ML20210S463

Rev 2 to TMI-1 Cycle 11 Colr

ML20210S463
Person / Time
Site:	Three Mile Island
Issue date:	08/07/1997
From:	Nelson M GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20210S460	List: ML20210S455 ML20210S463
References
TR-101, TR-101-R02, TR-101-R2, NUDOCS 9709100229
Download: ML20210S463 (37)

Text

- - - - _ - - - - - - - - - - - - - - - - - - - - -

TMI-1 Cycle 11 Core Operating Limits Report TOPICAL REIORT 101 Rev.2 HA Number 135400 TMI.1 Cycle 11 Reload Task Force July.1997 API'ROVALS:

2 7 77 O'rigina' tor F 8 Date

% rs %. W f

9 10 0 IIReload Task FoQChairman

' Date b

7-D-f7 ilanager, Nuclear Fuels Date f-/-f,7

~

Director. Engineering Support Date fhY$nA--

6/7l97

~ L A.m W~l/97 Plant Review Groug/

Date t

P PDR

ENuclear who TR 101 n.

TNI.) tycle 11 Core Operating 1.imits P.eport REV

SUMMARY

OF CHANot APPROVAL DATE I

1

.LCO imbalance limits for the 'After 500 EPPD" burnup window were revised to

i s.

I T include the impact of the redesigned cycle 11.

References and figure source documents

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(

were revised to' reflect the reevaluation of the redesigned Cycle 11.

p-l i /.I U" RPS axial power imbalance limits and setpoints, Figures 8 and 9 were revised a

to show the more conservative generic values currently used by plant hardware.

The minimum boron requirements for cold shutdown were moved to Itnclosure 1 and reworded consistent with their removal from the T.S.

Ihe "Atier 500 El'PD" burnep window for LCO imbalance s

b

, Innos was revised to be applicable for "500 to 655 EFPD".

A new burnup window was added Ihr 1.C0 imbalance limits to p 1l 10 0 be appheable for " Aller 655 El:PD".

gg 7.n47 lhe I.OCA 1,imited Masimum Allowable Linear lleat Rates for i

ihe l oper(aimo up to 690 EFPD. ore Monitoring System were revised to coser C c 3

APAR Rod Position 1.imit was added.

References and source documents were revised to renect the Cycle iI euension analyses. References also were revised to include Rev. I of!! AW.10179P A and remove references included in Rev.1. This change, as well as revisions to peaking tactors in 1:nelosure 2 correct the discrepancies identined in Performance issue #4 of GPUN Audit Report 0 TMI.96 02.

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TR101 Re.2 Page 1 of 35

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AHSTRACT This 'Nte Operating Limits Report (COLR) has been prepared in accordance with the requi.,ments of TMI I Technical Specification 6.9.5. The core operating limits were generated using the methodologies described in References I and 2 and were documented in References 3 through 6. The information in this COLR was reviewed for use at TMI l i

in References 7 through 10.

The Full incore System (FIS) operability requirements contained within describe the number and location of Self Powered Neutron Detector (SPND) strings that must he operable in order to monitor imbalance and quadrant tilt using the FIS.

Axial Power Shaping Rod (APSR) position limits and restrictions describe how the APSRs must he operated at the end-of-cycle, Quadrant till limits for FIS, out of core detector [OCD) system and minimum incore t

sptem l MIS) are gisen in Table 1.

Table 2 is discussed below with Figure 7.

4 Rod position limits are provided in Figures I to 3 to ensure that the safety criteria for DNilR protection. LOCA k </ft limits, shutdown margin and ejected rod worth are met. '

Imbalance limits for FIS, OCD and MIS are given in Figures 4 to 6.

COLR Figures I through 6 may have three distinctly defined regions:

1.

Permissible Region 2.

Restricted Region _

3.

Not Allowed Region (Operation in this region is not allowed)

Inadvertent operation within the Restricted Region for a period not exceeding four (4) hours is not considered a violation of a limiting condition for operation. The limiting criteria within the flestricted Region are potential ejected rod worth and ECCS power peaking. Since the probability of these accidents is very low, especially in a four (4) hour time frame, inadvertent operation within the Restricted Region for a period not exceeding four (4) hours is allowed.

COLR Figure 7 indicates the LOCA limited maximum allowable linear heat rates as a function of fuel rod burnup and fuel elevation for Mark B8 and Mark B9 fuel. Bounding values for monitoring these limits for the current cycle in terms of fuel batch, cycle burnup and axial detector levels are listed in Table 2.

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TRlol Res. 3 Page 2 of 35 COLR Figure 8 provides the Axlal Power imbalance Protective Limhs (APIPL) that prmerve the DNBR and Centerline Fuel Meh design critwin.

COLR Figure 9 provides the Protection Systeen Maximum Allowable Setpoints for Atlal Power Imbalance which cosabine the power / flow and error squeted atlal imbalance trip setpoints that ensure the APIPL of Figure 8 are not exceeded.

