HNP-10-124, Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report (COLR) References for M5 Cladding

Application for Revision to Technical Specification 5.3.1 and Core Operating Limits Report (COLR) References for M5 Cladding

ML110250265
Person / Time
Site:	Harris
Issue date:	01/13/2011
From:	Burton C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-10-124
Download: ML110250265 (20)

Text

J Progress Energy Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.

13 2011 Serial: HNP-10-124 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION 5.3.1 AND CORE OPERATING LIMITS REPORT (COLR) REFERENCES FOR M5 TM CLADDING Ladies and Gentlemen:

In accordance with the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc. (PEC), requests an amendment to Appendix A, Technical Specifications (TS), of Renewed Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP).

The proposed amendment would modify the HNP TS to permit the use of the AREVA fuel cladding alloy designated as M5TM.

The proposed change to the TS revises the description of fuel assemblies specified in TS 5.3.1 and adds the AREVA NP report BAW- 10240(P)(A), "Incorporation of M5 TM Properties in Framatome ANP Approved Methods," to the referenced analytical methods in administrative TS 6.9.1.6.2 to allow the use of M5TM alloy for fuel rod cladding.

HNP requests approval of the proposed license amendment by January 2012, with implementation prior to the start of Cycle 18, currently scheduled for the spring of 2012. This requested approval date will accommodate a standard NRC review period.

In accordance with 10 CFR 50.91(b), HNP is providing the State of North Carolina with a copy of this proposed license amendment.

This document contains no Regulatory Commitment.

Please refer any questions regarding this submittal to Mr. John Caves, Supervisor -

Licensing/Regulatory Programs, at (919) 362-3137.

PO. Box 165 New Hill, NC 27562 (M:o (

T> 919.362.2502 " IilIX F> 919.362.2095

Serial: HNP-10-124 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on Sincerely, Christopher L. Burton Vice President Harris Nuclear Plant CLB/kab

Enclosure:

Description and Evaluation of Proposed Change cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, N.C. DENR Section Chief Mrs. B. L. Mozafari, NRC Project Manager, HNP Mr. L. A. Reyes, NRC Regional Administrator, Region II

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDING USE OF ALLOY M5TM FOR FUEL CLADDING

Subject:

Request for License Amendment to revise Technical Specification 5.3.1 to allow the use ofM5TM cladding and to add new analyticalmethodology to the Core OperatingLimits Report (COLR) list of approved reports in Technical Specification 6.9.1.6.2.

1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

3.0 TECHNICAL EVALUATION

3.1 Addition of M5TM to Technical Specification 5.3.1 3.2 Addition of BAW-10240 to TS 6.9.1.6.2 3.3 Assessment of Methodologies not Discussed by BAW-10240

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions

6.0 REFERENCES

ATTACHMENTS:

1. Technical Specification Page Markups

2. Retyped Technical Specification Pages Page 1 of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL. SPECIFICATION REGARDING USE OF ALLOY M5T.M FOR FUEL CLADDING 1.0

SUMMARY

DESCRIPTION This evaluation supports a request by Progress Energy Carolinas (PEC) to amend Renewed Facility Operating License NPF-63 for the Shearon Harris Nuclear Power Plant,. Unit 1 (HNP), to permit the use of M5TM alloy for fuel rod cladding..in. future operating cycles. The proposed change would revise the Appendix A, Technical,Specifications (TS), to change the descriptionmof fuel assemblies specified in TS 5:31 and.to add the AREVA NP (AREVA) report, .

BAW- 0240(P)(A.), "Incorporation of M5TM.sPioperties in Framatome ANP Approved Methods,"

(Reference, 1) tothe analytical. methods referenced in-TS 6.9.1.6.2 to permit the use of M5TM alloy for fuel rod cladding in future operating. cycles... d-

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2.0 DETAILED DESCRIPTION TS 5.3.1, Fuel: Assemblies, provides the designi :description ,of.thereatctor core fuel assemblieS.,

The first sentence of the TS describes.the cladding matetial as foaot0.'A s:. -:,

• 5.3.1 The core sha! c ontain 1o57fuel, asblieswith :eache1assenbly nrmally,..:

containing 264 fuel rods clad with Zircaloy-4:*,*!cept thAtlimitedr substitution of fuel rods.

by filler rods consisting of Zircaloy-4, stainless steel, or by vacancies may be made in fuel assemblies ifjustified by a cycle-spe'ific evaluaýtion-:-,-,-,,. .

