Text

Proposed Tech Specs Incorporating W Beacon TR WCAP-12472-P-A to Augment Functionality of Flux Mapping Sys When Thermal Power Is Greater than 25% RTP
	ML20153C400
Person / Time
Site:	Summer
Issue date:	09/18/1998
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML20153C391	List: ML20153C387; ML20153C400;
References
	NUDOCS 9809240078
	Download: ML20153C400 (57)
	v • d • e

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INDEX ,

,n.?(

!. )

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS '

SECTION !

PAGE l- 3/4.2- \

POWER DISTRIBUTION LIMITS

ys j 3/4.2.1 AXIAL FLUX DIFFERENCE . . .

l 3/4.2.2

................ 3/4 2-1 i HEAT FLUX HOT CHANNEL FACTOR 3/4.2.3

............... 3/4 2-4 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR. . . . . . m. j 3/4.2.4 ................ 3/4 2-8 i!

QUADRANT POWER TILT RATIO .

. . . . . . . . . . . . . . . . . 3/4 2-12 3/4.2.5 DNB PARAMETERS . . . . . . .

................ 3/4 2-15 l 3/4.3 INSTRUMENTATION I 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION i

............. 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . . . . '

................ 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION

, ,_, Radiation Monitoring

! ................ 3/4 3-41 Movable Incore Detectors . .

................. 3/4 3-46 DELETED . . . . . . . . . .

................ 3/4 3-47 [/

Meteorological Instrumentation

. . . . . . . . . . . . . . . 3/4 3-50 Remote Shutdown Instrumentation .............. 3/4 3-53 Accident Monitoring Instrumentation

............ 3/4 3-56 ,

Explosive Gas Monitoring Instrumentation ..........

l 3/4 3-67 j Loose-Part Detection Instrumentation ............ 3/4 3-72 l.

1

&}>ntierrau $ win.,o Sp1e 3/4 3-73 l i

i SulHER - UNIT 1 IV AmendmentNo./f,///,122 r

W L> 9go9240078 980918 -

pDR ADOCK O 395 1 -(

l e

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ......... .. ..... . ... .......... ... ....... ... .. .. ...... ... 3/4 2-1 3/4.2.2 H EAT FLUX HOT CHANN EL FACTOR ....... ... .... .. ............... ... .... .... 3/4 2-4 1 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CH AN N EL CACTOR , ... . . ......... .. .. .. . .. .. ... .. .. .. .... .. .. . . .. . . . . .. . . . .. 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO ........... ........ ...... ... .... ...... .......... 3/4 2-12 l 3/4.2.5- DN B PAR AM ETER S . .. ..... ... . . ...... .. . ... .. .. ... . . ... .. .. . . . .. . .... . ......... . . . ... ... 3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION .... .... .. ............. ... .. 3/4 31 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTR UM ENTATION ...... ... ........ ... ....... .. . .......... ..... . .... .. .. . 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation' Monitoring ........ ........ . ...... .... .......... .. .... ....... ....... . ........ .. 3/4 3-41 j Movable incore Detectors ...... .................. .. ............... ..... . ....... ...... .... 3/4 3-46 D ELETE D . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . .. . . . . . . . . . 3/4 1

Meteorological Instrumentation . .......... .......... . .... ........ . ... .. .. . ... . 3/4 3-50 '

Remote Shutdown Instrumentation ...... ........ . .. . . . . ... .. ... . ... .. . . . . . 3/4 3 -53

Accident Monitoring Instrumentation ...... .. ..... . ... . .. . .. ........ ... .. .. . 3/4 3-56 i

Explosive Gas Monitoring Instrumentation.......... . ... ...... ......... .. ..... 3/4 3-67 Loose Part Detection Instrumentation ..... .. ....... . . .. ....... ... ... . . ...... 3/4 3 72 Power Distribution Monitoring System ....... ........ ... ... . . .... . .... .. . .. 3/4 3-73 !

l i

a i 1

SUMMER - UNIT 1 IV Amendment No. 79,1L",122 1

REACTIVITY CONTROL SYSTEMS ,

LIMITING CONDITION FOR OPERATION (Continued) a) A reevaluatHon of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain , valid for the duration of operation under these i conditions. l 1

b) The SHUTDOWN MARGIN requirement of Specification 3.1.'1.1 l is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

gof,5uremch^3

^

c)

A power distributio is obtafnedo'com th(movaM8 l pC docore Aetacabrs) and ) and F a within their limits wi hin 72 ho$s,reand verified to be j d) The THERMAL POWER 1evel is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour l and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flux '

trip setpoint is reduced to less than or equal to 85%

of RATED THERMAL POWER.

1 SURVEILLANCE REQUIREMENTS I

4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions ^at -

least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined,to be OPERABLE by movement of at least 10 steps in any one direction at,least once per 31 days.

~

SulHER - UNIT 1 3/4 1-15

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reeva!uation shall confirm that the previously analyzed results of these accident remain valid for the duration of operation under these conditions.

b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c) A core power distribution measurement is obtained and Fo(z) and F5 are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and d) The THERMAL POWER levelis reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the high neutron flax trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during ,

time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at lea t once per 31 days.

SUMMER - UNIT 1 3/4 1-15 Amendment No.

1 e 1 4.am W...

7-~ r POWER DISTRIBUTION LIMITS

_3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fg LIMITING CONDITION FOR OPERATION 3.2.2 Fq (z) shall be iimited by the following relationships:

F0 (z) $ (z)] r 0. 5

[]

RTP F.(z) < "F YK(z): fo r P < 0. 5~

.h J RTP wr.are F = the F q q limit at RATED THERMAL POWER (RTP) specified in the' CORE OPERATING LIMITS REPORT (COLR),

P _ THERMAL POWER , and RATED THERMAL POWER K(z) = the normalized F q (z) for a given core height specified in the COLR.

(

APPLICABILITY: MODE 1.

ACTION.

With Fq (Z) exceeding its limit:

a.

Reduce THERMAL POWER at least q1% for each 1% F (z) exceeds the limit within-15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent __ _

' POWER OPERATION may proceed provided the Overpower delta T Trip Setpoints have been reduced at least 1% for each 1% F (z) exceeds the limit. S I b.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a, '

above; THERMAL POWER may then be' increased provided F (z) is demon-strated through (Tnpere paj 9 to be within its limit.

= = :. - -

g tt. pow <r di.n U =n swawe

= _ _ . -

'i SUMMER - UNIT 1 3/4 2-4 Amendment 'No. f6, N, 88

4 d

POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fo{zl LIMITING CONDITION FOR OPERATION 3.2.2 Fo(z) shall be limited by the following relationships:

- MP' Fo Fo(z)s (K(z)] for P > 0.5 P

Fo(z)s Fy [K(z)] for P s 0.5

, 0.5 where Fj" = the Fo limit at RATED THERMAL POWER (RTP) specified in the CORE OPERATING LIMITS REPORT (COLR),

p , THERMAL POWER RATED THERMAL POWER , aM K(z) - the normalized Fo(z) for a given core height specified in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With Fo(z) exceeding its limit:

a.

Reduce THERMAL FOWER at least 1% for each 1% Fo(z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower delta T Trip Setpoints have been reduced at least 1% for each 1% Fo(z) exceeds the limit.

b. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced Emit required by a, above; THERMAL POWER may then be increased provided Fo(z) is demonstrated through core power distribution measurement to be within its limit. i I

SUMMER - UNIT 1 3/4 2-4 Amendment No. SS,75 SS,

-v I. V)HLA MUlAL NO "-

I's g

' S 2 3 fo, buf y $*f of ReTeD THEtt M A L. /o w s x , o (-

1. (A) h6 /) Ye owGr t h$ f'b V$d f%hWing S} stem (PDms) a mopmble ;

POWER DISTRIBUTION LIMITS y gca_a.5 sag N 6/ p <ed y 0 6 (3//'/'cd/c P.) S 11%vfactariq ar,d Musuremerrt uncs,Taoistre$ as s pe c.s [e ed SURVEILLANCE REQUIREMENTS ,'r,

+Ae COLR.

4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 For RAOC operation, F (z) shall be evaluated to determine if F (z) q is within its limit by: q

a. Using the movable incore detectors to obtain a power distribution

~

map-:t :ny 'MEP."."L PCMEP. grat r th= 5 Of AATED "ME.T."L POUCR.

/E- OL b. Incr ::ing th ::n;=d I (z)qcespenent ef the pc.;;r distributica (A)htn ME8MALMER =p by 3% t: ::ccent fer :=cf::tur'n; t:1:::n::: = d further

! [5 > 2.5 L of [$IEh I 007000iUG nrify th: th =;;iV0120 r;;=t: DOfE puif 10 ""n"atun :I ICT 200;"T;0"I TtdntI"-

UC"e

.2.2 :re a ti:fi f Satisfying the following relationship:

TNs/f/4A L /0a>2K)

A nd inci~t%5ing +h e N#5 d @f-) Sy /A L

. GPPlica ble p;anu fa c4v,,,v F(z)1FhTP x K (z) for P > 0.5 v

P x W (z) and musW6me dT Uncerraintes i as Spec.]ieg ,;, t/e COLk (z) q 1 FgRTP x K (z) for P 5 0.5 MVdedon COL.

W (z) x 0.5 aphee.Ue where F (z) is the measured Fq(z) increased by theIallowances for manufacturing tolerances and measurement uncertainty, F q

is the Fqlimit, K(z) is the normalized F q(z) as a function of core height, P is the relative THERMAL POWER, and W(z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation. F ,K(z) and W(z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

d. Measuring (Z) according to the following schedule:

1. Upon achieving equilibrium conditions after exceeding by 10%

or more of RATED THERMAL POWER, the THERMAL POWER at which Fq (z) was last determined,

or

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

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 1Ae Core power distribution w obtained.

SUMMER - UNIT 1 D 3/4 2-5 Amendment No. 88

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS e

- a - >, . - -

--.-e--- ,- - -,- - - ,+- - e- w+~~--w-4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 For RAOC operation, Fo(z) shall be evaluated to determine if Fo(z) is within its limit by:

a. Using the movable incore detectors to obtain a power distribution map

1. When THERMAL POWER is s 25%, but > 5% of RATED THERMAL POWER, or i

2. When the Power Distribubon Monitoring System (PDMS) is inoperable; and increasing the Measured Fo(z) by the applicable manufacturing and measurement uncertainties as spanified in the COLR.

b. Using the PDMS when THERMAL POWER is > 25% of RATED THERMAL ,

POWER, and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

c. Satisfying the following relationship:

1 Fs(z)s p

for P > 0.5 F5(z)s

for P s 0.5 where F#(z) is the measured Fo(z) increased by the applicable allowances for manufacturing tolerances and measurement uncertainty as specified in the COLR, F" is the Fo imit, K(z) is the normalized Fo(z) as a function of core height, P is the relative THERMAL POWER, and W(z) is the cycle dependent !

function that accounts for power dstribution transients encountered during j normal operation. F*, o K(z) and W(z) are specified in the CORE OPERATING !

LIMITS REPORT as per Specification 6.9.1.11.

d. Measuring F5(z) according to the following schedule:

1. Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which Fo(z) was last determined,

or

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

l

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 the core power distribution

measurement is obtained.

I SUMMER - UNIT 1 3/4 2-5 Amendment No. 88

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUTREMENTS (Continued)

e. With the maximum value of (z)

K(2) over the core height (z) increasing since the previous determination of (z) either of the following actions shall be taken:

(1) (z) shall be increased by 2% over that specified in

, Specification 4.2.2.2c. or (2) F (z) shall be measured at least once per 7 Effective Full Power Days until two successive aaps-indicate that the maximum value o pH L ,6v7<og eexsvevne 0 h K(z) over the core height (z) is not increasing.

f.

