ML20137C842

Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel

ML20137C842
Person / Time
Site:	Sequoyah
Issue date:	03/19/1997
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20137C831	List: ML20137C827 ML20137C842
References
NUDOCS 9703250144
Download: ML20137C842 (16)

Text

_ __ _ _ ..__ -. _ . ._ __ _ ___. ._. .. _ _.. _ _ . _ _ _ - . . . _ _ _ _ _ .

{

1 ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 t DOCKET NOS. 50-327 AND 50-328

{

(TVA-SON-TS-96-01, Revision 2)

LIST OF AFFECTED PAGES i Unit 1

% 2 12

% 2-13 i B % 2-4 ,

6-21 l l

Unit ?

% 2-10

% 2-11 B % 2-4 6-22 l

i 1

s 9703250144 970319 PDR ADOCK 05000327 p PDR

M

, POWER DISTRIBUT!0N LfMITS

• Sh 3/4.2.4 0UADRANT POWER TILT RATIO

)

! 4 I

, i l - LIMITING CONDITION FOR OPERATION

.) I 3.2.4 u i The QUADRANT POWER TILT RATIO shall not exce

.dtr.021 .

Fc -i i APPLICABILITY:

MODE 1 above 50% of RATED THERHAL .[ P '

ACTION:

a.

With but lessthe thanQUADRANT or equal to 1.09: POWER TILT RATIO determined ji to e 1.

v_ .

i Calculate the QUADRANT POWER TILT RATIO at least once pe until: -

e) limit, orEither the QUADRANT TILT RATIO is reduced to within its s b)

THERMAL POWER is reduced to less than 5C% of R POWER.

2. Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

b h a) s Either its within reduce limit,the or QUADRANT POWER TILT RATIO (to s b

,q k

. s b) '

p t,g Reduce THERMAL POWER at least 3% frem RATED TH

't for each excess of 1% of indicated QUADRANT POWER TILT RATIO '

Flux-Highj$ and similarly Trip Setpoints reduce within the the Power Range Neutro next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.

Verify that the QUADRANT POWER TILT RATIO 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 50% of RATED THERMAL POWE hours and reduce the Power Range Neutron Flux-High Trip setpoin te less next than or equal to SE% of RATED THERMAL POWER within the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4 Identify and correct the cause of the out of limit condition prior to increasing THERHAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its lim once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 9E%

or greater RATED THERMAL POWER.

"See Special Test Exception 3.10.2.

e C

MAY 081990 -

SEQUOYAH - UNIT 1 3/4 2-12 R142 Amendment No. 138

1

.' f 9 0WER DISTRIBUTION LIMITS ACTION $ (Continued) b.

With the QUADRANT misalignment POWER or of either a shutdown TILT RATIO control rod: determined to exceed 1.09 due 1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until: ,

a)

Either the QUADRANT its limit, or POWER TILT RATIO is reduced to within I L

b) 1 THERMAL POWER. POWER is reduced to less than 50% of RATED THER' MAL J

2.  !

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for _

f,02-* 1% of 30 within indicated QUADRANT POWER TILT RATIO in excess of minutes, -

x .

. 3.

Verify that the QUADRANT POWER TILT RATIO is within its limit 3 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or reduce THERMAL  :

POWER to less than 50% 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 reduce the Power Range Neutron Flux-High Setpoints -l to less than or equal to 55% of RATED THERMAL POWER ithin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. "

T w- '

i

4. Identify and correct the cause of the out of limit condition ^

prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the m i

QUADRANT POWER TILT RATIO is verified within its limit at least o once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95%

or greater RATED THERMAL POWER.

c.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shutdown or control rod:

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until:

a) Either the QUADRANT POWER TILT MMd is reduced to within its limit, or b) sMAL POWER is reduced to less than 50% of RATED THERMAL 5 i.sER.

l.h:)

v

+:1 o . .??

4 MhY 0 R m90 4

SEQUDYAH - UNIT 1 3/4 2-13 Amendment No. 13S .,

e e

POWER DISTRIBUTION LIMITS

[#

BASES F el r bowi redu s the ue of DN ratio. Mar n has bee etained D etw n th NBR v ue us in the s ty analysi and the de gn DNBR gg_4 3 li t to omple y off the rod ow penalty.

