ML20215M018

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Amends 73 & 54 to Licenses NPF-9 & NPF-17,respectively, Revising Tech Specs to Reflect Third of Several Refueling Stages Involved in Transition to Use of Optimized Fuel Assemblies in Unit 2
ML20215M018
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 06/22/1987
From: Youngblood B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215M020 List:
References
NUDOCS 8706260250
Download: ML20215M018 (18)
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(; $tso i UNITED STATES o,, NUCLEAR REGULATORY COhlMISSION f' o 4 5 p' WASHINGTON, D. C. 20555 { j DUKE POWER COMPANY i i DOCKET NO. 50-369 l' McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF ! ~ The Nuclear Regulatory Comission (the Commission) has found that: i 1. A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed i by the Duke Power Company (the licensee) dated April 9.-1987, and supplemented May 18 and June 15, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this cmendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth -in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common i defense and security or to the health and safety of the public; and l E. The issuance of this amendment is in accordance with 10 CFR Part 51 i of the Comission's regulations and all applicable requirements have been satisfied. 8706260250 870622 PDR ADDCK 05000369 i P PDR

em a y c 9 1 8 2. [Accordingly, the license'is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is.hereby amended to read as follows: .(2).TechnicalSpecifications The Technical Specifications contained in Appendix A,- as revised . through Amendment No. 73 ', are hereby incorporated into the license'. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of.its date of issuance. 'FOR-THE NUCLEAR REGULATORY COMMISSION' B. J..Youngblood, Director Project Directorate 11-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification

Changes Date of Issuance: June 22, 1987
  • See previous concurrence j

PD#fl-/DRP-II/I PD#II-3/DRP-I/II OGC/B PD#I) dlRP-I/II DHood:mac

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i' l 3 2.:'280s,9'o ) 8 UNITED STATES. [.. ,( j. g-NUCLEAR REGULATORY COMMISSION 2: WASHINGTON, D. C. 20$$$ ,[l .c ..... f a g DUKE POWER COMPANY' j I i DOCKET NO. 50-370 } McGUIRE NUCLEAR STATION, UNIT 2 f . AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 'i License No. NPF-17 1. The Nuclear Regulatory Commission (the Comission) has found that: A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated April 9,1987, and- -'1 r supplemented May 18 and June 15, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth'in 10 i CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the; provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will' be conducted-i in compliance with the Comission's. regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; anc E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been l' satisfied. l I i l l u

n i 7,.. u-s .2 s. 2. Accordirgly,, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, i and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows: (2)TechnicalSrsecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 54 are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifiestions and.+he Environmental Protection Plan. 3. This license amendment is. effective as of its date of issuance. FOR THE NUCLEE REGULATORY COMMISSION l B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-I/II 'i

Attachment:

Technical Specification Changes. Date of Issuance: Jdde 22, 1987 l l See previous concurrence RP-1/II PD# 3/DRP-II/I PD#11-3/DRP-I/II C/BETF PD# blood 06/]{ig/87 1{ Cg(W BJYob DHood:mac

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f. (".' ; l-. .,,s i ~ w .g. i I .i. .n. g *: .i ATTACHMENT TO LICENSE AMENDMENT NO. 73 h.j 'T FACILITY OPERATING LICENSE NO. NFF-9 3 a ' DOCKET NO. 50-369 7; ? .,, ' k' ' u., i (\\' 1 AND' j a TO LICENSE AMENDMENT NO. 54 fn ..c FACILITY OPERATING LICENSE NO. NPT -{ g DOCKET NO. 50-370 3 s Peplace the following pages of the Appendix "A" Technical Specifications with s ' ohe enclosed pages..The revised pages are identified by' Amendment number and I ccntain vertfcal lines indicating the areas of change. i Amended u Page v-l XXII 3/4 2-3 3/4 2-4 ) 3/4 2-6 3/4 2-7 3/4 2-8 3/4 2-9 3/4 2-9a i 3/4 2-9b-3/4 2-12 B 3/4 2-1 -j 6-21 l i 1 1 i r I o o i t, t 4