Note: Figures 8 and 9 show the conservative genwie ihnits and setpolots currently lastalled on the plant bardware. De souree documents noted on thee figures contain the cycle specific valum which have been verifled to be conservatively bounded by the generic values.- contalas operating ihnks not required by 'Ili. De core =laimum DNBR and the Maximum Allowable 14 cal Linear Heat Rate Limits are monkored by the Process Computer Nuclear Applications Software as part of b bases o' f the required limits and setpoints. De nalaimum boren volumes and concentrations for the Bode Acid Mh Tank (BAMT) and Recialmed ' doric Acid Storage Tanks (RBAST) are the boron levels unded to adleve cold shutdown condklens througbout the cycle using these ta nks.

, contalas the base descriptions of b Power-to Flow Trip Setpoint to prevent violation of DNBR crkeria and the Design Nuclear P2wer Peaking Factors for antal flux shape (7" ) anu bot channel nuclear enthalpy rise (F"4 that define the reference design peaking condhion in the core.

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TR 101 Res.2 PeteJaf35 TA BLE 0F CONTENTS PAGE Abstract 1

References 4

Full incore Sy stem lFIS) Operability Requirements APSR Rod insertion Limits se Table i Quadrant Till Limits 6

Table 2 Core Monitoring System Bounding Values for 7

LOCA Limited Masimum Alloweble Lineer Heat Rate Figure 1 Error Adjusted Rod insertion Limits 9

4 Pump Operatiom Figure 2 Error Adjusted Rod insertion Limiis 11 J Pump Operat6on figure J Error Adjusted Rod lasertion Limits 13 2 Pump Operation figure J FullIncore System Error Adjusted 15 Imbolence Limits 1

Figure 5 Out of Core Detector System Error Adjusted 19 Imbalance Limits Figure 6 Minimum intore System Error Adjusted imbalance Limits 23 Figure 7 LOCA Limited Masimum Allowable Lineer Heat Rate 27 2

Figure 8 Aslal Power imbalance Protectise Limits 29 Figure 9 Protection System Menimum Allowable Selpoints for Asial 30 Power Imbalance

. Operating Limits Not Required by Technical 31 Specifications DNBR related Bases Descriptions 33

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TM101 Res. 3 Page 4 of M

References:

l.

IIAW 10179P A. Rev.1, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," February 1996.

2.

BWFC Doc. No 861172640 00, " Detector Lifetime Extension Final Report for TMI l." September 1988.

3.

HAW 2250, Rev.1. "TM1 1 Cycle 11 Reload Report," September 1995.

4.

IIAW 2250, Addendum I, "TMI I Cycle 11 Redesign Verification Report Addendum to Cycle 11 Reload Report," October 1995.

5.

IlWFC Doc. No $1 1240408 00, "TMI I Cycle 11 Rev floron Shutdown," October

17. 1995.

6.

FCF Doc. No. 51 1267215-00, "TMI l Cycle 11 Extension Report," July 1997.

7.

GPUN Safety Evaluation 135400 013, Rev. 0.

• Tech Spec LOCA Limit Changes,"

June 28. 'W1.

H.

GPU Safety Evaluation 135425-006, Rev. O, " Tech Spec 6.9.5.2 Reference to il AW 10179P (TSCR 225)." May 3,1993.

9.

GPUN Safety Evaluation 135400-019. Rev.1. " Removal of Axial Power Imbalance Protective Limits and Setpoints from TS to COLR," May 8,1995.

10.

GPUN Safety Evaluation 135400-022. Rev. 3, "TMI l Cycle 11 Reload Design,"

July 1997.

1H 101 Ret. 2 Page $ of J$

Fuu Incore System (FIS)

Operabluty Requirements 9

'Ihe Full Incore System (FIS) is operable for monitoring axlat power knbalance provided the number of valid Self Powered Neutron Detector (SP:(D) signals in any one quadrant is not less than 75% of the total number of SPNDs in the quadrant.

4 Quadrant SPNDs 75 %

WX 85.75 64.5 XY 99.75 75.0 YZ 89.25 67.0 ZW 89.25 67.0

• !he Fuu incore System (FIS) is operable for monitoring quadrant tut provided the number of valid symmetric string ladividual SPND signals in any one quadrant is not less than 75% (21) of the total number of SPNDs in the quadrant -

(28).

Quadrant Symmetric Strings WX 7,9,32,35 XY 5,23,25,28 YZ 16, 19, 47, 50 ZW 11, 13, 39, 43 Sourte Doc.: B&W 861172640-00 Referred to by:

Tech. Spec. 3.5.2.4.a and 3.5.2.7.a e

__.m T R 101 Rn.2 Page,te of j$

s 1

i 4

e 3

k APSR Position Limits liefore the end-of-cycle APSR pull maneuver is completed, the Al%Rs may be positioned as necessary for transient imbalance control. The A15R pull maneuver shall be completed (i.e. APSRs fully withdrawn) at 655110 EFPD.