The plic e val of rod b penalty i eferenced 'n the FSAR. 7 9 argin n exc s of the d bow pena y is avail e for plant esign R L42 flep ility y e hot ch nel factor q (z) is m sured period' ally and in ased by c e and h 'ght depend power fa or,W(z),to ovide assur ce that th

b. I limit on e hot cha el factor, g(z), is met. (z) accoun for the e ects i of n mal operat' transien and was deter ned from e cted power control

)y ma vers over e full ra e of burnup cp ditions in J. e core. T W(z) RL59 Q ction is ecified i he COLR. / /  ;

N 3/4.2.4 QUADRANT POWER TILT RATIO

/ The q rant power t ratio limi assures th the ra ' 1 power d' tri-bution s isfies the de gn values u d in the p r capab' ity analy 's. .

f-  ;

ower distrib on measure ts are mad during s rtup test' g and ik '

Radia per* dically durin power opera on.

The two ur time all ance for op ation w a tilt c dition gr ater g than 1.02 less than .09 is prov ed to al w identif' tion and or-  ;

y rection a dropped misaligne od. In e event s action es not a corre the tilt, e margin fo uncertai y on F n is einstate y redu ng W the ower by 3 cent from ED THER POWER f5 each perc t of in 4 cess of 1.0 ,

I 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the para-meters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated R142 adequate to maintain a minimum DNBR of greater than or equal to the safety analysis DNBR limit throughout each analyzed transient.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

. MW- !~ I B 3/4 2.-4 Amendment No. 19 138, 155 SEQUOYAH - UNIT 1 Byletterdatedbecember8,1992

l I

1

\

INSERTl

. )

The QUADRANT POWER TILT RATIO limit assures that no anomaly exists such that J the radial power distribution satisfies the design values used in the power capability  !

analysis. Radial power distribution measurements are made during startup testing and i periodically during power operation. l The QUADRANT POWER TILT RATIO limit at which corrective action is required  !

provides DNB and linear heat generation ection with x-y plane r tilts. T e  !

QUADRANT POWER TILT RATIO limi ec!L_d_-_w in the COPTe OP nAT!NC Llt?T" i

"IPORT (COLn, is reflected by a corresponding peaking augmentation f actor which is i inclu ed in the generation of the AFD limits.

l The 2-hour time allowance for operation with the tilt condition greater tha the " * .L. 02 -

Y thh $ 2 but less than 1.09, is provided to allow identification and correction 6f a dropped or misaligned control rod. In the event such action does not '

correct the tilt, the margin for uncertainty on Fo (X,Y,Z) is reinstated by reducin the i all able THERMAL POWER by 3 "percent for each percent of tilt in excessJ .h; .! '!! l cp;;5;d in thc COLn,

~ ~ -

.f.02.

s^- '

~ >

g INSERT J The flow parameters indicated in Figure 3.2-1 have been rounded down to bias the analysis in the conservative direction.

l l

i

ADMINISTRxTIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statist'ics and shutdown experience,shall R76 including documentatien of all challenges to the PORVs or Safety Valves, ba submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

4 L CORE OPERATING LIMITS REPORT R159 6.9.1.14 Core operating limits shall be established and documented in the CORE g OPERATING LIMITS REPORT before each reload cycle or any remaining part of a ralcad cycle for the following:

g y. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, J. Jr.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 4, J'. Control Bank Insertion Limits for Specification 3/4.1.3.6, mic m. car m w wtAs cification 3/4.2.1, g, /I. Axial Flux Difference Limits for a or Pt R220 Heat Flux Hot Channel Factor ( K(=)fjdz)/

.e f, g'. e ce j'l ftf 1;kte 96t$nti,a'1 cbicrefsV,inj$q .a' ,

,4dc svieglfo_cedjfor Spec _ification 3/4.2.2, ar gho]

• R159 Ss Sr)

Nuclear Enthalpy Hot Channel Factor (p6dsdowe[ FaM or gilt M1ierlfor

/' f'. Specification 3/4.2.3 g

6.9.1.14.a The analytical methods used to determine the core operatingj elimits R

'shall be those previously reviewed and approved by NRC in:

s UA* ON METH OLOGY",

4INGHO E RELO SAFE ydAP- 272-

-A, 4 1 (W Pr ,rieta.