PEC proposes to revise .NP: TS, 5.3-:1 top.tu M5,'Th.:clatding.fig r future fuel cycles.:

The proposed xevision to*TS 5.3.1 istas .fd6lows:.. I. .

" 5.3.1 The core shall cbntain 157 fuel: ass*mblies with eacht fueltassembly'normally containing 264 fuel rods clad with Zircaioy-4 or. M5Th1.. Limited sub.titutioh of fuel.rods, by filler rods clad with Zircaloy-4 or M5TM, or by vacancies may be made in fuel assemblies if justified by a cycle-specific evaluation.

TS 6.9.1.6.2, identifies the afialyticalmetliodsused to determine, the: core operating limiis: *PEC' proposes.to revise the meihods.to permit theuse of M5TM cladding for future fuel cycles as, follows:, . ' .

" Add BAW-10240 as a new methodology in Section 6.9.1.6.2. The methodology will be, identified as new item "q", based on a license amendment request currently in NRC review; which also impacts TS 6.9.1.6.2..*

" Delete XN-NF-82-49(P)(A), "Exkxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," as a methodology in Section 6.9.1.6.2.k upon implementationof this proposed change.

Page: 2. of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING

3.0 TECHNICAL EVALUATION

3.1 Addition.ofM5TMto TS 5.3.1 -. .

The current fuel cladding used at HNP. is Zircaloy-4 as stated in TS 5.3.1. 'AREVA developed the M5TM advanced.fuel.rod cladding and'fuel :ssembly structural material. M5TM is a zirconium alloy composed of zirconium and niobium.:,M5TM has. demonstrated superior corrosion resistance and reduced creep relative to bothsstahdard and low-tin Zircaloy-4.' The properties of the M5TM material' relevaritto fuel, design and safety analysis are documented in BAW-10227(P)(A), Revision 0, "Evaluation of Advanced Cladding and Structural Material (M5TM) in PWR Reactor Fuel" (Reference 2). This topical report was reviewed and approved by the NRC.

The proposed change to TS 5.3.1 adds M5 TM as an acceptable fuel rod cladding material.

Additionally, the proposed change fequiresjthat:ieplacement rods, for reconhstituting fuel..

assemblies be clad with Zircatoýz4 or MSTM.,Thisisi consistent with the NRC-approved AREVA methodology ANP-90-82(P)(A), "Application of ANF Design Methodology for Fuel Assembly Reconstitution,?, in which repIaeeent.rods,is*vtarad-tubiflg of the same material type as the assembly being reconstituted (,Reference-4f2)>-,i .:*:,',*. ,.. .

3.2 Addition ofBAW-10240 to;TS'69,16.2.,.'

TS, 6.9.1.6.2 lists the methbodologiý, 9.sed in thoa deisign and safdty- analysis of core reloads., The core operating limits report (COLR) submitted to:th-e. NRC. for each cycle identifies those methods and revisions used in the effective COLR. AREVA assessed the impact of M5TM cladding onmethodologies!used! for Core reJ20ad~design-in B3AW*10240 (Referenceo1) .. The NRC approved' BAW-1.0240 for usein license`ýapplications in a letter dated May 5, 2004 (Reference BAW-10240 describes the incorporation of the NRC-approved M5TM material properties into a set of methodologiespreviously, approvedby the NRC for-use With Zircaloy-4 cladding, Of the methodologiescurtently identified: in TS 6.9.1.6.25 BAW-1,0240 identifies one method.that is not applicable for use with M5 TM cladding. BAW-10240 explains that large break LOCA evaluation model EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," is not intended for use with M5TrM cladding. -

However, NRC-approved topical report EMF-2103(P), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," (Reference 6) addresses the application of M5TM cladding. HNP's license amendment request to implement.. EMFE-2103 iscurrently in NRC review (Reference 10)..EMF-2087 will be deleted-from TS 6.9.1.6.2.f upon implementation of that license amendment.