With the relationships specified in Specification 4.2.2.2c. above not being satisfied:

(1) Calculate the maximum percent over the core height (2) that F

, 0(z) exceeds its limit 5 by the following expression:

I (z) x W(z)"I 1 RTP

~

I 1*

F 0

KC*)

.p -

' ~ 3 (z) x W(z)"

) RTP

.1, x 100 for P < 0.5 i

, x K(z) ,

I I

StM4ER - UNIT 1 --

3/4 2-6 Amendment No. 7), 88 l

l

! o POWER DISTRIBUTION LIMITS i

SURVEILLANCE REQUIREMENTS (Continued)

e. With the maximum value of l

Fs(z) l K(z) over the core height (z) increasing since the previous determination of Fs(z) either of the following actions shall be taken:

(1) F#(z) shall be increased by 2% over that specified in Specification 4.2.2.2c. or (2) Fs(z) shall be measured at least once per 7 Effective Full Power Days until two successive power distribution measurements indcate that the maximum value of Fs(z)

K(z) over the core height (z) is not increasing.

f. With the relationships specified in Specification 4.2.2.2c above not being satisfied:

(1) Calculate the maximum percent over the core height (z) that Fo(z) ;

exceeda its limit by the following expression:

l F MxW(z) g -1 . x 100 for P 2 0.5 x K(z)

F@z)xW(z) -1 . 100 for P < 0.5 Fj" xK(z) 0.5 .

l l

l SUMMER - UNIT 1 3/4 2-6 Amendment No. 767 88, l

[ ,. . . _ . .

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

(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 applicable AFD limits by 1% AFD for each percent qF (z) exceeds its limits as determined in Specification 4.2.2.2f.1). Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints to these modified limits, or (b) Comply with the requirements of Specification 3.2.2 for i

Fq (z) exceeding its limit by the percent calculated above, l or (c) Verify that the requirements of Specification 4.2.2.3 for l Base Load operation are satisfied and enter Base Lead I i operation.

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 regions:

1. Lower core region from 0 to 15%, inclusive.

2. Upper core region from 85 to 100%, inclusive.

4.2.2.3 Base Load operation is permitted at powers above APLND 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 4 for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Maintain Base Load operation !

surveillance (AFD within applicable target band about the target 1

! flux difference) during this time period. Base Lead operation is l

then permitted providing THERMAL POWER is maintained between APLND OL 0 and APL or between APL and 100% (whichaver is most limiting) and Fg surveillance is maintained pursuant to Specification 4.2.2.4.

BL

j. APL is defined as the minimun value of:

RTP Fg ,gg7)

APL0 ' = N x 100%

F (z) x W(z)BL qs Speq [g m d Q (

over the core height (z) where: F (z) is the measured F (z) 9 increased by the allowances for mandeturing tolerances and measurement uncertaint [ The Fq la .t is F qRTP .W hW@

dependent function that accounts for limited power distribution transient encountered during base load operation. F RTP , K(2), and 4

W(z)BL are specified in the CORE OPERATING LIMITS REPORT as per

} Specification 6.9.1.11.

l SUMMER - UNIT 1 ,

3/4 2-6a Amendment No. 73, S8 i

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

(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 appicable AFD limits by 1% AFD for each percent Fo(z) exceeds its limits as determined in Specification 4.2.2.2f.1). Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints to these modified limits, or (b) Comply with the requirements of Specification 0.2.2 for Fo(z) exceeding its Emit by the percent calculated s'.ove, or -

(c) Verify that the requirements of Specification 4.2.2.3 for Base Load operation are satisfied and enter Base Load operation.

g. The limits specified in Specifications 4.2.2.2c.,4.2.2.2e., and 4.2.2.2f. abnve are not applicable in the following core plane regions:

1. Lower core region from 0 tra f 5%, inclusive.

2. Upper core region from 85 to 100%, inclusive.

4.2.2.3 Base Load operation is permitted at powers above APL"if the following condtions are satisfied;

a. Prior to entering Base Load operation, maintain THERMAL POWER above APL" and less than or equal to that allowed by 8pecification 4.2.2.2 for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Maintain Base Load operation surveillance (AFD within 4 appEcable target band about the target flux difference) during this time period.

Base Load operation is then permitted providng THERMAL POWER is maintained between APL" and APL" or between APL" and 100% (whichever s

is mostAPL 4.2.2.4. limiting)is defined as the minimum value of:and Fo urveillance F xK(z)

APL"F z)=x W(z)a s(STP over the core height (z) where: F5(z) is the measured Fo(z) increased by the appicable allowances for manufacturing tolerances and measurement uncertainty as specified in the COLR. The Fo limit is Fj". W(z)a is the cycle dependent function that accounts for Emited power distribution transient encountered during base load operation. Ff", K(z), and W(z)a are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

SUMMER - UNIT 1 3/4 2-6a Amendment No. 75788r

O n h f owe'~0ts$,Llutusa Mc s da l:,,3 $yrkm POWER DISTRIBUT: IMITS (eoms) h increcaw; ami an.o;9 L p,w. red f(n) q by tLs. itfflac.,ye m s v6ctairh3 saa mdasurMsnr unv7.L.<,tue3 as speAsbe.) ;,. fle COLfi SURVEILLANCE REOUIREMENTS (Continued) 5. .

N- ' -

b. During Base Load operation, if the THERMAL F0WER is oecreased 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 q

Fq (z) is within its limit by: -

a. Using the movable incore detectors to obtain a power distribution mapatanyTHERMALPOWERaboveAPL"b -

b. -

Incr: = ing the = ured F (:) : r; = =t Of the p:'ce:r d!:tribut!=

Q

&- ,-x,,w+,,---...+,,....<,.,.4.,. '

+,u,-~ --,,,,w..

) W'40 M N'O IfEErEI IS[EhESE5EE by 5 EE'5EE5b? FEE $EEEEEE-EEt EEEEhthintir.

/ 'I+ evy ThcO7A. ' ver4 <y th': requi r:rt: " speci<intic, 2.2.2 2r ntere <ei

/80 wen c w T Satisfying the following relationship:

( % APL*.oj hcauSQ k aff < awe i RTP In c.rsa s mj Le thes wed y H # #

x y ,' f' -"',' $;4 #'*R',4 r(F) Q (z)

APLg ^ <i d ^ << w en un c e 1., 7,, 3 r q b y&. appiable x W(z)gg ,, ,g ,j ; ,, g % ~ fa.srs <iy a,,4 gp f*#*# where: F (z) is the measuredqF (zK TheqF limit is F q . } vn CMa.ntie1 e5 n / W C'# ecd in f46 P is the relative THERMAL POWER. W(z)BL is the cycle dependent (W func. tion that accounts for limited power distribution transients encountered during normal operation. F are PK (z) and W(z)BL g acified in the CORE OPERATING LIMITS REPORT as per 5eiM n; ation 6.9.1.11.

d. Meo w ng F"(z) in conjunction with target flux difference determination according to the following schedule: desfe44,v

1. Prior to entering BASE LOAD operation after satisfying -

"'f 44 '"3 448-tion 4.2.2.3 unless a ful' ::r: '1 = m:; h = ber taken in the 4 3-previous 31 EFPD with the relative thermal power having been ~ ND maintained above APL for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to -- pin:, and

2. At least once per 31 Effective Full Power Days. <.O.%

e. With the maximum value of F"(z)

K(z) SUMMER - UNIT 1 3/4 2-6b Amendment No. 7E, 88 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

b. During N Base Load operation, if the THERMAL POWER is decreased below APL then the condtions of 4.2.2.3.a shall be satisfied before re-entering Base Load operation.

4.2.2.4 During Base Load Operation Fo(z) shall be evaluated to determine if Fo(z) is within its limit by: , a. Using the movable incore detectors to obtain a power distribution map at any ' ! THERMAL POWER above APL" when the Power Distribution Monitoring l System (PDMS) is inoperable; and increasing the measured Fo(z) by the l applicable manufacturing and measurement uncertainties as specified in the COLR.

b. Using the PDMS at any THERMAL POWER greater than APL" ; and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertainties as specified in the COLR.

c. Satisfying the following relationship: I Fs(z)s; *I for P > APL" P x W (z)g where: Fs(z) is the measured Fo(z) increased by the applicable allowances for manufacturing and measurement uncertainties as specified in the COLR. The Fo limit is Ff. P is the relative THERMAL POWER. W(z)a is th3 cycle dependent function that accounts for limited power distribution transients encounterod during normal operation. F'"', q K(z) and W(z)a are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.11.

d. Measuring F5(z) in conjunction with target flux difference determination according to the following schedule:

1. Prior to entering BASE LOAD operation after satisfying Section 4.2.2.3 unless a core power distribution measurement has been obtained in the previous 31 EFPD with the relative thermal power having been maintained above APL" for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to measurement, and

2. At least once per 31 Effective Full Power Days.

e. With tile maximum value of Fs(z)

K(z) l SUMMER - UNIT 1 3/4 2-6b Amendment No. 74887 l . 1 p -- - m ~

t. ww THERMAL POWER, b $ 2,5 % , b ut > Slf of RAT 6DTHeAMAL PO WGA. , o r"

z. (Aen 14e Power On%b8m Menoter ong Sy' f% (PM:$)

POWER DISTRIBUTION LIMITS IS dnaf dra hk

1 and onco eo ve9 e occasured h) by de aff <calle l resu < creemy ud nens.iens,ent vacsera n t es a s i SURVEILLANCE REOUIREMENTS (Continued) Sp e c., f, e d <h -rd e COLR l l

\ over the core height (z) increasing since the previous determination of F (z) either of the following actions shall be taken:

1. F (z) shall be increased by 2 percent over that specified in 4.2.2.4.c, or

2. F (z) shall be measured at least once per 7 Effective Full l

Power Days until 2 successive,aape indicate t_ hat the maximum ! vaiue of g,Le,. dat<lf u% s.%, se.e; 1 u - -- 1 l Fj'(z) l K(z) f over the core height (z) is not increasing. l f. With the relationship specified in 4.2.2.4.c above not being

satisfied, either of the following actions shall be taken: l

1. Place core in an equilibrium condition where the limit in 4.2.2.2.c is satisfied, and remeasure FN (z), or

+ 2. Comply with the requirements of Specification 3.2.2 for F (z) exceeding its limit by the maximum percent. calculated b k #eNIO Q l , over the core height (z) with the following expression:

tvbes TH&KMAc. YOWer

- /.s > 2 5 % e4 8 A T6 0 f M $ l F (3) x g(g) (- ND l 77r'ERmA L /0WEA / d'?d 0 ) - 15 x 100 for P > APL ~ ress&rg 1Le sneasared I gyp ! ~'by 74e applau.ble 1 F n x K(z) j n .ifecturkg assi imsereeent\ 6 p - uncutx,isks c.s t .caf sd sh ' r* e C oce.

g. Te imits specified in 4.2.2.4. c, 4.2.2.4.e, and 4.2.2.4. f above i are not applicable in the following core plane regions: \

\

1. Lower core region 0 to 15 percent, inclusive. \

\ r ' \

2. Upper core region 85 to 100 percent, inclusive.

\ f \ ~.2.2.5 4 When F (z) is measured for reasons other than meeting the requirements i of Specificatio 4.2.2.2 an overall measured F (z) shall be obtained l n l power distribution map :nd 4-c er^d by * t: ::::::t f: ::nuf::tt *q; j t r '--~ : 2nd furt M - inc -e "-d T 5* +c "--a"a* " --~"----n* ' * *"t W ty. SUMMER - UNIT 1 3/4 2-6c Amencment No. 75, 88 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Contmuod) over the core height (z) increasing since the previous determination of Fs(z) either of the following actions shall be taken:

1. F5(z) shall be increased by 2 percent over that specified m 4.2.2.4.c, or

2. F5(z) shall be measured at least once per 7 Effective Full Power Days until 2 successive power distnbution measurements indicate that the maximum value of Fs(z)

K(z) over the core height (z) is not increasing.

f. With the relationship specdied in 4.2.2.4.c above not being satisfied, either of the following achons shall be taken:

1. Place core in an equilibrium condition where the limit in 4.2.2.2.c is sabsfied, j and remeasure Fj(z), or

2. Comply with the requirements of Speedicabon 3.2.2 for Fo(z) exceeding its limit

, by the maximum percent calculated over the core height (z) with the followmg l expression l l ! FU(z)xW(z)n -1 . x 100 for P 2 APL" l m l p xK(z) l g. The limits specified in 4.2.2.4.c,4.2.2.4.e and 4.2.2.4.f above are not applicable in the I following core plane regions *

1. Lower core region 0 to 15 percent, inclusive.

l 2. Upper core region 85 to 100 percent, inclusive. l 4.2.2.5 When Fo(z) is measured for reasons other than meebng the requirements of Speedicahon 4.2.2.2 l an overall measured Fo(z) shall be obtained:

a. from a power distnbution map

j. 1. when THERMAL POWER is 5: 25%, but > 5% of RATED THERMAL POWER, or l 2. when the Power Distnbubon Monitoring System (PDMS)is inoperable; and increasing the measured Fo(z) by the applicable manufacturing and measurement uncertamties as speedied in the COLR.

b. from the PDMS when THERMAL POWER is > 25% of RATED THERMAL POWER; and

, increasing the measured Fo(z) by the applicable manufacturing and measurement j uncertainties as speedied in the COLR. J l SUMMER - UNIT 1 3/4 2-6c Amendment No. 74r88r I l_ , _ _ POWER DISTRIBUTION LIMITS 3/45.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE IIOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination ofindicated Reactor Coolant System (ItCS) total flow rate and R shall be mamtained within the region of allowable operation as specified in the CORE OPERATING 131ITS REPORT (COLR) figure entitled RCS TotalFlow Rate Versus R For Three Loop Operation. # Where: .x % ###" 'S 5 #' bn > S % ef ICATC Timagse

a. R = Fw ,

p, w , ,,_ "'b M D '* '"'# ## N , 4 '?I F [1!0+ PFan(1.0 - P)}

2. Lison$ +1e pdm.s a n eg m a

/Opg4 ~ 'u . P = THERMAL POWER RATED THERMAL POWE~R @ g.

g MD

c. Fan = Measured values of Fan obtained by6 sing the movable incere detecto obtain a power distIribution mapj The measul N T I

[,ocrease d 37 cAc values of Fan shallbe used to calculate R since the RCS Total Flow Rate Versus R fi;:ure in the COLR includes measurement j Ayt,c4 6 le {^' /mensvee,,7 uncertainties of 2.1% (includes 0.1% for feedwater venturi and [ _ ~- fouling) for flow rd t'~ #^"~^-^ mr=:=ent of FI:;, rd [ d. RTP N . Fan = The Fan limit at RATED THERMAL POWER specified in the CCy

e. PFan = The Power Factor Multiplier specified in the COLR.

APPLICABILITY: MODE 1. ACTION: With the combination of RCS total flow rate and R outside the region of acceptable operation specified in the COLR:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1. Restore the combination of RCS total flow rate and R to within the abovelimits, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High trip setuoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . -

a co e1 20~sk % ~ ex s v rw

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ofinitiall. emg outside the abovelimits,ve through i =r: fh: sp ' and RCS total flow rate comparison that the combination of R andRUS total flow rata are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the ne::t 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SUMMER-UNIT 1 3/42-8 Amendment No. hh% IE 119 a POWER DISTRIBUTION LIMITS 3/4 2 3 R_QHEkQW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR , LIMITING CONDITION FOR OPERATION l 3.2.3 The combinaticn of irdicated Reactor Coolant System (RCS) total flow rate and R shall be maintained l I within the region of allowable operation as specified in the CORE OPERATING LIMITS REPORTS (COLR) figure entitled RCS Total Flow Rate Versus R For Three Loop Operation. Where: l a' R = F*N l F7{1.0 + PFm(1.0- P)]

i l

b. P =

THERMAL POWER RATED THERMAL POWER *

c. F$ = Measuredvaluesof FE obtainxiby l

1. Using the movable incore detectors to obtain a power distribution map when THERMAL POWER is s 25% but > 5% of RATED THERMAL POWER, or when PDMS is inoperable, and 1

] 2. Using the PDMS when THERMAL POWER is > 25% of RATED THERMAL POWER. .i l I The measur'ed values of F1 shall1:e increased by the applicable F1 mes.surement uncertainties as speerfied in the COLR, and used to calculate R ' since the RCS Total Flow Rate Versus R Sgure in the COLR includes measurement uncertainties of 2.1% (includes 0.1% for feedwater venturi l fouling) for flow,

d. FEP = The F$ limit at RATED THERMAL POWER specited in the COLR, and

{

e. PFm = The Power Factor MultipGer specified in the COLR.

l APPLICABILITY: MODE 1. t ACTION: - ! With the combination of RCS 10tal flow rate and R outside the region of acceptable operation specified in the COLR:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either.

1. Restore the combination of RCS total fluw rate and R to within the above limits, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux- High trip setpoint to less than or equal to 55%

of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

b. Wrthin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above lirruts, verify through a core power i

distribution measurement and RCS total flow rate comparison flat the combination of R and l RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . SUMMER UNIT 1 3/42-8 Amendment No. 45, " ,75, 88, 449r POWER DISTRIBUTION LIMITS LIMITING CONDITION FO} OPERATION - - _ _ _ ACTION: (Continued)

c. Identify and. corre':s the c.ause of the out-of-limit condition prior to increasmg THERMAL POWER above the reduced THERMAL POWER limit v requit ed by ACTION items a.2. and/or b. above; nubsequent POWER OPERATION may proceed provided that the combination of R and a c oce- P e r indicated RCS total flow rate are demonstrated, threugh : "--

ci t st c. ut , ,,,, mapptag and R"* total flow rate comparison, to be withm the region

e. u u ,u,,f ofacce followm,ptable ope t.ation speciHed in the COLR prior to exceeding the gTHERMALPOWERlevels:

1. A nominal 50% ofRATEDTHERMAL POWIR,

2. A nominal 75% of RATED THERMAL POWER, and

3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attainmg greater than or equal to 95% of RATED THERht% POWER.

SURVEILLANQE REQUIREMENTS , .. 4.2.3.1 The provisions of Specincation 4.0.4 are not applicabic. 4.2.3.2 The combination ofindicated RCS total flow rate and R shall be determined 1 to be within the region of acceptable operation specined in the COLR.

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

fuelloading, and l

b. Atle.ast once per 31 Effactive Full Power Days.

o.3.3 The indicated RCS total flow rate 5haD be veriRed to be within the region o eptable operation sp ecified in the COLR at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the l

most recertly obtained valus of ? btained per Specincation 4.2.3.2,is assumed to l exist. f.; l 9

4.2.3.4 The RCS total flow rate inteators sh11 be subjected to a CHANNEL CALIBRATION atleast once per 18 months. 4.2.3.5 The RCS total now rate shall be deteimined by heat balance measurement at 290% RATED THERMAL POWER at least once per 18 months. l ~ l 1 l SUMMEL UNIT 1 3'42-9 Amendment No. '45MR ! 119 l l I POWER DISTRIBUTION LIMITS LIMITING CONDIT!ON FOR OPERATION. . ACTION: (Continued)

c. Identify and correct the cause of tho out-of-limit condtion prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through a core power distribution measurement and RCS l total flow rate comparison, to be within the region of ex+3ete operation specified in the COLR prior to exceeding the fol!owing THERMAL POWER levels:

1. A nominal 50% of RATED THERMAL POWER,

2. A nominal 75% of RATED THERMAL POWER, and

3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

SURVEILLANCE_-_-n REQUIREME. NTS- . . - . - . , - - - .-----_-a , j 4.2.3.1 The provisions of Specification 4.0.4 are not applicable 4.2.3.2 The combination of indicated RCS total flow rate and R shall be determined to be i within the region of acceptable operation specified in the COLR.

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

b. At leat,t nace per 31 Effective Full Power Days.

4.2.3.3 The indicateo RCS total flow rate shall be verified to be within the region of acceptable operation specified in the COLR at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the most recently obtained value of R, obtained per Spe:ification 4.2.3.2, la assumed to exist. l I 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CAllBRATION at least once per 18 months. 4 2.3.5 The RCS total flow rate shall be determined by heat balance measurement at 290% RATED THERMAL POWER at least once per 18 rnonths. 4 SUMMER - UNIT 1 3/4 2-0 Amendment No. 45,75, SS, I 44Sr F Y - ..Ae - ~ - - . - .. -.- . - - . . . - - - . . - . - . ~ . . . . _ . . , - ~ . . - - ... . . + W Etesa POWER DISTRIBUTION LIMITS Lamot.uc. Coco % c Fop. Ope rst,'l , ~ ACTION: .(Continued) ~' 2. Reduce THERMAL POWER to less thart 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERFAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . 3. Identify and correct the cause of the out of limit conditica - prior to increasing THERMAL POWEP.; subsequent POER OPERATION above 50% of RATED THERMAL POW ~d may proceed p:ovided that the QUADRANT POWER TILT RATIO. is. verified-within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at, SS% or greater . RATED THERMAL POWER. d. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS , 4.2.4'.1 The QUADRANT POWER TILT MTIO shall be detamined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE. ~

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state operation when the ' alarm is inoperable. 4.2.4.2 The QUADRANT POWER TILT RATIO shak1 be determined to be within limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized -- symmetric power distribution. obtained from 2 sets of 4 symmetric.tMmble locations or a du24tcoh %x;dkD, is consistent with the indicated QUADRAFT POWER TILT RATIO at least oonce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . { w d.efL )*euv ebhYw .meeweem b

w. --

SUW4ER - UNIT 1 3/4 2-14 - . . ~ . . . . .-. . - . _ - . ._ .. . - . ~ . . . - - - . . - . - . . . .---. . .-- .s 4 4 POWER DISTRIBUTION LIMITS . LIMITING CONDITION FOR OPERATION =- l ACTION: (Continued)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Serpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

a

3. Identify and correct the cause of the out of limit condition prior to 1 increas.ing THERMAL POWER; subsequent POWER OPERATION l

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER. !' d. The provisions of Specification 3.0.4 are not applicable. SURVEILpNCE REQUIREMENTS ( 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit ! above 50% of RATED THERMAL POWER by: i j a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE.

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady state operation when the alarm is inoperable.

4.2.4.2 The OUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normaEzed symmetric i power distribution, obtained from 2 sets of 4 symmetric thimble locations or a core power I distribution measurement, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . } i SUMMER - UNIT 1 3/4 2-14 Amendment No. . - . .- . .~ . _.-.- . ~ . - . - . . . - . . . - . - - . . . - 4 L INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles, 7 b. A minimum of 2 detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the excore neutron flux detection system, ;

b. Monitoring the QUADRANT POWER TILT RATIO using a full-core flux map per Specification 4.2.4.2, or c.