g 1 4 ,! L glU: y[ y, ;. I ' - ( w w . hh INDEX-i; LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS s "l' ' SECTION4 .I' PACE " Control Rod Insertion Limi ts.............. -............... 3/4 1-21 'FIGORE3.1-1 R D BANK INSERTION LIMITS VE W S THERMAL POWER' FOUR LOOP OPERATION.................................... 3.4 1-22 FIGURE 3.1-2 (BLANK)....................................... 3/4~1-233 q ' 3/4.2 ' POWER DISTRIBUTION LIMITS-s, n ' 3/4.2.1 ' AXIAL' FLUX DIFFERENCE'- 3/4 2-1 FIGURE 3.2-l' AXIAL FLUX DIFFERENCE LIMITS'AS A FUNCTION OF-RATED THERMAL P0WER................................. 3/4'2-3 l 3/4.2.2' HEAT FLUX HOT CHANNEL FACTOR - F (Z)...................... 3/4 2-6 q . FIGURE 3.2-2a'.K(Z). NORMALIZED F (Z) AS A FUNCTION OF CORE' HEIGHT-(Unit 1)......... 0.................................. 3/4'2-12. O FIGURES 3.2 2h K(Z)a xNORMALIZED FQ(Z).AS A~ FUNCTION OF CORE HEIGHT -l (Unit 2)........................................... 3/4 2-13. E d.2.3 '.'RCS' FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL-3 FACT 0R.................................................. .3/4 2-14 FIGURE 3.2-Sa. RCS TOTAL' FLOW RATE VERSUS R (Unit 1)................ 3/4 2-16 FIGURE 3.2-$b'RCSFLOWRATEVERSUSR AND R - FOUR LOOPS: t 2 IN OPERATION (Unit 2).............................. 3/4 2-17 FIGURE 3.2-4' R0D BOW PENALTY AS A FUNCTION OF BURNUP (Unit 2)..... 3/4 2-18-- 3/4.2.4-QUADRANT POWER TILT RATI0................................. 3/4 2-19 .3/4.2.5 DNB' PARAMETERS............................................ 3/4 2-22

TABLE 3.2-1 DNB PARAMETERS........................................

3/4 2-23 I 3/4.3 ~ - INSTRUMENTATION - l 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION....................... 3/4 3-1 r r e n '- Amendment No. g ((Unit 1) V McGUIRE - UNITS 1 and 2-Amendment No. Unit 2)

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'INDEX ADMINISTRATIVE CONTROLS

  1. P SECTION-PAGE 6.5.2 NUCLEAR SAFETYLREVIEW BOARD (NSRB) 6-9 Function.t.................................................

Organization............................................... 6-10 eview.................................................... 6-11 R Audits.................................................... 6-11 Authority.................................................. 6-12 Records................................................... 6-13 6.6. REPORTABLE' EVENT ACTI0N........................................ 6-13 6.7 SAFETY LIMIT VIOLATION......................................... 6-13 6.8 PROCEDURES AND PR0 GRAMS........................................ 6-14 6.9 REPORTING REQUIREMENTS -6.9.1 R0VTINE' REPORTS.............................................. 6-16 Startup Report............................................ 6-16 Annual Reports............................................ 6-17 Annual Radiological Environmental Operating Report........ 6-18 i Semiannual Radioactive Effluent Release Report............ 6-18 l l Monthly Operating Reports................................. 6-20 Peaking Factor Limit Report............................... 6-21 1 1 l 1 McGUIRE - UNI'TS 1 and 2 XXII Amendment No. 73 (Unit 1) Amendment No. 54 (Unit 2)

........a--. i M_ isc . n, s to.. ( 3o.10o) (to.10o). soo ) l uw:cenasts / \\ -naia g / \\ l / e Acc1PTABLE E-l^ \\ f' To- [ \\ T / i [' e SE: i l o se - 0, i g (=95.So) (21. Sol [ do - \\ e a. 3C - l 3C -- i i 10 - j i I l i .so .o .so .so -se o so so so ao se Axial Flux Difference (% Delts-1) ) -[ Figure 3.2-1 f AFD Limits as a function of Rated 'fhermal Power 4 l McGUIRE UNITS I and 2 3/4 2-3 Amendment No.73 (Unit 1) ] Amendment No.54 (Unit 2)

ne. s. s l ;r .t i .1 a. .;s. : < h.- L. l. .3 I .- ( a In M This page deleted, i l McGUIRE UNITS 1 and 2 3/4 2-4 Amendment No.73 (Unit 1) Amendment No.54 (Unit 2) I

f POWER DISTRIBUTION LIHJTS v.