Page 3.of 9

Enclosure to SERIAL: HNP-10-ý,2'-t.,

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING Three of the methodologies currently identified in TS 6.9.1.6.2 are not specifically discussed in BAW-10240. These three methods are addressed in the following section.

3.3, Assessment of Methodologies'not discussed by. BAW- 10240

1. ANF-89-151 (P)(A), " ANF-RELAP Methodology for Pressurized&Water Reactors,',*:

Analysis of Non LOCA Chapter 15 Events"

2. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs",.

3. XN-NF-82-49(P)(A), "Exxon Nuclear Company. Evaluation'Model EXEM PWR' Small Break Model" Since these methodologies are not specifically disciissed' in.BAW- 10240;, disp-sition of each is as follows- ~ .f ~ ~~

ANF-89-151 (ANF-RELAP)and:EM.F-:84-093:-,.4 ANF-89-15,1 (Reference 7) and ,MF4IF4-093 (R6efe6iince8), nOn-LOCA 'miethlds for analysis of Chapter 15 Eveiits and Main Stea iLiein Bieýk(MSI Bt)` iles"ectiV:ly,`_de based on' aplication of the ANF-RELAP computer code. BAW-10240 evaluates the impact'o M5T cl~adding 'n:

non-LOCA events by assessing the impact on EMF-23 10 (Reference 5). EMF-23 10, an NRC-approved PWR non-LOCA transient analysis methodology incorporating SRE.LAP5 as the systems analysis code in place of ANF-RELAP. is applicable, to all PWR non-LOCA events, including MSLB.:

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.. ".* i, ' - ,:_ f.- -.. . . . . . . . . .

BAW-10240 assesses the impact of M5 TM on non-LOCA events isanegiigibleiand' cncludes thai EMF-2310 does'not require revision to address the use of M57M cladding. Since ANF-89-151, and EMF-84-093 are based on similar methodologies arid 'model tihesaie: events as EMF-23 10*,

the use of M5 TM cladding also has a negligible impact on the application of'ANF-89-151 and_

EMF-84-093 methodblogies to, the d&igin cfM5TM ia ding reloads .- . '

Additionally, the recent approval of EMF-23 10 methodology foir HNP cozntained'the reguilaiory commitment that the new (EMF-23 10) methodology will be utilized to perform new safety analysis of a specific event.'

XN-NF-82-49 (SBLOCA)

The XN-NF-82-49 SBLOCA methodology is based on ANF-RELAP. The SBLOCA analysis of fuel with M5 TM cladding will be performed using.methodology of EMF-2328(P)(A), "PWR Small Break-LOCA Evaluation Model, S-RELAP5 Based" (Reference. 4).,already approved for use at HNP. With the implementation of this proposedamendment and~transitionto M5TM fuel Page .4 of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TOTECHNICAL SPECIFICATION REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING cladding, XN-NF-82-49 will no longer beapplicable and Vwill! be removed as a reference from TS 6.9.1.6.2.k.

All required safety limits for future Operating 'cycles at.the HNP would continue to be analyzed using methodologies approved by the NRC. Therefore, this proposed change will have no adverse impact.on.plant safety.'. . .

4.0 REGULATORY EVALUATION

4.1 - Applicable Reqiuirements/Criteria:'. ;v .. -

The proposed changes have been evaluated to determine whether applicable regulations and requirementscontinue toi.benmet., Exemffption from th&e. reqjuirements of 10 CFR 50.46; "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," and 10 CFR 50, Appendix K, "ECCS Evaluation Models," for use of M5TM fuel cladding is required. That exemption request is bei~nsg, submitted in a separate letter (

Reference:

Serial HNP-10-125). Thepropos.edchangedos not-reequire relief from other regulatory requiremenis and do6i not dffe6t conforra with Geyielqa Design Criterion~differently than described1". he.CFSAR. .a s C i fr 4.2 Precedent"K . -

o s';, -- meIl 'c f wo The NRC has approved similar license emendment requests for Ft. Ca'h'un Staion,-

(Docket No. 50 -285), Palisades Nuclear Power Plant (Docket No. 50-255), and Sequoyah Nuclear Station(Docket No, 50-327). .. . " .. .". .