MessurementofFhF(I q ACTION: l With the movable incere detection system inoperable', do not use the system for ; the above applicable monitoring or calibration functions. The provisions of 1 Specifications 3.0.3 and 3.0.4 are not applicable. ! l l SURVEILLANCE REQUIREMENTS I 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , by normalizing each detector output when required for:

a. Recalibration of the excore neutron flux detection system, or

b. Monitoring the QUADRANT POWER TILT RATIO, or c.

MeasurementofFh$F(Z) q SUMMER - UNIT 1 3/4 3-46 j INSTRUMENTATIO_N MOVABLE INCORE DETECTORS l LIMITING CONDITION FOR OPERATION _ _ _ _ _ - - _ _ _ _ _ . ii l 3.3.3.2 The movable incore detection system shall be OPERABLE with:

a. At least 75% of the detector thimbles.

l b. A minimum of 2 detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map thase l thimbles.

APPLICABILITY: When the movable incore detection system is used for:

a. Recalibration of the excore neutron flux detection system,

b. Monitoring the QUADRANT POWER TILT RATIO using a full-core flux map per Specification 4.2.4.2, or

c. Measurement of F1 and Fo(z).

ACTION: With the movable incore detection system inoperable, do not use the system for ths above applicable monitoring or cahbration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l SURVEILLANCE REQUIREMENTS - -- - - - - - - - mm 4.3.3.2 The movable incore detection system shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , by normalizing each detector output when required for:

a. Recalibration of the excore neutron flux detection system, or

b. Monitoiing the QUADRANT POWER TILT RATIO, or

c. Measuroment of FL and Fo(z).

l l l l L SUMMER - UNIT 1 3/4 3-46 Amendment No I o - - , - .,) INSTRUMENTATION i.s

u.n6@+ u-

,[ PgR DISTRIBtJTICN MONITORING SYSTEM LIMITING CONDITION FOR OPERATION Il1 3 3.3 The POWER DISTRIBtJTION MONITORING S'ySTEM (PDMS) shey be OPERABLE witn:

a. A minimum of the followin inputs from the plant.ameMe available for use by the PCMS as defined in Table 3.3.3 .

W ff

1. Control Bank Position

2. T.,

3. Reac*or Power Leve8 ,

- 4. N!S Power Range Detector Section Signals t). Core Exit Thermocouple? (T/C) meeting the Criteria:

1. At l east 25% cperat.'e T/C w;th at Isost 2 T/C per quadrant, and

2. e of att The within aT/C pattem chest.heeade has coveragk move, interior fuel asserr.blies (no fac knight

3. At teest 25% operacio TN w;th at least 2 T/C per cuacrant, and the installed POMS calitaation was determineo within the last 31 Effective Full Power Days (EFPD).

4. The T/C temperatures used by the PCMS are calibrated via cross ca:ibration with the loup temperature rneasurement RTDs, and using the T/C !!aw mixing fac: cts determined during installed PCMS calibration,

c. An instrJied POMS calibration satisfying the criteria:

1. The initial calibration in each operating cycle is determined ushg measurements from atleast 75% of the incere movable detector thimbles obtained at a THERMAL FOWER greater than r :c' : 25% of RATED THERMAL POWER.

2. The calibration is determined using measurement., from at least 50% of tne ine re movable detector thimbles at any time except as spec:fiec in 3.3.3R.c.1, and ,

// e

3. Th? calibration is determined using a rninimum of 2 detemor thimbies per core j quadrant. !

Afeve 2f % $ATra R AMAl. /k~cA . APPUCABILITY: MODE 1,, C IA . v -_~~IL l ~~[ i ACTICN: With any of the operabi!ity criteria fisted in 32.3Ma,3.3.3.hb, or 3.3.3.h.c not met, eith correct the d'eficient operability condition, or ceclare the POMS INOFERABLE and use the it. core movable detector system, satisfying the OPERASILITY requirements listed in specification 3.3.3.2, to obtain any required core power distribution measurements. Increase ~ the measured core peaking factors using the values listed in the COLR for the POMS . INOPEF.ASLE condition. 3 TOE AOtSides of' 3/t.c.daG.s .3 A ~lf .no 3.0N m pr ,44s,u,jg i Surn*ra ~ twtr i *~N peme,p ,f. . _ . _ . _ . ~ . . . . ~ . _ , _ .. _. . . _ . _ , .. _ . _ . - - l

l i

I i I . b" l6 Y t//T)GA/ W Tro k : l 1 J / ~ SUTVE11. LANCE REQUr.*EMEN1;E i // // li , it I 4.3.1)Jr.1 The operability critaria listed in 3.3.3./a. 3.3.3Mb and 3.3.3.M. shall be verited to be . satisfied prior to acceptance of the PCMS core pow *1 distribution measuremen' resuits. + r/ ) 4.3.3.J2.2 Calibmtion of the PDMS is required: a,c4 i' a. Et least'every 180 Effective Fdl Power Days when the rninimum number and core coverage entr.ria as defined in 3.3.3 b.1, and 3.3.3. b.2 are satisfied. or ma

b. at least' eve.*y 31 Effective Full Power days when only the minimum r. umber criterien as 1 I

defined in 3.3.3.J2!b.3 is satis 5ed.

//

l ! I i i 2 i 1 i 1 1 j iI i I 1. 3 s ummen- v MT .1 3/'f ~5 - 7 't Asuwomwr 114. e .. E ji ; IN#1RUMENTATIQt), p , !)QWER DNTRIBUTION MONEQRING SYSTEM I LIMITING CONDITION FOR OPERATION i 4 3.3 3.11 The Power Distribution Monitoring System (PDMS) shall be OPERABLE with:

a. A minimum of the following inputs from the plant available for use by the PDMS as defined in Table 3.3-14.

1. Control Bank Position i i-t

, 2. Tom o ! 3. Reactor Power Level

4. NIS Power Range Detector Section Signah j b. Core Exit Thermocouples (T/C) meeting the criteria:

j 1. At least 25% operable T/C with at least 2 T/C per quadrant, and l }' 2. The T/C pata.orn has coverage of allinterior fuel assemblies (no face along the baffle), within a chess knight's move, radally, from a j responding, calibrated T/C, or i j 3. At least 25% operablo T/C with at least 2 T/C per quadrant, and tne installed PDMS calibration was determined within the last 31 Effective { Fbil Power Days (EFPD). [ 4. The T/C temperatures used by the PDMS are calibrated via cross , calibration with the loop temperature measurement RTDs, and using the T/C tiow mixing factors determined during installed PDMS calibration.

c. An installed PDMS calibration satisfying the criteria

1

1. The initial caibration in each operating cycle is determined using f' measurements from at least 75% of the incore movable detector

thimbles obtained at a THERMAL POWER greater than 25% of RATED j THERMAL POWER.

i.

2. The calibration is determined using measurements from at least 50% of the incore movable detector thimbles at any time except as specified in 3.3.3.11.c.1, and

3. The calibration is determined using a minimum of 2 detector thimbles per core quadrant.

i SUMMER - UNIT 1 3/4373 Amendment No. . . . _ . -. -- - -. .. - - ~ _- INSTRUMENTATION ._LlMITING CONDITION FOR OPERATION (Continued) APPLICABILITY: MODE 1, above 25% RATED THERMAL POWER (RTP) ACTION: With any of the operability criteria hsted in 3.3.3.11.a. 3.3.3.11.b, or 3.3.3.11.c not met, either correct the deficient operability condition, or declare the PDMS inoperable and use the incore movable detector system, satisfying the OPERABILITY requirements listed in Specification 3.3.3.2, to obtain any required core power distribution measurements. Increase the measured core peaking factors using the values listed in the COLR for the PDMS inoperable condition. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.11.1 The operability criteria listed in 3.3.3.11.a, 3.3.3.11.b. and 3.3.3.11.c shall be verified to be satisfied prior to acceptance of the PDMS core power distribution measurement results. 4.3.3.11.2 Calibration of the PDMS is required:

a. at least once every 180 Effective Full Power Days when the minimum number and core coverage criteria as defined in 3.3.3.11.b.1 and 3.3.3.11.b.2 are satisfied, or

b. at least once every 31 Effective Full Power Days when only the minimum number criterion as defined in 3.3.3.11.b.3 is satisfied.

6 i a a SUMMER - UNIT 1 3/4 3-74 Amendment No.

1 Ti t/3 7?ls/912WTA T to!J 1

I l l l l l l l i /f TABLE 3.3.3J- ef l REQUIRED FDMS PLANT INPUT INFORP.'ATION ~ l PLANT INPUT INFORMATION AVAILABLE MINIMUM NO. OF APPLICABLE l INPUTS VALID hiPUTS MODES Control Bank Pcsition 4 4' 1* 1. 3 2 1'

2. T.

3 1* 1*

3. Reacter Power Level N!S Power Range Execre Detector 8 6* l' 4.

Section Signals ~ TABLE NOTATIONS l

a. Determined frem either valid Demand Positierter the average of the valid individur.1 ACCA I position indications for all RCCAs in the Control Bank.

b. Determined frcm either the reacter thermal power derived using a valid secondary calorimetric measurement, the average NIS Power Range Dete:ter Pcwer, or the average RCS Loop AT.

c. [ eater than : :q.;' t: 25% RTP

d. Th: w=f a"-W c' u=M 37* -' + M comp !::d :f : :=p:ndn; upp : .d !::::: de;d;-

ci

n: :;n& !n :::'. :/C:: "::::r ".:ng: C:::d:: Ch:nn:!.-

c..nnaw .c,,a,yve aa w , 4,,,a sses,,as,;_ ,, ,a ,,, I'*~c M me ch d j a se,a,an d 2 _. u cg ,,, ,,p,;,,,, bM.A0lE 5 ummu -uhT 1 3/4 3 ~75~ ,4 ,,,a a ,,e n p s. i l INSTRUMENTATION l l TABLE 3.314 l REQUIRED PDMS PLANT INPUT INFORMATION l PLANTINPUTINFORMATION AVAILABLE MINIMUM NO. OF APPLICABLE INPUTS VALID INPUTS MODES

1. Control Bank Position 4 4* 1'

2. Tm 3 2 1'

3. Reactor Power Level b l 3 1 1'

4. NIS Power Range Excore Detector 8 6 d

1* ! Section Signals l TABLE NOTATIONS l l

a. Determined from either valid Demand Position or the average of the valid individual RCCA position indications for all RCCAs in the Control Bank.

b. Determined from either the reactor THERMAL POWER derived using a valid secondary l calorimetric measurement, the average NIS Power Range Detector Power, or the average RCS Loop AT.

c. Greater than 25% RTP.

d. Comprised of an upper and lower detector section signal per Power Range Channel; a minimum of 3 OPERABLE channels required.