p 3/4.'2.' 2 HEAT FLUX HOT CHANNEL FACTOR - Fn(Z) m 7 LIMITING CONDITION FOR OPERATION 3.2.2 F (Z)'s' hall be limited by the following relationship: q F (Z) $ [2 32] [K(Z)]'for.P > 0.5 q p F (Z). 5 Y3 [K(2)] for P 5 0.5 l E q Where: P _ THERMAL POWER - RATED THERMAL POWER ' o and K(Z) is the function obtained from Figure 3.2-2 for a given core height location. APPLICABILITY: MODE 1. j ACTION: With F (Z) exceeding its-limit: 9 Reduce THERMAL POWER at least 1% for each 1% F within15minutesandsimilarlyreducethePowkr(2)exceedsthelimit a. Range Neutron ' Flux-High Trip Setpoints within the next.4 hours;. POWER OPERATION may proceed for up to a total of 72 hours; subsequent POWER i OPERATION may proceed provided the Overpower Delta T Trip-Setpoints (value of K ) have been reduced at least 1% (in AT span) for each .{ 4 1% F (Z) exceeds the limit; and 9 b. Identify and correct the cause of the out of-limit condition prior ~to increasing THERMAL POWER above the reduced limit required by 1 ACTION a., above; THERMAL POWER may then be increased provided F (Z) l is demonstrated through incore mapping to be within its limit. q ] McGUIRE - UNITS 1 and 2 3/4 2-6 Amendment No.73(Unit 1) Amendment No.54(Unit 2)

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4 i N POWER' DISTRIBUTION LIMITS LSURVEILLANCEREQUIREMENTS

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4.2.2.1 The provisions of. Specification 4.0.4 are not applicable. l 1 4.2.2.2 For.RAOC operation, F (z) shall be evaluated to determine'if F (z) q q is within its. limit by: ] ~ Using'the movable.incore detectors to obtain a power distribution a. map at any THERMAL POWER greater than 5% of RATED THERMAL POWER. ]> b; Increasing the measured F (z) component of the power distribution q i map by 3% to account for. manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. J [ Verify.the requirements of' Specification 3.2.2 are satisfied. c.- Satisfying the following relationship: O (z) ~< 2.32x K(z) for P > 0.5 l I N F P x W(z) l FO (z) ~< x K(z) for P < 0.5 l 2.32 W(z) x 0.5 where F (z) is the measured _F (z) increased by the allowances for q manufacturing tolerances and measurement uncertainty, 2.32 is the l F. limit, K(z) is given in Figure 3.2-2, P is the relative THERMAL q POWER, and W(z) is the cycle dependent function that accounts for i 1 power distribution transients encountered during normal operation. 'This function is given in the Peaking Factor Limit' Report as per Speci-fication.6.9.1.9. M d. Measuring Fg (z) according to the following schedule: 1. Upon achieving equilibrium conditions after exceeding by i 10% or more of RATED THERMAL POWER, the THERMAL POWER at 4 which F (z) was last determined,* or q

2..

At least once per 31 Effective Full Power Days, whichever occurs first. 4

  • During power escalation at the beginning of each cycle, power level may be. increased until a power level for extended operation has been achieved and a power distribution map obtained.

i i McGUIRE - UNITS 1 and 2 3/4 2-7 Amendment No.73 (Unit 1) Amendment No.54 (Unit 2)