4.3. §igniicanf Hazards Consideration ., .

PEC has evaluated 'ývhether or, inota significant hazrds consideration is involved with the proposed amendment by focusing on the thi'ee standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:. ' -

1. Does {he proposed amendment involve'a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed license amendment adds a NRC "approved analytical method, BAW I0240(P)(A), "Incorporation of M5TM Properties in Framatome ANP Approved Methods,". used to determine the core operating limits4 -to TS 6.9.1.6.2 and changes the Page :5 of 9

Enclosure to SERIAL: HNP- 10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO 400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDING USE OF ALLOY M5TM FOR FUEL CLADDING description of fuel. assemblies specified:in TS 5:3.1..to allow use of the M5TM alloy. The proposed amendment does not affect the acceptance criteriafor any Final Safety Analysis Report (FSAR).safety analysis analyzed accidents and anticipated operational occurrences.ý As such, the proposedl.amendment~does not increase the probability or

-consequences of an accident.: The proposed amendment does not. involve, operation of the required structures, systems, or components; ($SSCs).in' a manner or configuration different from those previously recognized or evaluated.

Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed -amendment:create'thdipossibility of a new or different kind:0f of accident from anyaccident previously eevaluated? ' .: -.

Response: No. " . . ', ... :. '. -

Use of M5TM clad fuel will not result in changes in the operation or configuration of the facility. .Topical.,Repoart BA.Wr.10240. describes, :by refe'reneethat: the mrtterial'properties of the M5TM.. allby:are similar, to;or. betterthan those 6dZircaloy-, Therefore; since M5TM fuel rod cladding. will iperform similarly: to those:fabricatd from' Ziicaloy-4, .the.,

possibility of the fuel becoming an accident initiator and causing a new or different type of accident is precluded.

Since the material properties of M5TM alloy are similar to or better than those of Zircaloy:-4, there;will'be no.-significant changes in the types: of any effluents 'that.may be; -

releasedJ off-site. 'There will not-be a significant increase! in occupational:or public

• .radiation exposure. The pioposed amendment, do.es not .involve.operation. of any..requited SSCs in.a manner or configuration.different from -those'previously recogni'zed or, evaluated. No new failure mechanisms Will be introdticed'by the changesbeing' requested...* . :. : , ' > ..- ,  ; *I ;:.-*:i. :,, . -

Therefore, the proposed amendment does not create the possibility of a new or different kind of accident: from any accident-previously evaluated..

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed change will not involve asignificant reduction in the' margin of safety because it has been demonstrated that the material properties of the. M5TM alloy, are, not Page' 6 of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED 'LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDING .SE*OF ALLOY M5TM FOR FUEL CLADDING

.significantly.different from those of Zircaloy--4. .M5TM alloy is expected to perform similarly to or better.than Zircaloy-4 for all.normal' operating and accident scenarios, including both loss-of-coolant accident (LOCA) and non-LOCA scenarios. The proposed

,changes do'.not affect the acceptance criteria for-any FSAR safety analysisanalyzed accidents or anticipated operational 'occurrences.. All required safety limits will continue to be analyzed using.'methodologi's'aproved by theNRC.. .. "-..

Therefore, the proposed amendment would not involve a significant reduction in a margin of safety.:..

4.4 Conclusions In conclusidn,.Ibased 6n'thelconsiderati ns.described.above (1) there is reasonable assurance that the health and safety of the public will n6t:be. ,:1idangered by.operation :in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Based on the evaluatien above;."PEC:conclude,s: that.theIroipbIsbd amendment presents no significat.hazarids .consider*ationi:/nder thlestanfdards :s'et forth ifi10 CFR 501.92(c); and;.

accordirigly,-a. f~iding ofn":,oesigificant.h*izgdric'osideratiqn'iisjustified.