/ Ju 198 .1.3 - oderato Temperat .e

( thodo gy for pecifi ion 3 /'

.utdo ank I oertion mit, 3.1 .6 -

k oeffi .ent, 3 .3.5 - ux Diffe nee, k Cont 1B nserti Limit , 3.2.1 Axial i and 3 .3 - Nuc ar gg Flux t Char 1 Fact .,

iL .

3. .2 - H thalp ot Cha el Fac* r.)

IAL OF ET 1220 W -102 -P-A Re sion 1 , "RE TION OF ONSTANT

)T. CHNI ' SPECIF TION", BRUARY 994 g 3 ONTRO Fn SURV" LLANCE

(W P prieta .

al Flux ifferenc y159 I

~

(Meth ology f.c Spec' ication .2.1 -

Centro and 3. . - Hea lux Hot annel f (Re' ed Ax4 Offs surve' lance quiremer s for F ethodel ).) /

b F tor (W WCAP-10266-P-A, Rev. 2, "THE 1981 REVISION OF WESTINGHOUSE EVALUATION s } ,,/ MODEL USING BASH CODE", March 1987, (W Proprietary) .

4 ' (Methodology for Specification 3.2.2 - Heat Flux Hot Channel O Factor) .

Y PORTIN MORE GATIVE I.175 W -1363 -A, "SMITY EV TION 4.

CO ICIENT CHNI PECIF TION FC THE CDERAT TEMP .

' MAR 993 (W opriet ), /

SEQUO NU PLANT derator empera re (Method ogy fo Specif ation 3.

.1.3 -

'4

( Coeff4 ient)

M AN December 11, 1995 6-21 Amendment No. 52, 58, 72, 74, 117, SEQUOYAH - UNIT 1 152, 155, 156, 171, 216

INSERT K

1. f,(AI) limits for Overtemperature Delta T Trip Setpoints and f2 (Al) limits for Overpower Delta T Trip Setpoints for Specification 2.2.1. l 1

J INSERT L 4

1. BAW-10180P-A, Rev.1, "NEMO - NODAL EXPANSION METHOD OPTIMlZED",

March 1993. (FCF Proprietary)

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)

1 2. BAW-10169P-A,"RSG PLANT SAFETY ANALYSIS - B&W SAFETY ANALYSIS 4

METHODOLOGY FOR RECIRCULATING STEAM GENERATOR PLANTS",

• October 1989. (FCF Proprietary)

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)

3. BAW-10163P-A, Core Operating Limit Methodology for Westinghouse-Designed PWRs, June 1989. (FCF Proprietary)

(Methodology for Specification 2.2.1,- Limiting Safety System Settings

[f ( AI), f2 ( AI) limits], 3/4.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 -

3

, Control Bank Insertion Limits,3/4.2.1 - Axial Flux Difference , 3/4.2.2 - Heat

' Flux Hot han I Factor,3/4.2.3 - Nuclear Enthalpy Rise Hot Channel i Fact g 3/,.2.4 m3a= P .) 1 I

4

4. BAW-10168P-A, Rev.2, RSG LOCA - B&W Loss of Coolant Accident Evaluation Model for Recirculating Steam Generator Plants, (SER expected March 1996).

4 (FCF Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

i 5. BAW-10168P-A, Rev. 3, RSG LOCA - B&W Loss of Coolant Accident Evaluation

- Model for Recirculating Steam Generator Plants, (SER expected June 15,1996).

(FCF Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

e i

6. WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985. (yl Proprietary)

- (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

1 i

i 4

l l

POWER DISTRIBUTION LIMITS j 3/4.2.4 OUADRANT POWER TILT RATIO ,

LIMITING CONDITION FOR OPERATION r -

3.2.4 The QUADRANT POWER TILT RATIO shall not excee //0 1 ,

J,0 > L' se ci u. 1 APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER < ~ r. g Cc ,

l ACTION:

a. With the QUADRANT POWER TILT RATIO determined to excee g ut less than or equal to 1.09: 1.02

1. Calculate the QUARANT POWER TILT RATIO at least once per hour until either:

a) The QUADRANT POWER TILT RATIO is reduced to within its

]

limit, or i g b) THERMAL POWER is reduced to less than 50% of RATED THERFAL POWER.