n 7 + . >0hERdISTRIBUTIONLIMITS ^ SURVEILLANCE REQUIREMENTS (Continued) e. With measurements indicating (z)\\ - maximum F over Z '( K(z) ) "has increased since the previous determination of F kz) bither of' the following actions shall be taken: q N 1)' Fq (z) shall be increased by 2% over that specified in Specifi-cation 4.2.2.2c. or M f2) Fq (7) shall be measured at least once per 7 Effective Full . Power Days until two successive maps; indicate that [FM (7)Tis.not increasing. maximum over z \\ K(z)) f. With the relationships specified in Specification 4.2.2.2c. above not beingLsatisfied: 1) Calculate the percent F (z) exceeds its limit by the following' 9 expression: ) g (z) x W(z))l-1 5 x 100-9 Imaximum ~ M F for P > 0.5 (over z 2 32 x K(z) / p [ maximum O ( } X W( } ) 1} x 100 M l' for P < 0.5 (over z g 6] x K(z{) / 2) One of the following actions shall be taken: a)'.Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the AFD limits of 3.2-1 by 1% AFD for each percent F (z) exceeds its limits as deter-9 mined in Specification 4.2.2.2f.1). Within 8 hours, reset the AFD alarm setpoints to these modified limits, or 'b) Comply with the requirements of Specification 3.2.2 for F (z) q exceeding its limit by the percent calculated above, or 'c ). Verify that the requirements of Specification 4.2.2.3 for Base Load operation are satisfied and enter Base Load operation. ( ' McGUIRE - UNITS 1 and 2 3/4 2-8 Amendment No.73 (Unit 1) ~ Amendment No.54 (Unit 2) l

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) g. The limits specified in Specifications 4.2.2.2c, 4.2.2.2e., and 4.2.2.2f. above are not applicable in the following core plane regihns: 1. Lower core region from 0 to 15%, inclusive. 2. Upper core region from 85 to 100%, inclusive. I ND 4.2.2.3 Base Load operation is permitted at powers above APL if the following conditions are satisfied: a. Prior to entering Base Load operation, maintain THERMAL POWER above ND APL and less than or equal to that allowed by Specification 4.2.2.2 for at least the previous 24 hours. Maintain Base Load operation surveillance (AFD within 15% of target flux difference) during this time period. Base Load operation is then permitted providing THERMAL ' ND BL ND POWER is traintained between APL and APL or between APL and 100% (whichever is most limiting) and FQ surveillance is maint:ained OL pursuant to Specification 4.2.2.4. APL is defined as: 1 APLBL = minimum [ (2.32 x K(Z) ] x 100% over Z F (Z) x W(Z)BL where: F (z) is the measured F (2) increased by the allowances for q manufacturing tolerances and measurement uncertainty. The F limit q j is 2.32. K(z) is given in Figure 3.2-2. W(z)BL is the cycle dependent l function that accounts for limited power distribution transients en-countered during base load operation. The function is given in the J Peaking Factor Limit Report as per Specification 6.9.1.9. b. During Base Load operation, if the THERMAL POWER is decreased below ND APL then the conditions of 4.2.2.3.a shall be satisfied before re-entering Base Load operation. 4.2.2.4 During Base Load Operation F (Z) shall be evaluated to determine if F (Z) is within its limit by: q q a. Using the movable incore detectors to obtain a power distribution HD map at any THERMAL POWER above APL b. Increasing the measured F (Z) component of the power distribution g map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2 are satisfied. McGUIRE - UNITS 1 and 2 3/4 2-9 Amendment No.73(Unit 1) Amendment No.54 (Unit 2)

i.o< m as 9....,, IPOWERDISTRIBUTION-LIMITSc SURVEILLANCE REQUIREMENTS (Continued) l .c.- Satisfying-the following relationship: .Ff(Z)'< Z) for'P > APLND 2 'where: F (Z) is-the measured F (Z), The F limit-is 2.32'. q q K(Z) is given in Figure 3.2-2. P is the relative THERMAL POWER.' .W(Z)BL is the. cycle dependent function that accounts for limited power distributio'n transients encountered during normal: operation. This function is given in the Peaking Factor Limit Report as per- . Specification 6.9.1.9. 'd. .Me'asuring;F(Z)inconjunction-withtargetfluxdifferencedeter-mination according to'the following schedule: l 1. Prior to entering BASE LOAD operation;after.' satisfying Section j 4.2.2.3 unless a full core flux map has been taken in the-1 previous 31 EFPD.with the relative thermal-power having been maintaine' aboveLAPLND'for the'24 hours prior to mapping,land d 2. At least once per 31 effective full power days, q e. With :neasurements indicating maximum [ ]- i over.Z has increased since the, previous determination F (Z) either of the

e following actions shall be taken:

q -1. F (Z)~s' hall be' increased by'2 percent over that-specified_in 4.2.2.4.c, or l .2. F (Z) shall be measured at least once per-7 EFPD'until 2 q successive maps indicate that N Fn(Z) maximum [ g ] is not increasing. over z f. With the relationship specified in 4.2.2.4.c above not being i satisfied, either of the following actions shall be'taken: a 1. Place the core in an equilbrium condition where the limit in 4.2.2.2.c is' satisfied, and remeasure F (Z), or