5.0 ENVIRONMENTAL CONSIDERATION

PEC has determined-that the proposedaniendment, would)chinge a'requirementwith respect to installation or use of a facility component locafed within the .r~stricted.area, as defined in 10 CFR!20; or would change;an ,iispectiofi or ýsurveillance.requirement. However, the'proposed amendment does :not. involve (i),a:significant: hazards consideration, (ii) a significant 'change in the types or sighificantf increase ýindtie arnmuits'O f any effluentrthat~may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criteria for categorical exclusion set forth inii 0 CFR 51:22(c)(9).': Therefore, pursuant to' 10 CFR 51-.22(b),, no environmental impact statement or environmental assessment needbe prepared in connection with the proposed amendment.

6.0 REFERENCES

1. BAW-10240(P)(A); Revision 0,"Incorporation of M5TM Properties in Framatome ANP Approved Methods;" dated May 2004-.'. '* ,

Page: 7of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATION REGARDINGUSE OF ALLOY M5 TM FOR FUEL CLADDING

2. BAW-10227(P)(A)Revision 0, -"Evaluation of Advanced Cladding and Structural Material(M5TM) in PWR Reactor Fuel," Framatome Congema Fuels, dated February 2000.

3. EMF-92-116(P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.

4. EMF-2328(P)(A) Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based," Framatome ANP Richland, Inc., dated January 2000.

5. EMF-2310(P)(A) Revision 0, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP Richland, Inc., dated November 1999.

6. EMF-2103(P)(A), Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Framatome ANP Richland, Inc., dated August 2001.

7. ANF-89-151 (P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, dated May 1992.

8. EMF-84-093(P)(A), Revision 1, "Steam Line Break Methodology for PWRs," Siemens Power Corporation, dated February 1999.

9. Letter from NRC to Framatome ANP, Final SE for Topical Report BAW-10240(P),

"Incorporation of M5 Properties in Framatome ANP Approved Methods" (TAC NO.

MB7553), dated May 2004. (ML041260560)

10. Letter from C.L. Burton to the NRC (Serial HNP-10-029), "Application for Revision to Technical Specification Core Operating Limits Report (COLR) References for Realistic Large Break LOCA Analysis," dated March 2010. (ML100890594)

Letter from C.L. Burton to the NRC (Serial HNP-10-105), "Response to Request for Additional Information Regarding Amendment to Incorporate a Realistic Large Break Loss of Coolant Accident Methodology into the Core Operating Limits Report" (TAC NO.

ME3569), dated December 2010.

11. Letter from C.L. Burton to the NRC (Serial HNP- 10-073), "Additional Information Regarding Amendment to Allow the Use of Thermal-Hydraulic Analysis Code S-RELAP5 for Non-LOCA Accident Transients", dated July 2010. (ML102160371)

Page 8 of 9

Enclosure to SERIAL: HNP-10-124 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION-FOR REVISION TO TECHNICAL SPECIFICATION

.REGARDINGUSE OF ALLOY M5TM FOR FUEL CLADDING

12. ANF-90-82(P) Revision 1 , "Application of ANF Design Methodology for Fuel Assembly Reconstitution," AdvancedNuclear Fuels Corporation, dated May 199 1.

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-I Page'9'of 9

Enclosure to Serial: HNP-lI0_,1 24.,ir Attachment -1' SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING ATTACHMENT 1 TECHNICAL SPECIFICATION PAGE MARKUPS (5 pages)

EhcQ',,,we to Serial: HNP-10-124 Attachment I SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 J

APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5ýM FOR FUEL CLADDING DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The containment building is designed and shall be maintained for a maximum internal pressure of 45.0 psig and a peak air temperature of 380'F.

5.3 REACTOR CORE

[InsetA FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 xctta i~imtzd substitutien of fue! Fads h" filler Pegs f icly1 sczzi~ tain~less 5tee4. or by vacancies mayte m~a'd'e i'n-f-uel -a'ssemblies if-justified by a cycle-specific evaluation. Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assemblybe replaced per refueling a Special Report describing the number of rods replaced' will be submitted to the Commission, pursuant to Specification 6,.9:2..within 30 days-after cycle startup. Each fuel rod shall have a nominal active fuel length ofR44 inches.