i. i SUMMER - UNIT 1 3/4 3-75 Amendment No. POWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) x The hot channel factor F q(z) is measured periodically and increased by a 1:- .22'5&T / cycle Load operation, and height W(zdep)endent or W(z)BL, topower providefactor assurance appropriate to ei'ther that the limit RAOC or Base on the hot channel factor, F Q(z) is met. W(z) accounts for the effects of normal opera-tion transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)BL accounts for the more restrictive operating limits allowed by Base Load operation which result in less severe transient values. The W(z) and W(z)BL functions described above for normaloperation are specifiedin the CORE OPERATING LIMITS REPORT (COLR) per Specification 6.9.1.11. - grerr z ~ q n RCS flow r and Fa are asured, no addition allowances ar nece . prior to co arison with the imits of the RCS To Flow Rate Ve R figurein e COLR. Meas ment errors of2.15 orRCS total fl rate includ* 0.1%forfeedwa rventurifouling 4% for l a have bee allowed forin de inmg the limits o e RCS Total w Rate Versu figure in the C . The 12-hour periodic surveillance ofindicated RCS flow is sufficient to I detect only flow degradation which could lead to operation outside the acceptable l region of operation specified on the RCS Total Flow Rate Versus R figure in the j COLR. 1 3/4.2.4 QUADRANT POWER TILT RATIO 1 The quadrant power tilt ratio limit assures that the radial power distribution I satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup testing and periodically during power operation. The limit ofi.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of1.025 can be tolerated before the margin for uncertamty in l Fq is depleted. The limit of1.02 was selected to provide an allowance for 1 the uncertainty associated with the indicated power tilt. The two hour time allowance for operation with a tilt condition greater than 1.02 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 Fq is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of1.0. For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is moperable the movable incore detector are used to confirm that the normalized symmetric power distribution i o sistent with the QUADRANT POWER TILT RATIO. The incore detector mo itoringis done with a fullincore . flux map or two sets of 4 symmetric thimbles. ese locations are C-8, E-5, E-11, H 3, H-13, I,5, L-11, N-8. - - ,. ye a foW Cooe power b+eobefin meceemen SUMMER - UNIT 1 B 3/4 2-4 Amendment No. hk 119 9 i l , l l l l' ! I Insert 1 iI - For measurements obtained using the Power Distribution Monitoring System (PDMS), the appropriate measurement uncenainty is determined using the measurement uncertamty methodology contained in WCAP 12472-P-A. The cycle and plant uncertainty calculation information needed to support the PDMS calculation is contained in the COLR. The ; PDMS will automatically calculate and apply the correct measurement uncertamty, and apply a 3% allowance for manufacturing tolerance. 1 i Insert 2 I When RCS flow rate is measured, no additional allowances are necessary prior to l comparison with the limits of the RCS Total Flow Rate Versus R Figure in the COLR. Measurement errors of 2.1% for RCS total flow rate, including 0.1% for feedwater venturi fouling, have been allowed for in determining the RCS Total Flow Rate Versus R Figure in the COLR. l l For F"a measurements obtained from a full core flux map taken with the incore detector ~ l ! flux mapping system, a 4% measurement uncenamty allowance should be applied to the N measured F Value prior to Comparison with the limits of the RCS Total Flow Rate Versus R Figure in the COLR. The appropriate measurement uncertainty for F"a measurements obtained using the Power Distribution Monitoring System (PDMS)is i determined using the uncertainty methodology described in WCAP 12472-P-A. The cycle ! and plant specific uncertainty calculation information needed to support the PDMS l uncertainty calculation is contained in the COLR. The PDNIS will automatically calculate and apply the conect measurement uncertainty to the measured F*m. I 4 1 r POWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued) For measurements obtained using the Power Distribution Monitoring System (PDMS), the appropriate measurement uncertainty is determined using the measurement uncertainty methodology contained in WCAP 12472-P-A. The cycle and plant specific uncertainty calculation information needed to support the PDMS calculation is contained in the COLR. The PDMS will automatically calculate and apply the correct measurement uncertainty, and apply a 3% allowance for manufacturing tolerance. The hot channel factorFs(z) is measured periodcally and increased by a cycle and height dependent power factor aopropriate to either RAOC or Base Load operation, W(z) or W(z)st, to provide assurance that the limit on the hot channel factor, Fo(z)is met. W(z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. W(z)st accounts for the more restrictive operating limits allowed by Base Load operation which result in less severe transient values. The W(z) and W(z)st functions described above for normal operation are specified in the CORE OPE RATING LIMITS REPORT (COLR) per Specifcation 6.9.1.11. When RCS flow rate is measured, no addtional allowances are necessary prior to comparison with the limits of the RCS Total Rate Versus R figure in the COLR. Measurement errors of 2.1% for RCS total flow rate, including 0.1% for feedwater venturi fouling, have been allowed for in determining the RCS Total Flow Rate Versus R Figure in the COLR. For F1 measurements obtained from a full core flux map taken with the incore detector flux mapping system, a 4% measurement urcertainty allowance should be applied to the measured F1 value prior to comparison with the limits of the RCS Total Flow Rate Versus R Figure in the COLR. The appropriate measurement uncertainty for F1 measurements obtained using the Power Distribution Monitoring System (PDMS) is determined using the uncertainty methodology described in WCAP-12472 P A. The cycle and plant specific uncertainty calculation information needed to support the PDMS uncertainty calculation is contained in the COLR. The PDMS will automatically calculate and apply the correct measurement uncertainty to the measured F1 value. The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which would lead to operation outside the acceptable region of operation specified on the RCS Total Flow Rate Versus R figure in the COLR. 3/4.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt power ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power dstribution measurements are made during startup testing and periodically during power operation. SUMMER - UNIT 1 B 3/4 2-4 Amendment No n 45,75, M, 4497 POWER DISTRIBUTION LIMIT BASES Q UA OKehn fewS!L TIUT t{A Tro IIEAT FLUX HGT CEANNEL FACTOR oud RCS FLC"/ RATE end NUCLEA" ENTuAL"Y RISE IIGT CHANNEL FACTGR (Continued) 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelow of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have be'en analytically demonstrated adequate to maintain a minimum DNBR in the core at or above the design limit throughout each analyzed transient. The maximum indicated Tavg limit of 589.2*F and the minimum indicated pressure limit of 2206 psig correspond to analytical limits of 591.4*F and 2185 psig respectively, read from control board indications. The 12-hour 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. SUMMER-UNIT 1 B 3/4 2-5 Amendment No. h l 1 . I POWER DISTRIBUTION LIMIT BASES QUADRANT POWER TILT RATIO (Continued) ! The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x y plane power tilts. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in Fo is depleted. The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt. The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control l rod. In the event such action does not correct the tilt, the margin for uncertainty on Fo is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in , excess of 1.0. For purposes of monitoring OUADRANT POWER TILT RATIO when one excore detector is inoperable, the moval 'e incore detectors or a core power distribution measurement are used to confirm that the normalized symmetric power distribution is consistent with the OUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of 4 symmetric thimbles. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8. 3/4.2.5 DNB PARAMETERS . The limits on the DNB related parameters assure that each of the parameters 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 of DNBR in the core at or above the design limit throughout each analyzed transient. The maximum indicated Tm limit of 589.2'F and the minimum indicated pressure limit of 2206 psig correspond to analytical limits of 591.4'F and 2185 psig respectively, read from control board indications. The 12-hour periodic surveillance of tnese paraPeters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation. SUMMER - UNIT 1 B 3/4 2-5 Amendment No 15, "", SO,75, ??(c),

19,

INSTRUMENTATION BASES 3/4.3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with th requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 C2R Part 50. 3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION The OPERABILITY of the loose part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-:f-service times and surveillance requirements are consistent with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981. A/ W h E 3/4.3.3.k POWER DISTRIBUTION MONITORING SYSTEM (PDMS) The Power Distribution Monitoring System (PDMS) provides core monitoring of the limitin parameters. The PDMS continuous core power distribution measurement method with the periodic generation of a highly accurate 3-D nodal simulation of the current reactor power distribution. The simulated reactor power distribution is then continuously nodal and thermocouple calibration factors derived from an incore power distribution measurement obtained using the incore movable detectors to produce a highly accurate powe distribution measurement. The nodal calibration factors are updated at least once ever Effective Full Power Days (EFPD). Between calibrations, the fidelity of the measured p distribution is maintained via adjustment to the calibrated power distribution provided by continuously input plant and core condition information. The plant and core condition - utilized by the PDMS is cross checked using redundant information to provide a r for continued operation. Tne loop iniet temperature is generated by averaging the re temperatures from each of the loops, excluding any bad data. The core exit th provide many readings across,the core and by the nature of their usage with smoothing of the measured data and elimination of bad data is performed with t Spline fit. The PDMS uses the NIS Power Range excore detectors to provide Range information on the axial power distribution. Hence, the PDMS averages the data from the four P excore detectors and eliminates any bad excore detector data. SUMMER - UNIT 1 B 3/4 3-4 Amendment No. MW i , . I INSTRUMENTATION BASES 3/4.3.3.9 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring and controlling the l concentrations of potentially explosive gas mixtures in the waste gas holdup system. The i l OPERABILITY and use of this instrumentation is consistent with the requirements of General l l Design Criteria 60,63 and 64 of Appendix A to 10 CFR Part 50. l 3/4.3.3.10 LOOSE-PART DETECTION INSTRUMENTATION 1 l The OPERABILITY of the loose-part detection instrumentation ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary systern components. The allowable out-of-service times and surveillance requirements are consiHp with the recommendations of Regulatory Guide 1.133, " Loose-Part Detection Program t i..e Primary System of Ught-Water-Cooled Reactors," May 1981. l 3/4.3.3.11 POWER DISTRIBUTION MONITORING SYSTEM (PDMS) Thn Power Distribution Monitoring System (PDMS) provides core monitoring of the limiting parameters. The PDMS continuous core power distribution measurement methodology begins with the periodc generation of 9 highly accurate 3-D nodal simulation of the current reactor power distribution. The simd ad reactor power dstribution is then continuously adjusted by nodal and thermocouple (,alibration factors derived from an incore power distribution measurement obtained using the incore movable detectors to produce a highly accurate power distribution measurement. The nodal calibration factors are updated at least once every 180 Effective Full Power Days (EFPD). Between calibrations, the fidelity of the measured power distribution is maintained via adjustment to the calibrated power dstribution provided by continuously input plant and core condition information. The plant and core condition data utilized by the PDMS is cross checked using redundant information to provide a robust basis for continued operation. The loop inlet temperature is generated by averaging the respective temperatures from each of the loops, excludng any bad data. The core exit thermocouplet provide many readings across the core and by the nature of their usage with the PDMS, smoothing of the measured data and eliminationi of bad data is performed with the Surface Spline fit. PDMS uses the NIS Power Range excore detectors to provide information on the axial power distribution. Hence, the PDMS averages the data from the four Power Range excore detectors and eliminates any bad excore detector data. The bases for the operability requirements of the PDMS is to provide assurance of the accuracy and reliability of the core parameters measured and calculated by the PDMS core power distribution monitor function. These requirements fall under four categories: l 1. Assure an adequate number of operable critical sensors.

2. Assure sufficiently acccmte calibration of these sensors.

3. Assure an adequate calibration data base regarding the number of data sets.

l 4. Assure the overall accuracy of the calibration. SUMMER - UNIT 1 8 3/4 3-4 Amendment No. M4r / 4.3 INSTRUMENTATION BASES . kss'Ett DistnigvToy /t fw/ Tow & ftsstem fcon%xd)' provide assurance of the ' The bases for the operability requirements of the P'DMS ,is pt S accuracy and reliability of the core parameters measureddcalculate power distribution monitor function. These requirements fall unde

1. Assure an adequate number of operable critical se:tsers.

2. Assure sufficiently accurate calibration of these sensors.

3. Assure an adequate calibration data base regarding the number o

4. Assure the overall accuracy cf the calibration.

The minimum number of required plant and core condition inputl

1. Control Bank Positions.

2. At least 50?o of the cold leg temperatures.

l 3. t least 757, of the signals from the Power Range execre detector c (comprised of a top and bottom detector section). 1 I

4. Reactor Power 1.evel.

5. A minimum number and distribution of operable core exit thermocouples.

6. A minimum number and distribution of measured fuel assembly power distribution infonnation obtained using the incore movable detectors is incorporated in the nodal model calibranon information.