L t 2. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either: (~

d U'

~ a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or

(

b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER f q for eacrt 1% of indicated QUADRANT POWER TILT RATIO in ekcess fp and similarly reduce tne P wer Range Neutron k> l* 0, Flux-High Trip 5etpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

l

3. Verify that the QUADRANT POWER TILT RATIO 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 50% 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 reduce the Power Range Neutron Flux-High Trip set-points to less than or equal to 55% of RATED THERFAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l

4. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95%

or greater RATED THERFAL POWER.

C5ee Special Test Exception 3.10.2.

R130 SEQUOYAH - UNIT 2 3/4 2-10 Amendment No.130 00T 021EW

l POWER DISTRIBUTION LIMITS {

ACTION: (Continued) i

b. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due .o  !

misalignment of either a shutdown or control rod: -L )

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:  %

.c 5

The QUADRANT POWER TILT RATIO is reduced to within its a) limit, or , hq f

b) THERMAL POWER is reduced to less than 50% of RATED THERMAL b i POWER.  % l A l

\

2. Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for g 1% of indicated QUADRANT POWER TILT RATIO in excess of '

LO2 . within 30 minutes.

3I Verify that the QUADRANT POWER TILT RATIO is within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% 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 reduce the Power Range Neutron Flux-High W Set-

'l points to less than or equal to 55% of RATED THERMA POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

lbP

4. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least i once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95%

or greater RATED THERMAL POWER. ,

1

c. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a shutdown or control rod:

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either: .

a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

R130 Amendment 130 SE0VOYAH - UNIT 2 3/4 2-11 ,

OCT0% u0 .

i 0 l l I

. i l . . POWER DISTRIBUTION LIMITS )

l q

, 8ASES  !

l 1

-FiTel rod ing redujc e'The value NB ratio. . rgin has be etained fw betw it the DNBR sTue used i o e safety to co tely offs + he rod bow ysis and tha esign DNBR nalty.

3g_

j

3 1 l

d T pplicable ue of rod penalty is . erenced in ' FSAR. R11 06 1

Margi n excess o .e rod bow . ty is ava' e for p design  !

R1- 30 x1bility.

J N

e hot chan factor F is meas periodic and incr d by a cycle a power f war W(z), rovide ass '

P i 1 ,eight depepi ce that thp ' l id limi the hot c anel factor g(z),is .

W(z) acc us for the 'f1Fcts is f normal o ration tra 'ents and w etermined i expected er control N maneuv over the range.o rnup condi ~ s in the c .

The W(z) R146 1 p lon is s fied in t OLR.

f l

~

T 3/4.2.4 QUADRANT. POWER TILT RATIO quadrant r tilt ratio l' 'o assures that th 1al power distr'- ]31 j bution sati s the design v used in the po apability anal

. i Radi wer distribu ~ easurements are e during startu ing and r i

%y riodically d power operatic e two hour ti a owance for o -

on with a tilt 1 tion greater than 1.02 bu . s than 1.09 is ded to allow i . rication and corre +' of a dropped . saligned rod. . e event such n does not i the tilt margin for uncer ~ y on Fq is r 4 sated by reducina

(

~

the y 3 percent from THERMAL P0' r or each percent of in ,

cs _ ess of 1.0. /

3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the para-meters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of greater than or equal to the safety R130 analysis DNBR limit throughout each analyzed transient.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their R21 limits following load changes and other expected transient operatien.

lalSA M .y l

SEQUOYAH - UNIT 2 B 3/4 2-4 Admendment No. 21, 130, 146  ;

- By letter dated December 8, 1992

INS'ERTl The QUADRANT POWER TILT RATIO limit assures that no anomaly exists such that ,

the radial power distribution satisfies the design values used in the power capability l I

analysis. Radial power distribution measurements are made during startup testing and periodically during power operation. I 4

The QUADRANT POWER TILT RATIO limit at which corrective action is required provides DNB and linear heat generation protection with x-y lane r tilts. T e ,

QUADRANT. POWER TILT RATIO limi crec!'ied in ec CORE OP n AT!NC Llr/'T" l

.m. vii, mvm o is reflected by a corresponding peaking augmentation factor which is inclu ed in the generation of the AFD limits.