The initial core loading shall have d roaxiaiupi e~rwichenL of 3.5 weight percent U-235. Reload fuel shall be similar in physical..design to the initial core loading and shall have a maximum enrichment of 5.0.weightpercent U4235.

CONTROL ROD ASSEMBLIES... .....

5.3.2 The core shall contain 52 shutdown~and controlrod assemblies. The shutdown and rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80% silver, 15% indium, and 5% cadmium, or 95% hafnium with the remainder zirconium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM' DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR. with. allowance for normal degradation pursuant to the applicable Surveillance Requireiients,

b. For a pressure of 2485 psig, and

c. For a temperature of 650'F. except for the pressurizer which is 6800F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is approximately 10,300 cubic feet at a nominal T_. of 588.8 0 F.

SHEARON HARRIS - UNIT 1 5-6 Amendment No 1'r

. Enclosure to Serial: HNP-10-124 Attachment I SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO. TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-O54(P)(A). "PDC-3: Advanced ,Nuclear, Fuels Corporation Power DistributionýControl for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2." approved version as specified. in the COLR - -.

i. EMF-92-081(P)(A), "Statistical Setpoint/Transient Methodologgy for SWestjrighus" Tyeqa'c.,,ors, *' .apo_ eqversi on as, so*ec]tfied:.'fn the

..COLIR.

j .HTP; *)606prt6re4rom EM-F.92;153()(A) Nucleate Boiling 1..k, EMF-96.O FX1-2 29(,Pi(A)i' P R*act 4328P")(A), SA']*raECAn E

ly aniýAnali*sc6 emsl F.u ti,OrMoton Ev'alu PRs.del,

'".approved i

RELAP "M

" vers'ion .a's 'specified iii tlhe 'COLR "' ". . .. *..tJ I.. EMF-96LO2310()

II (A):"SRP haterý' 15Nn-LOC-ehd1g f ..........

por Baessried, .a~rR~t*s'!

approved,.version the .as in OL) .specified the COLR.

SHEARON HARRIS - UNIT 1 6-2-4b Amendment No.

Enclosure to S ,'a:1NP-10-124 Attachment 1 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING ADMINISTRATIVE CONTROLS 6.9.1.6 CORE:OPERATING LIMITS REPORT-(Continue'd)

XN-NF-81-58(P)(A), "RODEX2 Fuel; Rod Thermal-Mechanical Response Evaluation Model,":a,pproved.version.as specified, in, the COLR. -

ANF-81-58(P)(A), "RODEX2 Fuel Rod. Thermal Mechanical Response Evaluation Model," approved version as specified in the COLR.

XN-NF-82-D6(P)(A). "Qualification of Exxon Nuclear Fuel for

,Extended Burnup," approved version as specified in the COLR.

ANF-88-133(P)(A), 'Qualification:ofAdvanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," approved

,version as specified in the COLR.

'XN-NF-85-92,(P)(A), 'Exxon Nuclear:Uranium Dioxide/Gadolinia Irradiation. Examination and Thermal Cqnductivity Results."

approved version as specified in the COLR.

EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as, specified in the COLR.

p. EMF-2103(P)(A)."Realistic Large Break LDCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

iner B >

6.9.1.6.3 The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, nuclear limits such as shutdown.margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk. with copies to the Regional Administrator and Resident Inspector.

6.9.1.7 STEAM GENERATOR TUBE INSPECTION REPORT A report shall be submitted within 180 days after the initial entry into HOT SHUTDOWN following completion of an inspection performed in accordance with Specification 6.8.4.1. The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found, C. Nondestructive examinatioh technicjues utilized for each degradation mechanism, SHEARON HARRIS - UNIT 1 6- 24c #Amendment No,

Enclosure to Serial: HNP- 10-124 Attachment I SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO., 1 DOCKET NO.. 50-400/RENEWED LICENSE-NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGA'RDING USE OF ALLOY M5 TM FOR FUEL CLADDING INSERT A:

or M5"M . Limited substitution of fuel rods by filler rods clad with Zircaloy-4 or M5TM ,

INSERT B:

q. BAW-10240(P)(A), "Incorporation of M5T Properties in Framatome ANP Approved Methods" M

Enclosure to Serial: HNP-10-124 Attachment 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING ATTACHMENT 2 RETYPED TECHNICAL SPECIFICATION PAGES (4 pages)

, '" , .Enclos-Li.;ý,-o Seri'-)r H-N`P--1M-24 Attachmert 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. I DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE.OF ALLOY MSTM FOR FUEL CLADDING r ;,:tirT.h gtt bul im- is d2&ig2 amd shg1 he maiit~ird for a 11,* imun ireIrnal rre i . ofI1C3D i0 and a peak 1r I' ;rar I' 3E7F.

