ML20206J086

Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Spec 3.2.3 to Delete Rod Bow Penalty & Deleting Tech Spec Figure 3.2-3

ML20206J086
Person / Time
Site:	Farley
Issue date:	06/16/1986
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206J089	List: ML20206J086 ML20206J092
References
TAC-60291, TAC-60292, NUDOCS 8606260411
Download: ML20206J086 (18)

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UNITED STATES y

g NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C. 20555

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ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated November 27, 1985, as supplemented April 11, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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 regulations of the Commission; n.

C.

There is reasonable assurance: (i) 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 in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR'Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:

8606260411 860616 PDR ADOCK 0000 8

P l

. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION cub #1 Lester S. Rubenstein, Director ifJL PWR Project Directorate #2 Division of PWR Licensing-A j

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 16,1986 i

if ATTACHMENT TO LICENSE AMENDMENT NO. 64 TO FACILITY OPERATING LICENSE NO. NPF-2 4

00CKET NO. 50-348 Replace the following pages of the Appendix "A" Technical Specifications l

with the enc:osed pages as indicated.

The revised pages are identified i

by amendment number and contain vertical lines indicatir.g the area of change.

The corresponding overleaf pages are also provided to maintain document j

completeness.

i Insert Pages Remove Pages s

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(2)Dd 032nNYWWON-(Z)M FARLEY-UNIT 1 3/4 2-7 AMENDMENT NO. 26

POWER DISTRIBUTION LIMITS N

3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F4sH LIMITING CONDITION FOR OPERATION N

3.2.3 F Ji H shall be limited by the following relationship:

F)gH<1.55[1+0.3(1-P)]

THERMAL POWER where P = RATED THERMAL POWER s

APPLICABILITY: MODE 1 ACTION:

WithF$gHexceecingitslimit:

a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to <-

55% of RATED THERMAL POWER witnin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, Demonstrate through in-core mapping that F$5H is within its limit b.

witnin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter exceeding the limit or reduce THERMAL POWER to less tnan 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by g or b, above; subsequent POWER OPERATION may proceed provided that FAH is demonstrated through in-core mapping to be within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL POWER and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.

FARLEY-UNIT 1 3/4 2-8 AMENDMENT h0 26, 37, 64

POWER DISTRIBUTION LIMITS i

SURVEILLANCE REQUIREMENTS N

4.2.3.1 F

shall be determined tc be within its limit by using the movable incoredeth!torstoobtainapowerdistributionmap:

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

c.

The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The measured F of 4.2.3.1 above, shall be increased by 4% for measurement uncertainty.g 1

i

• g.

i t

i FARLEY-UNIT 1 3/4 2-9 AMENDMENT NO. 26

9 This Page Intentionally Blank FARLEY-UNIT 1 3/4 2-10 AMENDMENT NO. 16, 64

Percent of Rated Thermal Power 5%

5%

gg F-90%

E

. M.

90%

70%

5_

s Target Flux Difference EM i

50%

40%

+.

E 5

10%

N

- - ~

30%

20%

10%

0

+10%

+20%

+30%

INDICATED AXIAL FLUX DIFFERENCE j

Figure B 3/4 21 TYPICAL INDICATED AXIAL FLUX DIFFERENCE VERSUS THERMAL POWER l

FARLEY - UNIT 1 B 3/4 2-3 AMEN 0 MENT NO. 26

POWER DISTRIBUTION LIMITS BASES sussssssssssssssssssssseressssssssssssssssssssssssenessssssssssammasssamasas F H will be maintained 'within its limits pgovideg condi,tions a.

t hroug

d. above are maintained. The relaxation of FAH as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod, insertion limi ts.

When an Fn neasurement is taken, an allowance for bcth experimental error and manufecturing tolerance must be made.

An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a 3% allowance is appropriate.for manuf acturing tolerance.

When F[H is measured, experimental error must be allowed for and 4% is the appropriate allowance for a full core maj taken with the incore The specified limit for F g also contains. an St allowance detection system.

3 f r uncertainties which means that nornal operation will result in F H<1.55/1.08. The 8% allowance is based on the folf owing considerations:

a. Ahnormal perturbations in the radial power shape,'such as from rod misalignment, af fect F g more directly than (,

g D. Although rod movement has a direct influence upon limiting F0 10 w thin its limit, such control is not readily available to limit i

F H, and

c. Errors in prediction for control power shape detected during startup physics tests can be corpensated for in Fg by restricting axial flux distriDution.

Tnis compensation for F[g is lets readily available.

=

~

Fuel rod bowing reduces the value of DNB ratio.