The 2-hour time allowance for operation with the tilt condition greater tha 9:"-" 1.02 I[thA D but less than 1.09,is provided to allow identification and )

correction of a dropped or misaligned control rod. In the event such action does not correct the tilt, the margin for uncertainty on F a(X,Y,Z) is reinstated by reducing the i all ' able THERMAL POWER by 3 percent for each percent of tilt in excess o th: !!~'it I

" ~

.f . 02 .

~

spcci' icd in the COEn,  !

/ ' I c.

INSERT J  ;

The flow parameters indicated in Figure 3.2-1 have been rounded down to bias the analysis in the conservative direction.

l I

l l .

l

.. ~ . - - -_ ~ - - . - - - . . __ . . . - - _ . _.- , ,

ADMINISTRATIVE CONTROLS 4

MONTHLY REACTOR OPERATING. REPORT l 6.9.1.10 Routine reports of operating statistics and shutdown experience, j i

including documentation of all challenges to the PORVs or Safety Valves, shall R64 l y be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

L CORE OPERATING LIMITS REPCRT R146 g 6.9.1.14 Core operating limits shall be established and documented in the CORE 3 OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following: l l

2., f. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, j 3, f. Shutdown Bank Insertion Limit for Specification 3/4.1.3.S, y,4. Control Bank Insertion Limits for Specification 3/4.1.3.6,

,w % d a Po rw G unrrn,4.%

i g g. Limits for Specification 3/4.2.1,

f. g. Heat Flux Ect Channel K(:)l,/G( , d e .actf. tp6t hetyden / /

R206 i cogsts r e perteyrtia}/cecyttape i. .a 4-su deil' e Ifor cation 3/4.2.2, QD . R146 i

! "/ g. Nuclear Enthalpy Hot Chann 1 Factor [p6d /owpf F gte;d4ul*4pl %rlfor

~

Specification 3/4.2.3 t 6.9.1.14.a The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in: l

\s 1. W -92 [-P-A, / ESTIN~.OUSE N LOAD S ETY TION THODO ,

y1 5 (W repriet 9f) , ,

N Methe ogy f . Spec' icatic 3 .1.1. 3 . Moder or Temp .ature

- Shut wn Bank nsertic Limit, r

I Coeff'.ient, Con el B

.1.3.

Inser ion Lim' s, 3.2. - Axia Flux Di .erence,

.1.3.6 -

N 3. .2 - H t F1 Hot Ch .nel Fac~ r, and . 2. 3 ' ' clear s

or.) /

~

el Fa 1

py b

.thalpy Iot CF W -1021 P-A, vision "RE TION O CONSTAfr/ AXIAL 0 SET R206 '

g  ?.

OL g SUR LLANCE . CHNI SPECIFI TION", RUARY 994 l ~

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Methe logy fo Specifi tion 3. .1 - Ax' 1 Flux fferen 7146 d - Heat F ux Het hannel 3 (Re1 ed Axia Offset ntrol)

Facy. r (w(:) surveill ce re .rements/ orfFn M hodolo 3.2.

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[. WCAP-10266-P-A, Rev. 2, "THE 1981 REVISION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987, (W Proprietary).

0 (Methodology for Specification 3.2.2 - Heat Flux Hot Channel s

q Factor). _

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316-P-A, SAFETY ALUATI i SUPPO NG A NE VE EOL -

s.,j 4. WCAP-1 SP:EC ICATIO FOR THE / 161 3 MOD 40R TEMP ATURE C- FFICID . TECHNI ary).

W k' SEQ ' YAH NU PLANT ," Marc 1993, ._ Propr j (Methe logy fo Specif' ation 3 .1.3 -f oderat . Temper ure

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4 '?.

N December 11, 1995 SEQUCYAH - UNIT 2 6-22 Amendment No. 44, 50, 64, 66, 107, 134, 142, 146, 161, 206 s

m _ . _ . . _ . _ _ . _ _ . _ _ _ _ _ . _ _ - - _ _ _ _ . _ _ _ _ _ . . _ _ _ . _ _ _ . _ _ _ _ _ . _ _ _ _

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+

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f (All limits for Overtemperature Delta T Trip Setpoints and f 2(AI) limits for

1. 3 Overpower Delta T Trip Setpoints for Specification 2.2.1.

