amendment
: request, please provide unbiased andstatistically significant data analogous to that reported in Table 3-1 of WCAP-13749-P-A for calculations performed with the PARAGON code for contemporary PWR coredesigns, along with: (1) justification that this data belongs to the same population as thepre-1995 data in WCAP-1 3749-P-A, generated with the PHOENIX-P code; or (2) a newpredictive correction term for the PARAGON code for contemporary cores that is basedon a 95195 tolerance limit appropriate for modifying end-of-cycle MTC predictions madewith this code.Response:
A database of plants is used for regression testing and continued qualification of core designsystem code releases.
This database consists of multiple cycles of plants chosen to encompass the variety of plant, fuel lattice types, and fuel management strategies that the code will be usedto analyze.
Comparison of the results for any release with those of previous releases assurescontinued compliance of the code with its licensing basis.This set of contemporary PWR cores has been selected as representative of the statistical database used in WCAP-13749-P-A.
These cores have been modeled using both PHOENIX-P/ANC and NEXUS/ANC (the NEXUS cross-section generation system uses PARAGON as thelattice transport code).Table I below lists data analogous to that reported in Table 3-1 of WCAP-1 3749-P-A forcalculations performed with NEXUS/ANC.
Benchmarks for both PHOENIX-P/ANC andNEXUS/ANC are listed in the table to show a comparison between the two code sets. MeasuredEnd-Of-Cycle (EOC) Hot Full Power (HEP) Moderator Temperature Coefficient (MTC) data isnot readily available for most of the benchmark cores, and therefore, for this parameter, measured-minus-predicted data was only provided for Turkey Point for PHOENIX-P/ANC.
Additionally, Beginning-of-Cycle (BOC) Hot Zero Power (HZP) Isothermal Temperature Coefficient (ITC) data was included instead of BOC HZP MTC data as the measured BOC HZPMTC is just the predicted BOC HZP Doppler Temperature Coefficient (DTC) subtracted from themeasured BOC HZP ITC.The results in Table 1 show that[]a,c Using the measured-minus-predicted values in Table 1, the predictive correction term fromWCAP-1 3749-P-A[
]aCUsing commercial statistics
: software, the BOC HZP ITC M-P data points in Table 1 have beendemonstrated to fall within a normal distribution per the Anderson-Darling and Ryan-Joiner tests, with a M-P mean of [ ]a~c pcm/OF and a standard deviation of [ ]a~ pcm/OF. Fromthis data, a 95/95 one-sided tolerance limit for the HZP predictive correction of [ ]a'c pcm/OFcan be calculated using a K-value of []~
L-201 5-189Attachment 5Page 4 of 10Applying[
]a.c from WCAP-1 3749-P-A
[ ]a.C yields a HFP predictive correction of [ ]a,c pcm/OF.[]a,cAdditionally, the predictive correction term for PHOENIX-P/ANC was recalculated forcomparison (for contemporary cores). [ ]a,cusing the K-value of [ ]a~C a HZP Predictive'correction of [ ]a,c pcm/OF wascalculated.[
]a.c yields a HFP predictive correction of [ ]a~c pcm/OF.[]a~c This shows that: (1) the PHOENIX-P/ANC results inWCAP-13749-P-A are reproducible with the contemporary PWR cores and latest code versions, and (2) the set of cores chosen represents a good unbiased sample of the larger data set usedin WCAP-1 3749-P-A.
L-201 5-189Attachment 5Page 5 of 10Table 2: Summary of Statistics for Measured Minus Predicted Differences of Criticalboron, ITC, MTC, and Rod Worths for Westinghouse CoresPHOENIX-PIANC NEXUSIANC Mean Std. 0ev. Mean Std. Dev.NO.Pts. -a,cParameter Farlev and Vogitle RAI Question 1:On December 28, 2012, the NRC issued requests for additional information (RAIs) for asimilar license amendment request (LAR) at Beaver Valley Power Station (BVPS). InEnclosure 9, SNC provided their responses to. these RAIs. Table I of Enclosure 9provides a summary of statistics to compare PHOENIX-PIANC and NEXUSIANC results.Though the PHOENIX-PIANC and NEXUSIANC results compare favorably to each other,they appear to differ significantly from the values found in Table 3-1 of WCAP-1 3749-P-A.
Please discuss this discrepancy.
In this discussion, emphasis should be placed on the differences in the means andstandard deviations between the two tables, particularly for the end-of-cycle (EOC) hotfull power (HFP) moderator temperature coefficient (MTC). The discussion shouldpresent a statistical analysis of the datasets used to generate the two tables to explainwhether or not the results presented belong to the same population.