The sensor calibration of items 1.,2.,3., and 4. above are covered under other specifications. Calibration of the core exit thermocouples is acccmplished in two parts. Tne first being a sensor specific correction to K-type thermocouple it.mperature indications based on data from a cross calibration of the thermocouple temperature i1dications to the average RCS temperature measured via the RTDs under isotherma' RCS conditions. The second part of the thennoccuple calibration is the generation of thermocouple flow mixing factors which cause the radial power distribution measured via the thrmoccupies to agree with the radial power distribution from a full core flux map measured using the incere movable detectors. This calibration i.s updated at least once every 180 EFPD. SummErL: UtitN g y/Y35 / kmeue AedT/f4, INSTRUMENTATION BASES POWER DISTRIBUTION MONITORING SYSTEM (PDMS) (Continued) The minimum number of required plant and core condition inputs includes the following:

1. Control Bank Positions.

2. At least 50% of the cold leg temperatures.

3. At least 75% of the signals from the Power Range excore detector channels (comprised of a top and bottom detector section).

4. Reactor Power Level.

5. A minimum number and distribution of operable core exit thermocouples.

6. A minimum number and distribution of measured fuel assembly power distribution information obtained using the incore movable detectors is incorporated in the nodal model calibration information.

The sensor calibration of items 1.,2., 3., and 4. above are covered under other specifications. Calibration of the core exit thermocouples is accomplished in two parts. The first being a sensor specific correction to K-type thermocouple temperature indications based on data from a cross calibration of the thermocouple temperature indications to the average RCS temperature measured via the RTDs under isothermal RCS conditions. The second part of the thermocouple calibration is the generation of thermocouple flow mixing factors which cause the radial power distribution measured via the thermocouples to agree with the radial power distribution from a full core flux map measured using the incore movable detectors. This calibration is updated at least once every 180 EFPD. SUMMER - UNIT 1 B 3/4 3-5 Amendment No. ADMINISTRATIVE CONTROLS - 6.9.1.9 Not used. ~ MONTHLY CPERATING REPORT 6.9.1.10 Routine recerts of operating statistics and shutacwn experience, in-ciuding documentation of all challenges to the PORV's er safety valves, shall be submitted on a monthly basis to the Direccor, Office of Rescurce Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a ecpy to the Regional Office of Inspection and Enforcement, no later than the 15th of eacn month following the calendar month covered by the report. A report of any major changes to the radioactive waste treatment systems shall be suomitted with the Menthly Operating Report for the peried in which the W evaluatien was reviewed and accepted as set forth in 6.5 above. CORE OPERATING LIMITS REPORT 6.9.1.11 Core coerating limits shall be established and documented in the CORE CPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining , pertien cf a reload cycle, for the following:

a. Moderater Temperature Coefficient EOL and EOL Limits and 300 pps surveillance limit for Specification 3/4.1.1.3,

'b . Dutdcwn Rod Insertion Limit for Specification 3/4.1.3.5,

c. Centrol Red Insertion Limits for Specificatien 3/4.1.3.5,

d. Axial Flux Difference Limits, target band, and APLND for = __u Specificatien 3/4.2.1, pdFm m J, q /

q

e. Heat Flux Het Channell Factor, , K(Z), W(Z), APL @ W(Z)BL for Specification 3/4.2.2, ,r 3 l RTP

f. Nuclear Enthalpy Rite Hot Channel Factor, Fg..Ame' Power Facter - -

Multiplier, PFg, dimits for Specification 3/4.2.3. Q~pg ,ytg The analytical metheds used to detemine the core operating limits shal *# " those previously reviewed and approved by the NRC, specifically tacse described in the following documents:

a. WCAP-9272-P-A, ' WESTINGHOUSE RELOAD SAFETY EVALUATION METriOOOLOGY,'

July 1985 (W Proprietary). i SU9iER - UNIT 1 6-16 Amenc=ent No. H,22,IM,117 l ._ _. -. m__ . _ _ . _ _ . . .. . _ . _ _ _ _ . _ _ - _ _ . . . . . _ _ . _ . - . . . . ._.___ _ _ _ ADMINISTRATIVE CONTROLS 6.9.1.9 Not used. MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, includng l documentation of all challenges to the PORV's or safety valves, shall be submitted on a ' monthly basis to the Director, Office of Resource Management U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report. A report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted as set forth in 6.5 above. CORE OPERATING LIMITS REPORT 6.9.1.11 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a. Moderator Temperature Coefficient BOL and EOL Limits and 300 ppm serveillance limit for Specification 3/4.1.1.3,

b. Shutdown Rod insertion Limit for Specification 3/4.1.3.5,

c. Control Rod Insertion Umits for Specification 3/4.1.3.6,

d. Axial Flux Difference Umits, target band, and APL"for Specification 3/4.2.1,

e. Heat Flux Hot Channel Factor, Fj", K(z), W(z), APL*, W(z)st, and Fo(z) manufacturing / measurement unceriainties for Specification 3/4.2.2,

f. Nuclear Enthalpy Rise Hot Channel Factor, F%P 3 , Power Factor Multiplier, PF,g , and FE measurement uncertainties limits for Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

a. WCAP-9272-P-A," WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY," July 1985 (W Proprietary).

J SUMMER - UNIT 1 6-16 Amendment No. 79,89,101,**7, 1 ( ADMINISTRATIVE CONTROLS l CORE OPERATING LIMITS RE' PORT (Continued) \ i on (Methodology for Specification 3. 1.3 - Moderator Temperature l g,3 _ CnaW ent,3.1.3.5 - Shutdown Insertion Limit,3.1.3.6 - Contro%ek Insertion Limit,3.2.1 - Anal Flux Difference,3.2.2 - l Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot ChannelFactor). 3 4 , g i b. WCAP-10216-P-A,Rev.1A," RELAXATION OF CONSTANT AXIAL i l OFFSET COh L FQ SUEVEILLANCE TECILNICAL SPECIFICATIO ebruary1994 (WProprietary). ) i (Methodologyfor Specifications 3.2.1 - Axial Flux Difference (Relaxed Azial Offset ControD and 3.2.2 - Heat Flux Hot Channel Factor (Fg Methodology for E(2) surveillance requirementG4) I i c. WCAP 10266-P-A, Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987; Including

i Addendum 2-A " BASH METHODOLOGY IMPROVEMENTS AND RELIABILITY ENHANCEMENTS," MAT 1988, (W Proprietary).

M7 (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor). The core operatinglimits shall be determined so that all applicable limits I (e.g., fuel thermal-mech e ical limits, core thermal-hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including anymid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desh with. copies to the Regional Administrator and ResidentInspector.

d. WCAP- l1912- e-h, " BescoM c..re m.dekr) u.t 4-kns .%,.o.4

~ Adml' Ayd- Inb (W hpchry). (thAJAp r., spekk.- 3/2. 2.- 66 % M d'ad l 123 _ gc3 m RAe ..,, sc.(d n+LH gm A+ h 4 i Fu.h ,, . 4 3,2,4 . A g A. % , y a A b ), SUMMER -UNIT 1 6-16a Amendment No.ff jl,fp, I23 t r _. . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ . ~ . _ _ _ - _ _ _ _ _ _ _ l . 1 ADMINISTRATIVE CONTROLS I CORE OPERATING LIMITS REPORT (Continued) (Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod insertion Limit, 3.1.3.6 - Control Rod Insertion Limit, 1 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor.)

b. WCAP-10216-P-A, Rev.1 A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fo SURVEILLANCE TECHNICAL SPECIFICATION", February 1994 l (W Proprietary). 1 (Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (Fo Methodology for l

W(z) surveillance requirements)).

c. WCAP-10266-P-A, Rev. 2, "TH851981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987; including Addendum 2-A," BASH METHODOLOGY IMPROVEMENTS AND RELIABILITY ENHANCEMENTS", May 1988, (W Propriotary). l (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor),

d. WCAP-12472 P A," BEACON CORE MONITORING AND OPERATIONS SUPPORT SYSTEM", August 1994, (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - RCS Flow Rate and Nuclear ' nthalpy Rise Hot Channel Factor, and 3.2.4 - , Quadrant Power Tilt Ratio). I The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal- l mechanical limits, core thermal-hydraulic limits, nuclear Emits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. , The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements there to shall be provided upon issuance, for each reload cycle, to the tJRC Document Control Desk with copies to the Regional Administrator and Resident inspector. SUMMER - UNIT 1 6-16a Amendment No. 88,121,133, Documtnt Control D sk Attachm:nt ll TSP 970006 RC-98-0168 Page 1 of 9 l l SAFETY EVALUATION i FOR REVISING THE TECHNICAL SPECIFICATIONS i l TO INCORPORATE BEACON l lN THE VIRGIL C. SUMMER NUCLEAR STATION TECHNICAL SPECIFICATIONS Description of Amendment Reauest The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) are being revised to incorporate a Power Distribution Monitoring System (PDMS). This system utilizes a NRC approved Westinghouse Proprietary Computer System, the Best Estimate Analyzer for Core Operations - Nuclear (BEACON), to augment the functionality of the flux mapping system for purposes of power distribution surveillances. The proposed Technical Specification Changes allow the use of the PDMS to perform core power distribution surveillances. However, the PDMS is only . used when Thermal Power is greater than 25% RTP. At Thermal Powers less than or I equal to 25% RTP or when the PDMS is inoperable, the movable incore detector ! system will be used. The existing Technical Specifications require the surveillances to l l be performed using the movable incore detector system. The affected Technical Specifications are: (a) 3/4.1.3 Movable Control Assemblies - Group Height (b) 3/4.2.2 Heat Flux Hot Channel Factor (c) 3/4.2.3 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel Factor (d) 3/4.2.4 Quadrant Power Tilt Ratio (e) 3/4.3.3.11 Power Distribution Monitoring System (f) 6.9.1.11 Core Operating Limits Report in addition, one section is added to the Core Operating Limits Report (COLR). This section defines the equations and constants used to determine the applicable measurement uncertainties applied to the core peaking factors when determined by l either the PDMS or the flux mapping system. The constants found in this section of the COLR are used as coefficients in the uncertainty calculations and are determined using l NRC-approved methodology. The constants may be revised periodically as appropriate l to reflect cycle-specific variables. The NRC approved WCAP-12472-P-A (Topical Report for BEACON) on February 16, 1994. The NRC concludes that BEACON provides a greatly improved continuous on-line power distribution measurement and display, limit surveillance, and operation prediction information system for Westinghouse reactors. d f L i i

Docum: nt Control Desk Attacnment ll i i

TSP 970006 RC-98-0168 Page 2 of 9 Virgil C. Summer Nuclear Station is proposing to implement BEACON to augment the

functionality of the flux mapping system for purposes of power distribution j surveillances. The Technical Specification changes discussed in WCAP-12472-P-A

are applicable to an application of BEACON in which the core power distribution limits i

are changed and BEACON is monitored continuously by plant operators. For the 4 application of BEACON to Virgil C. Summer, the premise is that BEACON will be used for power distribution measurement instead of the flux mapping system when Thermal

Power is greater than 25% RTP. All power distribution limits remain unchanged. Thus,