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1. BAW-10180P A, Rev.1, '"NEMO - NODAL EXPANSION METHOD OPTIMlZED",

March 1993. (FCF Proprietary)

(Metho:lology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)

2. BAW-10169P-A,"RSG PLANT SAFETY ANALYSIS - B&W SAFETY ANALYSIS i METHODOLOGY FOR RECIRCULATING STEAM GENERATOR PLANTS", d i

October 1989. (FCF Proprietary) _

(Methodology for Specification 3.1;1.3 - Moderator Temperature Coefficient.)

3. BAW-10163P-A, Core Opera. ag Limit Methodology f'or Westinghouse-Designed ]

PWRs, June 1989. (FCF Proprietary)

(Methodology for Specification 2.2.1,- Limiting Safety System Settings

[f,(AI), f 2(AI) limits],3/4.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - J Control Bank Insertion Limits, 3/4.2.1 - Axial Flux Difference , 3/4.2.2 - Heat 1

..hO Flux Hot a alF or 4.2.3 - clear Enthalpy Rise Hot Channel I i

~V Facto l'4.2.4 C u s t ..i I c.. c.- T; : P.o:: .)

4. BAW-10 68P-A, Rev.2, RSG LOCA - B&W Loss of Coolant Accident Evaluation Model for Recirculating Steam Generator Plants, (SER expected March 1996).

(FCF Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

5. BAW-10168P-A, Rev. 3, RSG LOCA - B&W Loss of Coolant Accident Evaluation Model for Recirculating Steam Generator Plants, (SER expected June 15,1996).  :

(FCF Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)  ;

6. WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985. (W Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.) i i

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-96-01, Revision 2)

DESCRIPTION AND JUSTIFICATION FOR THE CONVERSION FROM WESTINGHOUSE ELECTRIC CORPORATION FUEL TO FRAMATOME COGEMA FUEL (FCF) (MARK-BW 17)

Descriotion of Chanae TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) and to revise the original TS change request. This revision will withdraw the request to relocate the quadrant power tilt ratio (QPTR; to the core operating limits report (COLR). The QPTR limits will be returned to the TS at the current value of 1.02. This revision proposes a change in the QPTR value used in TS Actions 3.2.4.a.2.b and 3.2.4.b.2 from 1.0 to 1.02. This revision will also include associated changes to the discussions for Bases Section %.2.4.

Reason for Chanae This revision to the original request is proposed as a result of discussions with the NRC reviewers that indicated the relocation of the QPTR limits to the COLR would require additional justifications to demonstrate consistency with the guidance in Generic Letter 88-16. TVA is therefore revising the proposed TS change request to support timely approval by NRC and minimize the impact to the Unit 1 Cycle 9 start-up. The revision of the OPTR value, for TS action requirements that require the reduction of thermal power, has been revised consistent with the Framatome Cogema Fuel (FCF) analysis. This change was applicable to the original request and is proposed to allow the use of margins verified by the FCF analysis and to minimize the power level reductions required by TS.

Justification for Chanaes The revision that withdraws the relocation of the OPTR limit to the COLR simply returns the TS requirements to the current requirements and does not impact nuclear safety. The revision of the OPTR value used for power reductions in TS actions -

associated with exceeding QPTR limits has been evaluated by FCF in Topical Report BAW 10163P-A. This evaluation has considered a core tilt of two percent in the analysis and therefore, does not require a power reduction penalty for the first two percent of tilt. For core tilt in excess of two percent, the power reduction penalty of  ;

three percent for each percent of tilt above this limit will be applied. The current analysis for QPTR does not include an analysis of core tilt up to the 1.02 limit and therefore, requires a power reduction penalty for all core tilt. The FCF analysis has been reviewed and approved by NRC and provides appropriate power reduction l requirements for QPTR conditions between 1.02 and 1.09. The original evaluations  ;

for this TS change request continue to be valid because the analysis has not changed and the impact to the plant is the same as originally described. The original TS changes not associated with the OPTR requirements are not impacted by this request and continue to be justified by the original discussions and evaluations.

1 Environmentalimoact Evaluation I

The proposed change does not involve an unreviewed environmental question because operation of SON Units 1 and 2 in accordance with this change would not:

1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES,  ;

environmental impact appraisals, or decisions of the Atomic Safety and Licensing i Board. i

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SON that may have a significant environmental impact.

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