"The discussion should also address the deviation between measured and predicted critical boron throughout the cycle. Based on the statistics
: provided, many of thecalculated values would apparently violate the generally-used acceptance criterion of +50 ppm for comparison to measurements (as discussed in ANSI/ ANS-19.6.1, thePARAGON topical report WCAP-1 6045-P-A, and others).
L-201 5-189Attachment 5Page 6 of 10ResponseResponse to Paragraphs 1 and 2The plants and cycles used for benchmarking Westinghouse PWR nuclear analysis methodsare continuously updated to reflect the changes that occur in fuel management and operations.
Westinghouse does not use one single consistent set of plant/cycles for code qualification, because that would restrict the validation basis to include only old operating cycles that do notreflect today's modern fuel designs, power uprates, increased fuel burnups, and longer cycleswith higher operating capacity factors.Table 3-1 in WCAP-13749-P-A compares the measured to predicted EOL HFP MTC. The Table3-1 results show a mean difference of [ ]a~ pcm/OF and a standard deviation of [ ]a,cpcm/&deg;F based on [ ]a~c data points. Based on RAls received for the EOL MTC topical report,additional data was also provided in Section G, Table 2 of that topical report. The EOC HFPMTC data is expanded to include [ ]a~c data points with a mean difference of [ ]a~c pcm/OFand a standard deviation of [ ]a~ pcm/OF.The response to BVPS RAl Question 2 compared recent NEXUS/ANC code system predictions to recent PHOENIX-P/ANO code system predictions to establish the similarity of predictions forMTC and ITO between the two code systems.
The data presented was from the qualification ofthe NEXUS/ANC code system, so it used the more recent plant/cycle data used in that codesystem qualification.
: However, EOL HFP MTC comparisons of measured and predicted datawere not available for this qualification effort, so only comparisons of predictions for EOL HFPMTO between the NEXUS/ANC and PHOENIX-P/ANC code systems were presented.
Thesecomparisons demonstrate the predictive capability for the NEXUS/ANC code system iscomparable to the predictive capability for the PHOENIX-P/ANC code system.Table 1 in the response to BVPS RAI Question 2 provides the ITO and MTO comparisons.
Using the more recent plant/cycle data, the BOO, HZP ITO predictions from [ ]a~c data pointsusing the PHOENIX-P/ANC code system show a mean difference of [ ]a~c pcm/OF and astandard deviation of [ ]a~c pcm/OF. This code performance is comparable to the datapresented in the EOL MTC topical report. The comparable NEXUS/ANC code system datashows a mean difference of [ ]a~c pcm/OF and a standard deviation of [ ]a,c pcm/OF. TheNEXUS/ANC code system appears to be slightly more accurate for BOO, HZP ITO predictions c'ompared to the PHOENIX-P/ANC code system, although the differences are relatively small. Absolute comparisons of predicted EOL, HFP MTC are also presented in that table forboth code systems to again demonstrate the similarity of the predictions.
These are notmeasured minus predicted comparisons, but just comparisons of absolute MTC predicted values. For the PHOENIX-P/ANC code system, the mean prediction is [ ]a~ pcm/OF with astandard deviation of [ ]a~ pcm/OF. For the NEXUS/ANO code system the mean prediction is[]a,c pcm/OF with a standard deviation of [ ]a'c pcm/OF. This comparison again demonstrates that the code systems provide comparable predictive capability, so the conclusions of the EOLMTC topical report, WCAP-1 3749-P-A would not change based on substitution of the NEXUScode system for the PHOENIX-P/ANC code system.Some comparisons of PHOENIX-P/ANC code system predictions of EOL HFP MTC tomeasurements are also provided to illustrate that data comparisons using more recentplant/cycles
.show behavior that is as good as or better than that presented in the EOL MTC L-201 5-189Attachment 5Page 7 of 10measurement elimination topical report, WCAP-13749-P-A.
The more recent PHOENIX-PIANC code system EOL, HFP MTC measured to predicted comparisons show a mean difference of[]a,c pcm/OF and a standard deviation of [ ]a,c pcm/OF. These comparisons show somewhatbetter performance compared to the EOL MTC measurement elimination topical report, WCAP-13749-P-A, but are also taken from a smaller set of plant cycles, where [ ]a.C plant cyclesare presented.
Based on the close agreement between PHOENIX-PIANO and NEXUS/ANC, asdescribed above, comparable measured to predicted statistics for the EOL HFP MTC areexpected when the predictions are based on NEXUS/ANC.