McGUIRE - UNITS 1 and 2 3/4 2-93 Amendment No. 7:(Unit 1)

Amendment No. St(Unit 2) 1

s - POWER DISTRIB' TION LIMITS U .SURVEILL'ANCE REQUIREMENTS (Continued) .2. lComplywiththerequirementsofSpecification3.2.2 brF(2). 9 exceeding-its limit by the percent calculated with tije following expression: F (Z)'x W(Z) L ND- [(max. over 'z of [-2.32 3 ) _y.] x 100 for P > APL p-x K(Z): g. The11imits-specif.ied in 4.2.2.4.c, 4.2.2.4.e, 'and.4.2.2.4.f above are not applicable in the following core plan regions: 1. Lower core region 0 to 15 percent, inclusive.

2..

Upper core region 85 to 100 percent, inclusive. t 4.2.2.5EWhen F (Z) is measured for reasons other than meeting the' requirements 9 .of specification'4.2.2.2 an overall measured F (z) shall be obtained from a power-q distribution map and. increased by.3% to-account for manufacturing tolerances .and further. increased by 5% to account for measurement uncertainty.^ ] 1 i .a 'McGUIRE - UNITS 1 and 2 3/4 2-9b Amendment No.73(Unit 1) Amendment No.54(Unit 2)

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3/4.2 POWER DISTRIBUTION LIMITS BASES 2 The specifications of this section provide assurance of fuel integrity duringConditionI(NormalOperation)andII(IncidentsofModeratejFrequency) events by: (1)' maintaining the calculated DNBR in the core at or above the design limit during normal operation and in short-term transients, a'nd (2) limiting l the fission gas release, fuel pellet temperature, and cladding mechanical prop-erties to within assumed design criteria. In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200 F is not exceeded. The definitions of certain hot channel and peaking factors as used in these specifications are as follows: F (Z) Heat Flux Hot Channel Factor, is defined as the maximum local 0 heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing toler-ances on fuel pellets and rods; F Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of H the integral of linear power along the rod with the highest integrated power to the average rod power. 3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper 9 bound envelope of 2.32 times the normalized axial peaking factor is not exceeded l during either normal operation or in the event of xenon redistribution following power changes. j Target flux difference is determined at equilibrium xenon conditions. i The full-length rods'may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerations. l McGUIRE - UNITS 1 and 2 B 3/4 2-1 Amendment No. 73 (Unit 1) Amendment No. 54 (Unit 2)

4 ~ ',pt 1,, n. ,yv i ADMINISTRATIVE CONTROLS 1 .g _ 4 ~ 6.9.1.9 PEAKING FACTOR LIMIT REPORT-3 ND The N(z) Functions for RAOC and Base Load operation and the value fc r APL (as requir'ed). shall. be established for each reload core and implemerited prior - to use. -The methodologydused to generate the W(z) functions for RAOC and Base Load-ND Operation and the value for APL shall be those previously.' reviewed and ap-proved by the NRC*. If changes to these methods are deemed necessary.they will be evaluated in accordance with 10LCFR 50.59 and submitted to the NRC for re-view and' approval prior to their use if the change is determined to irwolve an unreviewed safety question or if such a change would require amendment of pre-y i viously submitted documentation. -l A report containing the W(z) functions for ROAC and Base Load operation and: UhevalueiforAPl.ND (as required) shall be provided to the NRC document con- . trol desk with copies to the~ regional administrator and the resident inspector within 30 days of their implementation. l ND "Any information.needed to support W(z), W(2)BL and APL will be by request from"the'NRC and need not'be included in this report. SPECIAL REPORTS '6.9.2 Speciai reports shall be submitted-to the Regional Administrator of the NRC Regional Office within the time period specified for each report. l Surveillance Tech-

  • WCAP-10216 " Relaxation of Constant Axial Offset Control-FO nical Specification".

McGUIRE - UNITS 1 and 2 6-21 Amendment No.73 (Unit 1) Amendment No.54 (Unit 2) -}}

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