.; the VCSNS use of the BEACON system is a more restrictive application than is approved in the WCAP. In this application, if the PDMS meets specified operability requirements (i.e., operability of incore detectors, core exit thermocouples, and excore detectors), it is 2 used to determine the measured core peaking factors. The power distribution l surveillance continues to be performed with the same periodicity (once every 31 EFPD ] under normal circumstances, although more frequent surveillances may be required i under certain circumstances) 1 l s Safety Evaluation The use of BEACON as a power Distribution Monitoring System has no impact upon plant operation or safety. No safety-related equipment, safety function, or plant operations will be altered as a result of this proposed change. Since the applicable FSAR limits will be maintained and the Technical Specifications will continue to require operation within the core operational limits calculated by these NRC-approved methodologies, this proposed change is administrative in nature. Appropriate actions to be taken if limits are violated also remain unchanged in the Technical Specifications. This proposed change will control the cycle-specific parameters within the acceptance criteria and assure conformance to 10 CFR 50.36 by using the approved methodology instead of specifying Technical Specifications values. The COLR will document the specific parameter limits resulting from VCSNS calculations, including mid-cycle or other revisions to parameter values. Therefore, the proposed change is in conformance with the requirements of 10 CFR 50.36. Any changes to the COLR will be made in accordance with the provisions of 10 CFR 50.59. From cycle to cycle, the COLR will be revised such that the appropriate core operating limits for the applicable cycle will apply. The facility Technical Specifications will not require future changes associated with core parameters. -. ~ - -- - _ . - - Document Control D:sk Attachmtnt il TSP 970006 RC-98-0168 Page 3 of 9 i The following is a summary / excerpt of BNLs Technical Evaluation Report (TER) for WCAP-12472-P-A. The section numbers and titles are those specified in the TER. .BNLs Technical Evaluation Report (TERh 2.1 BEACON On-line Core Monitorina Methodoloav: 2.1.1 Determination of the Core Power Distribution 4 The primary function of the BEACON core monitoring system M the determination of the three-dimensional core power distributiori. 6 BEACON, this calculation is performed with the NRC arproved Westinghouse SPNOVA nodal method. The SPNOVA data libratif.s and core models are consistent with the NRC approved Westinghous6 PHOENIX /ANC design models and hava been extensively benchmarked against operating reactor measurements. 2.1.2 Calibration of the Core Power Distribution: BEACON uses the incore flux detector measurements, core-exit thermocouples and excore detectors to perform the local calibration of the SPNOVA three-dimensional power distribution. The SPNOVA predicted detector reaction rates are normalized to the incore measurements at the incore radial locations and over an axial mesh. The thermocouple adjustment is two dimensional and is made by normalizing the SPNOVA radial power distribution to the assembly power inferred from the core-exit thermocouples. The thermocouple assembly power measurement is periodically calibrated to the incore-measured assembly power. The incore detectors and core-exit thermocouples do not provide complete coverage of the core and BEACON employs a two-dimensiorial spline fit to interpolate / extrapolate these measurements to the unmonitored assemblies. The spline fit includes a tolerance factor which controis the degree to which the fit is forced to match the individual measurements. If, l for example, the measurements arr< believed to be extremely accurate

(inaccurate) a low (high) tolerance factor is used and the SPNOVA solution is (not) forced to be in exact agreement with the measurements.

The BEACON axial power shape is adjusted to insure agreement with the axial offset measured by the execre detectors. This adjustment is made by adding a sinusoidal component to the SPNOVA calculatad axial power shape. The SPNOVA excore axial offset is determined by an appropriate weighting of the peripheral assembly powers. The excore

detector axial offset is periodically calibrated to the incore detector

! measuremont. l - - . - .. - - . - . - - - . .. ~ _ _ - . - . .. .. - ... - - - - . -

~

Documsnt Control D sk Attachment il TSP 970006 ! RC-98-0168 Page 4 of 9 i 2.1.3 BEACON Core Monitorina Methodoloay: i The BEACON core monitoring process is canied out in three steps. In I the first step tha SPNOVA model, individual thermocouples, and the I excore axial offset tr.re calibrated to the full-core incore ifux i measurement. In the second step, the SPNOVA modelis updated I based on the most recent operating history, and adjusted using the thermocouple and excore measurements. The continuous monitoring is performed in Step-3 using the thsrmccouples and excores to update the l , BEACON model. ! The continuous core rnonitoiing of the current reactor statepoint (fuel l burnup, xenon distribution, soluble boron concentration, etc.) provided I by BEACON allows a more precise determination of the parameters . used in the transient analyses, and therefore relaxes the requirement to L limit the transient initial conditions via power distribution control. As part , of the continuous monitoring, the fuellimits are calcu!ated using the standard Westinghouse methods. VCSNS BEACON application does not take credit for the continuous monitoring of the power distribution. Therefore, the transient initial conditions limits via power distribution control are not allowed to be relaxed. This results in the peaking factor limits at VCSNS remaining unchanged from the existing limits. 2.2 Comoarison of BEACON and INCORE Power Distributions: As an initial assessment of the power distribution calculation. Westinghouse has performed detailed comparisons of BEACON to the predictions of the INCORE System presently used at Westinghouse )

plants. Tliese cornparisons were made for three plants over four cycles, ;

, and included a range of fuel burnup, core loadings, power level and l 3 control rod insertion. For the high powered assemblies (P > 1), a BEACON reproduced a set of axially integrated ineasurements to within a few percent. The BEACON and INCORE axially integrated assembly , powers also agreed to within a few percent for a sample of high powered { assemblies. The uncertainties applied to the BEACON power distribution meusurements are different than those applied to the traditional flux map systems because BEACON uses a more comprehensive set of instrumentation. An uncertainty analysis of the BEACON power d.istribution measurement is reported in WCAP-12472 P-A. Since the power distribution measurement methodology is the same between BEACON and the VCSNS application of BEACON, the uncertainty anahsis and methodo;ogy is applicable to the Docum:nt Control Desk Attachment ll - TSP 970006 RC-98-0168 Page 5 of 9 ! i 1 VCSNS application of BEACON. Portions of the BNL TER relevant to the uncertainty analysis are excerpted as follows. 1 2.3 Determination of ti,e BEACON Uncertainty Components: i

2.3.1 ModelCalibration:

,. l l 4 Due to the change in reactor statepoint, EPNOVA modehng l approximations and instrumentation error, a model calibration uncertainty ) is introduced into the BEACON predictions. Westinghouse has l

evaluated this uncertainty by comparing BEACON predicted and

, measured incore t eaction rates over four cycles and a range of opetating j conditions, and has found that the model calibration uncertainty was very i smaH and varied only slightly for these comparisons. i 2.3.2 _T_h_ermocouole Calibration: l The thermocouple calibration uncettainty is due to the change in reactor statepoint and to instrument error. Westinghouse has evaluated this - uncertainty by comparing the assembly powers infened from the thermocouples to SPNOVA incore-corrected assembly powers. ! Comparisons for three plants and a range of operating conditions ! indicate a difference of less than a few percent at full power. The observed calibration uncertainty increased at lower powers due to the

reduced enthalpy rise and changes in cross-flow.

t 2.3.3 Axial Power Distribution IJncertainty:

in order to determine the axial power distribution uncertainty,. ;

! Westinghouse has compared SPNOVA incore-updated and SPNOVA i . excore-updated predictions of the axial power shape. These

comparisons included a range of fuel bumups and red insertions, and

indicated a 95/05 upper tolerance limit of less than a few percent with a slight dependence on rod movement since calibration.

h 2.3.4 Calibration interval: j Based on Sn extonsive set of calibration data, the model calibration uncertainty is observed to increase as the calibration intorval (in units of

j. fuel buniup) increases. Using the observed fuel bumup dependence, an i additional casembly power uncertainty is determined to account for the effects of increased calibration interval.

i. 4 i i Document Control D:sk Attachment il TSP 970006 l RC-98-0168 l Page 6 of 9 I 2.3.5 Inocerable Detectors: The failure of detectors in the BEACON system results in a r61axation of the local calibration to measurement, and an increase in the power distribution uncertainty. The effect of random failures of the incore and thermocouple detectors on the assembly power was evaluated for failure rates of up to 75%. It is noteworthy that the assembly power uncertainty was found to increase lineady with incore detector failure and quadratically with the failure of thermocouples. 2.3.6 Local Power Distribution Uncertainty: The BEACON calculation requires local power distribution factors for: (1) the ratio of assembly power-to-detector response, (2) assembly local peaking factor, and (3) the grid power-depression factor. The BEACON uncertainty analysis employs previously approved upper tolerance values for the assembly ower-to-detector response ratio and the local peaking factor. The gi . actor uncertainty was determined by comparison to meas' flux traces and is found to be relatively small. 2.4 Determination of the BEACON Power Peakina Uncedainty: The uncertainty in the BEACON power peaking resulting from errors in the SPNOVA model calibration and thermocouple calibration is determined using an analog Monte Carlo error propagation technique. In this analysis, the BEACON three-step calibration, model update and power distribution update procedure is simulated. The SPNOVA model and thermocouple calibration factors are subjected to random variations l (based on their uncertainties) and the resulting variations in the BEACON power distribution are used to determine the 95% probability upper tolerance limit on the assembly power for the twenty highest powered assemblies. The analysis is performed for a range of operating conditions including off-normal power distributions and extended calibration intervals. A typical set of thermocouple uncertainties is used together with a relatively large tolerance factor which results in substantial smoothing of ' the thermocouple measurements. The upper tolerance limit on the I assembly power peaking factor is calculated and found to increase as l the square-root of the thermocouple uncertainty. I l . . . ~ .. - - - - . - . - - - - - .. - - . . . - ._ . -. .. . Docum:nt Control Desk - Attachment ll TSP 970006 RC-98-0168 Page 7 of 0 4 The enthalpy-rise (FAH ) and power peaking factor (Fa) unce:1ainties are determined by a statistical combination of the assembly peaking factor, l axial peaking factor, calibration interval, inoperable detector and local

power peaking component uncertainties. The Fas and Fo uncertainties

are calculated for a typical case.

3.0 Summa.v of the Technical Evaluation: } The BEACON Core Monitoring and Operations Support System Topical Report WCAP-12472-P provides a detailed description of the BEACON , methodology, the uncertainty analysis required to support the proposed Technical Specifications and the operation of the overall system. The review of REAOON focused on the approximations and assumptions impscit in the BEACON methodology, the completeness and accuracy of l the BEACON uricertainty analysis and the adequacy of the BEACON core monitoring. Severalimpodant techn:calissues were raisod during j the initial review which required additional information and clarification i from Westinghouse. This information was requested in Reference 6 l [ Letter from R. C. Jones (NRC) to N. J. Liparulo (Westinghouse),

" Request for Additional Information for the Review of the Topical Report j WCAP-12472-P, BEACON," August 25,1992] and was provided in the j Westinghouse response included in Reference 7 [ Letter from N. J.

l Liparulo (Westinghouse) to R. C. Jones (NRC), " Responses to NRC i Request for Additionallnformation for WCAP-12472-P (Proprietary),"

November 4,1992]. This evaluation is based on the material presented i in the topical report and in Reference 7, and discussions with j Westinghouse and the NRC staff at two meetings at the Westinghouse Corporate Offices in Rockville, Maryland on June 9 and September 11,

! 19S2. The evaluation of the major issues raised during this review are l summarized in the following. - 3.1 BEACON Methodoloay; The BEACON power distribution calculation is updated using the thermocouple and excore detector measurements. The thermocouple measurements are interpolated /extrapnlated radially using the spline fit. The BEACON system provides both a full three-dimensional nodal power dictiibution calculation as well as a simplified more approximate one-dimensional calculation. The BEACON on-line limits evaluation will be performed in three dimensions and the one-dimensional calculation will only be used as a scoping toolin predictive analysis. Document Control Desk .i Attachmsnt 11 TSP 970006 l' RC-98-0168 Page 8 of 9 The accuracy of the BEACON analysis decreases as the calibratio'n , intervals increase and the power distribution diverges from the reference power shape, in order to minimize BEACON uncertainty, the reference , power distribution is updated every 15 minutes or whon significant

changes occur in the AFD or the core power.