Response to Paraciraph 3Regarding the question on deviation between measured and predicted critical boronconcentrations throughout the cycle, the measured data includes the effects of boron-i10 (108)depletion in the coolant during the cycle, while the predictions assume the nominal (no 1&deg;Bdepletion) 1&deg;B fractions.
During operation, the 1&deg;B in the coolant will deplete due to exposure toneutron flux from the reactor core. As a result, the measured concentration at the middle of thecycle will be higher to maintain critical conditions than if no 1&deg;B depletion occurred.
Westinghouse chose to present the comparison data without accounting for depletion effects inthe predictions, since we do not have access to the actual measured 10B fractions for all of thecycles where we compare it to measured data. The effect of 1&deg;B depletion is largest at themiddle of cycle, where the measured concentrations are typically 50-100 ppm higher than if no108 depletion were occurring.
Based on Westinghouse's experience with modeling 1&deg;B depletion when the data is available, accounting for this effect would significantly reduce the mean error inthe presented MOO data such that it would compare with or be better than previously reportedperformance statistics.
To illustrate this point, two plant cycles were simulated to predict the effects of 1&deg;B depletion inthe coolant.
One is a three loop plant and the other is a four loop plant. The three loop plantshows that accounting for l&deg;B depletion increased the MOC boron concentration by [ ]a,c ppm,while the four loop result is a [ ]a,c ppm increase in predicted boron. These results areconsistent with the reported MOO difference in boron concentration where l&deg;B depletion effectswere not included in the predictions.
L-2015-1 89Attachment 5Page 8 of 10a.caocResponse Conclusion In conclusion, the plants/cycles chosen for code validation are always being updated as newdata from more recent, modern core and fuel design become available.
A comparison of thecode performance for MTC predictions shows a general improvement over time. TheNEXUS/ANC code system also shows slightly better performance compared to the olderPHOENIX-P/ANC code system. As such, the conclusions of the EOL MTC measurement elimination topical report, WCAP-1 3749-P-A remain applicable when either code system isused.
L-201 5-189Attachment 5Page 9 of 10Farley and Vogitle RAI Question 2"The LAR states that the 'FNP [Farley Nuclear Plant] and VEGP [Vogtle Electric Generating Plant] core design calculations are currently being transitioned from nuclear calculations that are performed with the PHOENIX-P lattice code to generate cross-section data tothose that will be performed with the PARAGON lattice code.' Farley TS 5.6.5.b, the CoreOperating Limits Report (COLR) reference list, includes references for PHOENIX-P aswell as the PARAGON and NEXUS methodologies.
Vogtle TS 5.6.5.b, on the other hand,does not include any of these references.
In both sites' TS, WCAP-9272-P-A,
'Westinghouse Reload Safety Evaluation Methodology' is referenced for calculation of the moderator temperature coefficient.
WCAP-9272 states that 'the values of all measured parameters are calculated using thedesign codes described in Table 3.1.' Table 3.1 is a list of older neutronics codes, suchas LEOPARD and TURTLE, which were in use at the time when WCAP-9272-P-A was firstpublished in 1978. While the Vogtle and Farley Final Safety Analysis Reports (FSARs)include references to these older codes as well as newer codes like PHOENIX-P andANC, they both indicate that the newer codes are used for core design.a. Please discuss how WCAP-9272-P-A is being used for calculation of the MTClimits for TS 3.1.3 when the codes being used for design are not part of theWCAP-9272-P-A methodology.
: b. Please provide a justification for why the COLR reference list for Vogtle doesnot need to be updated to include PHOENIX-P,
: PARAGON, andlor NEXUS.This is especially pertinent given that Farley submitted an LAR on August 14,2012 (ADAMS Accession No. ML 12227A884),
specifically to include NEXUS intheir COLR reference list.Response to a.WCAP-9272-P-A is currently being used at Turkey Point Units 3 and 4 for the calculation of theModerator Temperature Coefficient (MTC) limits, as is currently identified in TS 6.9.1.7 for eachof those plants. As noted in the RAl, the computer codes cited in WCAP-9272-P-A, LEOPARDand TURTLE have been superseded by newer codes, specifically PHOENIX-P and ANC, ascorrectly described in the Turkey Point Units 3 and 4 ESARs. ANC was approved by the NRCvia WCAP-1 0965-P-A, which states: "The intended usage of the Advanced Nodal Codeencompasses all applications described in the reload safety evaluation methodology topicalreport. [3]", where [3] refers to WCAP-9272-P-A.
The NRC then approved the use of PHOEN IX-P and ANC based on qualification work that was documented in WCAP-1 1596-P-A, whichincorporates WCAP-1 0965-P-A by reference.