FUELu TX. QmigE E.32.1 ThF, coe g lIhalýaont in 157 fujl ds,*-Tbli* .ith e 'TOh je Lb, I

'suL'st t L,,cn

• i cf uel_ r7 b filler'y rdslad - L -i jttf 7irF I,-y- r

~~i~u~~tiari.~ at1 Oie]rx d r trI

-houcl I,zSpnlnf I ro:

rit7rmer any tfiCro* asTeIl *e r ii! *b *r ne.p1a*¢ed .,uL nftt*"f feiiný the. ,a ija`Fvl tCoeu..an*in,rt pur~uant de)c 1bnCg *0 t.Ie p0-fia in 6,9.2, -Ithin 3D d ys ftL; cycle sertup. Eich fl I rd helo de ri I In i Fuli" 1coi: I-11 Ic 14d c im 1-Rim 'tiolin he11 a m r 1 lrrwi rei' lnrct~t oI J.5! s. r ieenlta- Reload fujel 0h

.te similar in p 'sicaldesin to the ifutil cono Iedna anJ shell hIve a

~ia rr1.~i f D tpecet U,2,~

/ The core s 1 contain 52 s-utd end.

l n:rol r*d aszEmblies. The

.5hutdrln ar*d r'a as-sebl

• t'lal.* Th' nr vi a! 'a1es as.. -.

hil cc:nta.jn it fminal 142,iihes of bs er', viate .a! ha!l be.~I *Jt of .akbben'~'eir'

-control rc- ýhal1 be y.ýhd J s teiinlesi_ stqEe j,.ý Ii STGR~ P¶ELRESAS11J,- ~ lI 5.4A. The ReLanl- nLant S, stsn LS desi gnesd and shal; bea ruitýiirid:

a. * *tcavar e ith.r te C .e ,"equ e*,ten sc., led tI %c.ion 5 of the F. . Ith allwanae fa& m [e d-'iradasion purs t, the zoan a~p! hical utrv# I 1aRaeRWetui¢**'

b. F_. a p sure 21 psig, ad

-,%4t.retizerLur -. r*..

63F, expt: for t..~ p u' i1..e

• ,;h-i:

5.4.2 The toSt wIterd st2 oltne ,'.1f J Reaict* *'An JF i j~.

tio t:~at a ilfo 1inal ~ .8L~

4<~~~K H 'D _I .

5-6

I, .

• "Enclosure to Serial: HNP-10-124 Attachment 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING AMEM STPATIVE fxiTROLS 6-9ý16 CO1RF OPEiRATM;I LMIT$, P!EPI~T(O n~iu h, WI*-8S-0154M(PA). "FDG Ad,,,WCM w:clear Puel*s. Ccrporatilca Pmer Distriibul ion CoinLroi for Pram1ized w~aLt.r m.eactLrs and.

ApplicoLtiw of PDr-3 to H. B.. R birisn UMniL 2'." qprv,'ýd versirm as specified tn thE DDLR

1. *}E..F-q 1.~~~~~ EfI~81P{)~~-it~t~.~

BI[PM(A3, "$Statstical Setwi!bat/Tramrie* Fetrodxlogoy for ttd~~

WNtlw1home Type Reators, approved v~es1:9i ,s spec-ifleM. in the

.O-R.

j1~. EHFf Co'me!.attio 151,PX.), "HTP; for Nig)h Oartire B

Theru1o Fue! ." eoi!irn rarufrn*wNwieeate ppro', 'NOera a s.ec1 w ed in the OF _R.

k." DELETED.