Credit is available to of fset this reduction in the generic margin. The generic design margins, totaling 9.1% DNBR, cocpletely offset any rod bow penalties (less than 3%

for the worst case which occurs at a burnup of 33,000 MWD /MTU). This margin includes the following:

1) Design limit DNBR of 1.30 vs.1.28

2) Axial Grid Spacing Coefficient (ks) of 0.046 vs. 0.059

)

3) Thermal Dif fusion Coefficient of 0.038 vs. 0.059

4) DNBR Multiplier of 0.865 vs. 0.88

5) Pitch reduction AMENDMENT NO. 26,64 FARLEY-UNIT 1 B 3/4 2 4

j/ *'

UNITED STATES y-

't, NUCLEAR REGULATORY COMMISSION g

W ASHINGToN. D. C. 20555 ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE s

Amendment No. 57 License No. NPF-8 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Alabama Power Company (the licensee) dated November 27, 1985, as supplemented April 11, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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 regulations of the Commission; C.

There is reasonable assurance: (i) 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 in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifict.tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby amended to read as follows:

. j (2)

Technical Specifications The Technical Specifications contained in Appendices 3

A and B, as revised through Amendment No. 57, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

N FOR THE NUCLEAR REGULATORY COMMISSION p Lester S. Rubenstein, Director gpgg PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 16,1986 d

g y

r--

g-y-y

-r

ATTACHMENT TO LICENSE AMENDMENT N0. 57 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.

The revised pages are identified i

by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

s Remove Pages Insert Pages 3/4 2-8 3/4 2-8 3/4 2-10 3/4 2-10 B3/4 2-4 B3/4 2-4 l

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POWER DISTRIBUTION LIMITS N

3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F45 H LIMITING CONDITION FOR OPERATION N

3.2.3 F4kH shall be limited by tne following relationship:

N FAsH < 1.55 [1 + 0.3 (1-P)]

THERMAL POWER where P = RATED THERMAL POWER s

APPLICABILITY: MODE 1 ACTION:

N With F4kH exceeding its limit:

a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to <

55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, N

b.

Demonstrate through in-core mapping that F4LH is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 5% of RATED TdERMAL POWER witnin the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by g or b, above; subsequent POWER OPERATION may proceed provided that FaH is demonstrated through in-core mapping to be within its limit at a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL POWER and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.

FARLEY-UNIT 2 3/4 2-8 AMENDMENT NO. 27, 57

I POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS N

4.2.3.1 F

shall be determined to be within its limit by using the movable incoredeth$torstoobtainapowerdistributionmap:

Prior to operation above 75% of RATED THERMAL POWER after each fuel a.

loading, and b.

At least once per 31 Effe'ctive Full Power Days, The provisions of Specification 4.0.4 are not applicable.

c.

4.2.3.2 The measured F of 4.2.3.1 above, shall be increased by 4% for g

measurement uncertainty FARLEY-UNIT 2 3/4 2-9

4 This Page Intentionally Blank n.

FARLEY-UNIT 2 3/4 2-10

l Percent of Rated Thermal Power 5%

8%

100%

x

)

M

=

i i

00%

70%

r i

Terget Flux Difference 80%

50%

40%

n.

30%

20%

10%

i 30%

20%

10%

0

+10%

+20%

+30%

INDICATED AXIAL FLUX DIFFERENCE Figure B 3/4 21 TYPICAL INDICATED AX1AL PLUX DIFFERENCE VERSUS THERMAL POWER f

FARLEY-UNIT 2 B 3/4 2-3

POWER DISTRIBUTION LIMITS BASES EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEESSEEEEEEEEEEEEEEEEEEE33333333333 F$H will be maintained within its limits provide conditions a.

througn d. above are maintained. The relaxation of F as a function of THERMAL POWER allows changes in the radial power shape or all permissible rod insertion limits.

When an Fo measurenent is taken, an allwance for both experimental error and manufacturing tolerance must be made.

An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a 3% allowance is appropriate for manuf acturing tolerance.

When F[H is measured, experimental error must be allowed for and 4% is the appropriate allwance for a f'ull core mag taken with the incore detection system. The specified limit for FAH also contains an 8% allowance f r uncertainties which means that nonnal operation will result in F H 11.55/1.08. The 8% allowance is based on the following considerations:

a. Abnormal perturbations in the radial power shape, such as from rod misalignment, af fect F g more directly than F g,

b. Although rod movement has a direct influence upon limiting Fg to within its limit, such control is not readily available to limit Ffg, and

c. Errors in prediction for control power shape detected during startup physics tests can be co censated for i Fg by restricting axial flux distribution.

This cocpensation for F H is less readily available.

Fuel rod bowing reduces the value of DNB ratio.

Credit is available to offset this reduction in the generic margin.

The generic design margins, totaling 9.1% DNBR, conpletely of fset any rod bow penalties (less than 3%

for the worst case which occurs at a burnup of 33,000 MW)/MTU). This margin includes the follwing:

1) Design limit DNBR of 1.30 vs.1.28

2) Axial Grid Spacing Coefficient (ks) of 0.046 vs. 0.059

3) Tnermal Dif fusion Coefficient of 0.038 vs. 0.059

4) DNBR Multiplier of 0.865 vs. 0.88

5) Pitch reduction j

FARLEY-UNIT 2 B 3/4 2-4 AMENDMENT N0. 57

-.