This reference (WCAP-1 1596-P-A) thus supportsthe use of PHOENIX-P and ANC in lieu of LEOPARD and TURTLE.Similarly, Westinghouse recently developed the NEXUS/PARAGON code suite for use withANC and received NRC approval for its use in core design work via WCAP-1 6045-P-A andWCAP-16045-P-A, Addendum 1-A. These approvals support this application and provide thenecessary benchmarking data to support Turkey Point Units 3 and 4 transitioning toNEXUS/PARAGON in the future.
L-201 5-189Attachment 5Page 10 of 10The supporting Safety Evaluation Report for WCAP-9272-P-A acknowledges that "significant changes to codes and methods are extensively documented in topical reports to the NRC staffin order that generic approval be obtained."
: Likewise, as updated codes and methods areapproved and used in reactor core designs they follow the design guideline provided in WCAP-9272-P-A and incorporated into the design using 10 CFR 50.59 because they are previously approved methods.Response to b.Similarly, like Vogtle, Turkey Point also does not include PHOENIX-P in the list of COLRmethodologies.
As stated, PHOENIX-P has been generically approved.
When the PHOENIX-P method and other updated codes and methods are generically approved they can beincorporated into the plant's design using 10 CFR 50.59. Furthermore, these methods are toolsused to confirm that reload parameters are bounded by the values used in the safety analysis.
These tools are not methodologies used to calculate core operating limits. As such, TurkeyPoint does not propose to add PHOENIX-P, PARAGON,-or NEXUS to the listed COLRreferences in the technical specifications.
L-2015-1 89Attachment 6Attachment 6Application for Wi.thholding Proprietary Information from Public Disclosure We in houseWestinghouse Electric Company0 Engineering, Equipment and Major Projects1000 Westinghouse Drive, Building 3Cranberry
: Township, Pennsylvania 16066USAU.S. Nuclear Regulatory Commission Direct tel: (412) 374-4643Document Control Desk Direct fax: (724) 940-856011555 Rockville Pike e-mail: greshaja@
westinghouse.corn Rockville, MD 20852 Proj letter: NF-NEXT-15-74 CAW- 15-4 156April 7, 2015APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
 
==Subject:==
 
Turkey Point Units 3 and 4,Docket Nos. 50-250 and 50.251,License Amendment Request 240,Conditional Exemption from End-of Life Moderator Temperature Coefficient Measurement, FPL Response to BVPS, FNP and VEGP RAI Questions (Proprietary)
The proprietary information for which withholding is being requested in the above-referenced documentis further identified in Affidavit CAW-15-4156 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The Affidavit, which accompanies this letter, sets forth the basison which the information mnay be withheld from public disclosure by the Commission and addresses withspecificity the considerations listed in paragraph (b)(4) of 10 CER Section 2.390 of the Commission's regulations.
Accordingly, this letter authorizes the utilization of the accompanying Affidavit by Florida Power andLight Company (FPL).Correspondence with respect to the proprietary aspects of the Application for Withholding or theWestinghouse Affidavit should reference CAW-15-41 56, and should be addressed to James A. Gresham,Manager, Regulatory Compliance, Westinghouse Electric
: Company, 1000 Westinghouse Drive,Building 3 Suite 310, Cranberry
: Township, Pennsylvania 16066.Very truly yours,/James A. Gresham, ManagerRegulatory Compliance CAW-l 5-4 156April 7, 2015AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
SSCOUNTY OF BUTLER:I, James A. Gresham, am authorized to execute this Affidavit on behalf of Westinghouse ElectricCompany LLC (Westinghouse),
and that the averments of fact set forth in this Affidavit are true andcorrect to the best of my knowledge, information, and belief.
A Gr~esham, angeRegulatory Compliance 22 CAW- 15-4156(1) I am Manager, Regulatory Compliance, Westinghouse Electric Company LLC (Westinghouse),
and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plantlicensing and rule making proceedings, and am authorized to apply for its withholding on behalfof Westinghouse.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of theCommission's regulations and in conjunction with the Westinghouse Application for Withholding Proprietary Information from Public Disclosure accompanying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether theinformation sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned and has been heldin confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and notcustomarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information inconfidence.
The application of that system and the substance of that system constitute Westinghouse policy and provide the rational basis required.
Under that system, information is held in confidence if it falls in one or more of severaltypes, the release of which might result in the loss of an existing or potential competitive advantage, as follows:(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of 33 CAW-I15-41 56Westinghouse's competitors without license from Westinghouse constitutes acompetitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (orcomponent, structure, tool, method, etc.), the application of which data secures acompetitive economic advantage, e.g., by optimization or improvedmarketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve hiscompetitive position in the design, manufacture,
: shipment, installation, assurance of quality, or licensing a similar product.(d) It reveals cost or price information, production capacities, budget levels, orcommercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer fundeddevelopment plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(iii) There are sound policy reasons behind the Westinghouse system which include thefollowing:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure toprotect the Westinghouse competitive position.