1 EMF-'}6-,29(P){A). "React l,na*lv$5 Systal for"PRs.' apprF4,Rr verslornas .peIfied in the lil, m- EHF-!2328[Pf{A3' FA4R Sall Brealk LOM Ev!:Uatidnf HMJel, S.-RELWP5 BulI approv'd,

,P, ,ers1in as spetcfifd in 'th COLRv.

n). E*H1-3 O,[P "",SRP te, 1i Norm.LOCA. Mehod'ology th ,,

wrecsu.i zed Mater Ma.CtorS'".- ppi'o',,ed Veks51*, as wop i e0 in th OLIý1 L-- 1.- I 1 1 1 -

SHCEAW.N RiAPRIIS - UIJNT 1,i~~t o

Enclosure .o;S&,rlal: E.i 10-!4 Attachment 2 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 APPLICATION FOR REVISION TO TECHNICAL SPECIFICATIONS CHANGE REGARDING USE OF ALLOY M5 TM FOR FUEL CLADDING

$tM*I NISTPATIWE CONJTROLS

. 1.6 CORE OPkATrl w Lsu__REF)T (ECont irwud) o.. Mechanical Design Methpdblagies YN-NF-81-5B(:P)(A), "RODEU Ful Rod Therm l-Kecdeanical; Response Evaluation Iideil,-" apprcmtved rsi.n 05 sFapified in the C(IOR, ANF-81-58(P)(A.) "RODEX-2 Fuel Rod Tlelil Mechancacl Rpone.

Eva1Luatlon Model," approved ,,arsion as s'pclfld in tie CULR.

XW-NF-82-DD60()P(A), :Quail tutlon Of Exxtd NuCl--ar Fwl] for Ex.terwed Burvup," approved ,erdion as Sp;ecifie in th.' COLR.

ANF-E8-.31(JP)(A)., 'Qual ification of 'dAivaed Muc-lear Fur s' TRP Design eAthodalogy fbr Rod Burnups of 62 Jd/MTU.' approved version as specified in the (MR.

.-NF-8S-92(P )(). 'Exxon Nuclear Utravkn Dd1oxide/Ga& linia lrradlation '![anmhiatlon and The",aal ndctlA ty Resual ts o approved version as ý*lt~led in thte bTiL.

Eff-92-116(P)i(A), "Generic 64khanical Design C~riteria faor F¶R Fuel Dezigns."' .pFrored yersion iv specified in'the COLR, p EF.-IO13;(P)*A,"Realstic D, Large. Break LX, Methodology for Rressurized Water R.emctrs." approved ,mrsion as spci fled It the UDL,.

q: 2A*-lI0OP4)(Aj, AM Apoý Mtoha "InwrPoro*ain

&.." of rJT' PrapgruQ r eklra 1.,1.- The corez opcratlig~ Ivii its sIM]I bP datermnf nd So U5that II pl tcabl e 'limts (e. r., fuel "therial-n-mechanical Dimits, core 1tkerr1-hydlrolic limits, nuc@Lr limits .surh as $huk-kin rmirgin, and transien Fnd anciddnt anly:siis limits) of the ýsafety znalyqi- jrýt 6,9,1.6.4 The CMRE DRERATMT, LIMITS REfIRM, including ni -c.cA*y e

rmisions or sboplemerins., shall be provi-_d on Mssuan)ke for each reload cycle. to Uhe NR- Wwcent Cmitrol Desk. Oth coptes to tile Rei-onal dmininstr tor and Ressdmt ,Inspectr A relxrt. s-hll be sutznitted within 1i0 4ys-ifter the initia! ent' into [)T

• H-UtB.-IIN fQo.!

! n* ¢*leti* opf im insc..tipi perfkried in ,;ccr*.,e ;nth Zpecificatism' 6,.13.4, The report shall inclhde;

a. The scope of inspe-tMons per'lonied on each &21.

6. Active degradaticvri merianisift tfoidz.

c, NondPestrurctive mirnattion t.-hniques vti1i-_ed for each degraacati on mechaniism, SHEAKA RA~M$] - 1,11T 1Iuecket~ 5-2*4C Amndwnt W),