Tha majority of the Technical Specification modifications are simply changes which allow the use of the Power Distribution Monitcring System for power distribution limit surveillances. The conditions under which BEACON is determined to be operable were defined during the uncertainty analysis discussed previously and will be incorporated into the facility Technical Gpecifications. Thus, this ensures that the VCSNS BEACON uncertaintiec are applicable to the set of instrumentation which BEACON is using. i According to the SER: The power distribution limits (Technical Specifications 3.2.1 through

. 3.2.4) remain for the mont part unchanged from the cun'ent Technical Specifications except that they allow a core power distribution

. measurement to be obtained through BEACON (when Thermal Power is i greater than 25% .RTP) without using the incore movable detectors. The criteria for the incore neutron detectors, with BEACON operable, 1 require at least 75% available at beginning-of-cycle, and a minimum of 50% !- at any time afterward, with a minimum of two per quadrant. Except for lowering the criterion to 50%, this is the same as in the current STSs. The 50% fevelis reasonable for BEACON operable because of the increased , surveillance available from, for example, the core exit thermocouples. For BEACON inoperable, the minimum requirement remains at 75% and 4 per quadrant, which is acceptable. (This requirement tends to keep the

minimum for BEACON operaole higher than 50%.)

The criteria for the core exit thermocouples, with BEACON operable, require at least 25% of the thermocouples, with at least 2 per quadrant, with the added requirement that the operable pattarn normaliy covers all intemal fuel assemblies within a chess " knight" move (an adjacent plus a , diagonal square away), or there must be more frequent calibration. j Calibration, with the incores, is required every 180 effective full-power days. However, calibration is required every 30 days when the knight rnove requirement is not satisfied The accuracy of the power distribution information wiih decreased incore or thermocouple detector operability has been analyzed by W9stinghouse, and penalties are applied to the calculated peaking factors (refer to TER section 2.3). The review has concluded that the minimum ava;1able incore and thermocouple detectors, when coupled with the increased uncertainty penalties, provide censonc.ble and acceptable power distribution , information. 4 i _ _ _ . . _ _ _ . . __ .~.. __ . . _ _ . . . _ _ _ ~ . . _ _ _ . _ _ _ _ . . . _ . _ -

Document Control Desk l Attachment ll TSP 970006 l RC-98-0168

Page 9 of 9 4

l The BEACON system provides the capability for accurate and continuous core j monitoring. At VCSNS, BEACON will be used instead of the flux mapping system for power distribution surveillances when Thermel Power is greater than 25% RTP. It uses

current plant instrumentation in conjunction with a fully analytical rnethodology to generate on-line three-dimensicnal power distributions. The BEACON methodology I j and the impact of BEACON on Technical Specifications have been accepted by the 1 NRC as documented in WCAP-12472-P-A. The Technical Specifications changes j proposed in this submittal are more rectrictive than these approved in WCAP-12472-P-A and will not adverse!y impact the safe operation of VCSNS.

3 I 4 I i i i i 5 l l i i w - . __ , _ - _ . 'O i Document Control Desk Attachment til l TSP 970006 ! RC-98-0168 Page 1015 L NO SIGNIFICANT HAZARDS EVALUATION FOR REVISlNG THE SPECIFICAT!ONS TO INCORPORATE BEACON IN THE VIRGIL C. SUMMER NUCLEAR STATION TECHNICAL SPECIFICATIONS Description of Amendment Reauest The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) are being revised to incorporate a Power Distribution Monitoring System (PDMS). This system utilizes a NRC approved Westinghouse Proprietary Computer System, the Best Estimate Analyzer for Core Operations - Nuclear (BEACON), to augment the functionality of the flux mapping system for purposes of power distribution sutveillances. The proposed Technical Specification Changes alk)w the use of the PDMS to perform core power distribution surveillances. However, the PDMS is only used when Thermal Power is greater than 25% RTP. At Thermal Powers less than or equal to 25% RTP or when the PDMS is inoperable, the movable incore detector system will be used. The existing Technical Specifications require the surveillances to be performed usmg the movable incore detector system. l The affected Technical Specifications are: (a) 3/4.1.3 Movable Control Assemblies - Group Height (b) 3/4.2.2 Heat Flux Hot Channel Fador (c) 3/4.2.3 RCS Row Rata and Nuclear Enthalpy Rise Hot Channel Factor l (d) 3/4.2.4 Quadrant Power Tilt Ratio (e) 3/4.3.3.11 Power Distribution Monitoring System (f) 6.9.1.11 Core Operating Limits Report i in addition, one section is added to the Core Operating Limits Report (COLR). This section defines the equations and constants used to determine the applicable measurement uncertainties applied to the core peaking factors when determined by l either the PDMS or the flux mapping system. The constants found in this section of the

COLR are used as coefficients in the uncertainty calculations and are determined using NRC-approved methodology. The constants may be revised periodically as appropriate I

to reflect cycle-specific variables. l The NRC approved WCAP-12472-P A (Topical Report for BEACON) on February 16, l 1994. The NRC concludes that BEACON provides a greatly improved continuous on-i line power distnbution measurement and display, limit surveillance, and operation prediction information system for Westinghouse reactors. l I s, G Document Control D:sk Attachment 111 TSP 970006 RC-93-0168 Page 2 of 5 Virgil C. Summer Nuclear Station is proposing to implemerit BEACON to augment the functionality of the flux mapping system for purposes of power distribution surveillances. The Technical Specification changes discussed in WCAP 12472-P-A are applicable to an application of BEACON in which the core power distribution limits are changed and BEACON is monitored continuously by plant operators. For the application of BEACON to Virgil C. Summer, the premise is that BEACON will be used for power distribution measurement instead of the flux mapping system when Thermal Power is greater than 25% RTP. All power distribution limits remain unchanged. Thus, the VCSNS use of the BEACON system is a more restrictive app!icMion than is approved in the WCAP. In this application, if the PDMS meets specified operability requirements (i.e., operability of incore detectors, core exit thermocouples, and excore detectors), it is used to determine the measured core peaking factors. The power distribution surveillance continues to be pedormed with the same periodicity (once every 31 EFPD under norrnal circumstances, although more frequent surveillances may be required , under certain circumstances). Basis for No Sinnificance Hazards Consideration Determination South Carolina Electric & Gas Company (SCE&G) has evaluated the proposed changes to the VCSNS TS described above against the Significant Hazards Cateria of 10 CFR 50.92 and has determined that the changes do not involve any significant hazard. The following is provided in support of this conclusion.

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed change allows the Power Distribution Monitoring System (PDMS) to be used for measuring posuer distribution limits when Thermal Power is greater than 25% RTP. This includes relocating manufacturing and measurement uncertainty values from the Technical Spocification to the COLR. Also included in this change is the addition of a new specification and bases section for the Power Distribution Monitoring System (PDMS). The Technical Specification Power Distribution Limits are not being changed; only the method in which they are measured is being changed. The probability of an accident is nct significantly increased. The measurement of power distribution limits and the location of manufacturing and measurement uncertainty values are not initiators of any analyzed event. The change will not affect the consequences of any analyzed event. The power distribution limits will still be measured and , verified to be within limits as required by the current Technical Specification 3 Surveillance. The cycle-specific core operating limits, although not in Technical . _ _ _ ~ .. _ _ _ _ . _ _ _ . _ _ _ . . _ _ . _ _ _ __ _ . w Docum: int Contro! Desk l Attachment lll TSP 970006 RC-98-0168 Page 3 of 5 Specifications, will be followed in the operation of VCSNS. The actions as required by current Technical Specifications, when or if limits are exceeded are not being changed. This change will not significantly affect the assumptions ! relative to the mitigation of accidents. l Each accident analysis addressed in the VCSNS Final Safety Analysis Report ! will be examined with respect to changes in cycle-dependent parameters, which , are obtained from application of the NRC-approved reload design methodologies, to ensure that the transient evaluation of new reloads are , bounded by previously accepted analyses. This examination, which will be performed per requirements of 10 CFR 50.59, ensures that future reloads will

not involve an increase in the probability or consequences of an accident previously evaluated. 1 l

Therefore, the change does not involve a significant inucse in the probability l or consequences of an accident previcusly evaluated.

2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?

The proposed change allows the Power Distribution Monitoring System (PDMS) 1 to be used for measuring power distribution limits when Therma! Power is greater than 25% RTP. This includes relocating manufacturing and measurement uncertainty values from the Technical Specification to the COLR. Also included is the addition of a new specification and bases section for the Power Distribution Monitoring System. No safety-related equipment, safety function, or plant operation will be altered as a result of this proposed change. No hardware is being added to the plant as part of the change. The cycle specific variables are calculated using the NRC-approved methods and l submitted to the NRC to allow the Staff to continue to trend the values of these j limits. The Technical Specifications will continue to require operation within the i required core operating limits and appropriate actions will be taken when or if limits are exceeded. The change wi!l not introduce any new accicent initiators. l

Therefore, the change does not create the possibility of a new or different kind i of accident from any accident previously evaluated.

)

3. Does this change involve a significant reduction in margin of safety? l The proposed change allows the Power Distribution Monitoring System (PDMS) to be used for measuring power distribution limits when Thermal Power is greater than 25% RTP. The margin of safety presently provided by current l Technical Specifications remains unchanged. Only the method in which the i power distribution measurements are obtained is being changed. This method I is verified by Westinghouse, and reviewed and approved by the NRC.

I 7, 4 Docum::nt Control Desk Attachment lil TSP 970006 ! RC-98-0168 Page 4 of 5 i 1 Appropriate measures exist to control the values of the manufacturing and measurement uncertainties. The proposed amendment continues to require operation within the core limits, as obtained from NRC-approved reload design methodologies. Appropriate actions required to be taken when or if limits are violated remain unchanged. Future changes to measurement and manufacturing uncertainties located in the r current Technical Specification will be evaluated per the requirements of 10 j CFR 50.59. Since the 10 CFR 50.59 process does not allow any reduction in i the margin of safety, prior NRC approvalis required prior to a reduction in the margin of safety. If the evaluation of the changes do not result in a unreviewed safety question, piior NRC approval will not be required. Additionally, the VCSNS Technical Specifications require that all revisions of the plant COLR be submitted to the NRC upon issuance. ! Therefore, the change doos not involve a significant reduction in a margin of i safety

Pursuant to 10 CFR 50.91, the preceding analyses provides a determination that the

proposed Technical Specifications change poses no significant hazard as delineated by

! 10 CFR 50.92. i j Environmental Assessment

This proposed Technical Specification change has been evaluated against criteria for i and identification of licensing and regulatory actions requiring environmental L assessment in acccrdance with 10 CFR 51.21. It has been determined that the

! proposed change meets the criteria for categorical exclusion as provided for under 10 i CFR 51.22(c)(9). The following is a discussion of how the proposed Technical l Specification change meets the criteria for categorical exclusion. s 10 CFR 51.22(c)(9): Although the proposed change involves change to requirements i with respect to inspection or Surveillance Requirements, (i) the proposed change involves No Significance Hazards Consideration (refer to the No Significance Hazards Consideration Determination section of this Technical Specification Change Request); (ii) there are no significant changes in the types or significant increase in the amounts of any effluents that may be released offsite since the proposed change does not affect the generation of any radioactive effluents nor does it affect any of the permitted release paths; and

4. %

Docum:nt Control Desk Attachment lll TSP 970006 RC-98-0168 Page 5 of 5 (iii) there is no significant increase in indvidual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) Based on the aforementioned and pursuant to 10 CFR 51.22 (b), no environmental assessment or environmental impact statement need be prepared in connection with issuance of an amendment to the Technical Specifications incorporating the proposed change request. i r

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