(b) It is information that is marketable in many ways. The extent to which suchinformation is available to competitors diminishes the Westinghouse ability tosell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage byreducing his expenditure of resources at our expense.
44 CAW-15-4156 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage.
Ifcompetitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of acompetitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence ofWestinghouse in the world market, and thereby give a market advantage to thecompetition of those countries.
(f) The Westinghouse capacity to invest corporate assets in research anddevelopment depends iupon thle success in obtaining and maintaining acompetitive advantage.
(iv) The information is being transmitted to the Commission in confidence and, under theprovisions of 10 CFR Section 2.390, it is to be received in confidence by theCommission.
(v) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method tothe best of our knowledge and belief.(vi) The proprietary information sought to be withheld in this submittal is that which isappropriately marked in "Turkey Point Units 3 and 4, Docket Nos. 50-250 and 50-251,License Amendment Request 240, Conditional Exemption from End-of Life Moderator Temperature Coefficient Measurement, FPL Response to BIVPS, FNP and VEGP RAIQuestions" (Proprietary),
for submittal to the Commission, being transmitted by FloridaPower and Light Company (FPL) letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted by Westinghouse is that associated with FPL's request for NRCapproval of a License Amendment Request that would allow a change to the TurkeyPoint Units 3 and 4 Technical Specifications to provide a conditional exemption fromModerator Temperature Coefficient measurement, and may be used only for that purpose.
55 ~CAW- 15-4156(a) This information is part of that which will enable Westinghouse to:(i) Assist FPL with Obtaining NRC approval of' a License Amendment Request that would allow a change to the Technical Specifications toprovide a conditional exemption from Moderator Temperature Coefficient measurement.
(ii) Provide Results of customer specific calculations.
(iii) Provide licensing support for customer submittals.
(b) Further this information has substantial commercial value as follows:(i) Westinghouse plans to sell the use of similar information to its customers for the purpose of meeting NRC requirements for licensing documentation associated with End of Life Moderator Temperature Coefficient Elimination submittals.
(ii) Westinghouse can sell support and defense of industry guidelines andacceptance criteria for plant-specific applications.
(iii) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.
*Public disclosure of this proprietary information is likely to cause substantial harm to thecompetitive position of Westinghouse because it would enhance the ability ofcompetitors to provide similar technical evaluation justifications and licensing defenseservices for commercial power reactors without commensurate expenses.
Also, publicdisclosure of the information would enable others to use the information to meet NRCrequirements for licensing documentation without purchasing the right to use theinformation.
6 CAW-15-4156 The development of the technology described in part by the information is the result ofapplying the results of many years of experience in an intensive Westinghouse effort andthe expenditure of a considerable sum of money.In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower:
effort, having therequisite talent and experience, would have to be expended.
Further the deponent sayeth not.
PROPRIETARY INFORMATION NOTICETransmitted herewith are proprietary and non-proprietary versions of documents furnished to the NRCassociated with FPL' s request for NRC approval of a License Amendment Request that would allow achange to the Turkey Point Units 3 and 4 Technical Specifications to provide a conditional exemption from Moderator Temperature Coefficient measurement, and may be used only for that purposeIn order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning theprotection of proprietary information so submitted to the NRC, the information which is proprietary in theproprietary versions is contained within brackets, and where the proprietary information has been deletedin the non-proprietary
: versions, only the brackets remain (the information that was contained within thebrackets in the proprietary versions having been deleted).
The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f)located as a superscript immediately following the brackets enclosing each item of information beingidentified as proprietary or in the margin opposite such information.
These lower case letters refer to thetypes of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the Affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).
COPYRIGHT NOTICEThe reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted tomake the number of copies of the information contained in these reports which are necessary for itsinternal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment,
: transfer, renewal, modification, suspension, revocation, or violation of a license,permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on publicdisclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding.
With respect to the non-proprietary versions of these reports, the NRC ispermitted to make the number of copies beyond those necessary for its internal use which are necessary inorder to have one copy available for public viewing in the appropriate docket files in the public documentroom in Washington, DC and in local public document rooms as may be required by NRC regulations ifthe number of copies submitted is insufficient for this purpose.
Copies made by the NRC must includethe copyright notice in all instances and the proprietary notice if the original was identified as proprietary.}}

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