Once the APSR pull maneuver has been completed, the APSRs shall not he inserted for the remainder of the fuel cycle and 0-99% WD shall be considered a " Restricted Region" as defined in the abstract section of this COLR.

l J

Source Doc.:

FCF Doc. No. 51 1267215-00 4

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l Table 1 Quadrant Tdt twmts Steady State Limit Steady State twat Maumum Limit 15% < Pcw < 50%

Indcated Power > 50%

Indicated Power > 15%

Fullincore System 6.79%

3.81 %

16.8%

(FIS)

Out-of-Core Detector 4.05%

1.96%

142 %

System (OCD) 84nimum incore System 2.80 %

1.90%

9.5%

(MIS)

Note:

MIS limits assume no MIS detedors exceed 60% sensitivity depletion.

Source Docc B&W 86-1235208-01 Referred to ty Tech Spec. 3.52.4 e

e yM

TR lol Res. 2 Page 7 of JS TAHLE 2 tPage i of 2)

Core Monlloring Splem llounding Values for IDCA Limited Matimum Allowalite Linear lical Hale (LW/ftl Hatches 100. IID and 110 CMS

0. H5 -

MS - 690 Level EFPD EFPD

\\

'8 8.9 8.7 7

10.6 10.4 6

l 1.2 10.9 5

11.2 10.9 4

11.2 10.9 3

11.2 10.9 2

10.6 10.3 1

8.9 8.7 l'

listehes 128.12C.12D and 12 E

( \\ls II. 7 7 278 278 387 387 - 433 433 665 665 - 690 1.s s ti liPD L F,"D EFPD EFPD EFPD EFPD l

N I3.2 13,2 12.9 l 2.4 9,9 9.7 3

l 1

l 5.7 15.7 15.4 14.7 11.8 I l.6 6

16.4 16.4 16.1 15.5 12.4 12.2 5

I 6.3 16.3 16.0 15.5 12.4 12.2 4

16.3 16.3 16.0 15.5 12.4 12.2 3

15.7 16.I I5.8 15.5 12.4 12.2 2

14.6 15.1 14.8 14.6 l 1.7 11.5 i

I 2.4 12.8 12.5 12.4 9.9 9.7 Hatch 13 A CMS 0 58 58 321 321 - 690 Imel EFPD EFPD EFPD 8

12.8 12.8 12.8 7

15.2 15.2 15.2 6

16.2 16.2 16.2 5

16.1 16.l =

16.1 4

16.1 16.1 16.1 3

15.1 15.2 15.7 2

l4.0 14.0 14.7 I

I I.8

~~ II.8 12A

TR 101 Res.2 Page li cf J.4 TABLE 2 (Page 2 of 2)

I t

Core Monitoring System Bounding Values for IDCA t imited Manimum Allomjble Linear Heat Rate 1

(kW/ft)

Hatches 13B,13C.13D and 13E 4

CMS 0 241 241 - 375 375 - 690 level EFPD EFPD EFPD 8

13.6 13.7 13.2 7

16.2 15.7 15.7 6

17.0 16.4 16.4 5

17.0 16.3 16.3 4

17.0 16.3 16.3 3

16.0 15.7 16.1 2

l 14.6 14.6 15.1 1

12.4 12.4 12.8 i

Hatches 13F and 13G CMS 0 244 244 - 690 14sel EFPD EFPD 8

13.6 13.2 7

16.2 15.7 6

67.0 16.4 5

17.0 16.3 4

17.0 16.3 3

16.0 15,7 2

14.6 14.6 1

12.4 12.4 The masimum linear heat rate for each CMS les el, as measured with the NAS Thermal H)draulic Package (Display 4h should be less than the corresponding bounding tatue from Table 2 above.

Source Does.:

FCF Doc. No. 51 1267215 00 FCF Doc. No. 51 1267237-00

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Figure 1 (Page 1 of 2)

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TR lli Res. 3 i

Page l$ of M j

i 1

' Figure 4 (Page 1 of 4)

FullIncore System Error Adjusted Imbalance Limits 0 To 75 +/-10 EFPD ii.

38.4.102 l 15.103 lll

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TR 101 R:s. 3 Page 16ef 35 Figure 4 (Page 2 of 4) 1 Fullincore System l

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Source Doc a&W 861235284 01 Referred tu by Tech Spec 3.5.2.7.a and 3,5.2.4.e.3

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TR 101 Ret 2 Figure 4 (Page 3 cf 4)

Po n em Full Incore System Error Adjusted imbalance Limits 50.0 +/-10 EFPD to 655 +/ 10 EFPD 110

- 110 1

l l

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m 50 45 -40 35 30 25 20 15 10 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power lmbalance, %FP Each Div. = 1% FP '

Source Doc. FCF 861235286 02 Referred to by Tech Spec 3.5.2.7 and 3.5.2.4.e.3

70101 un.:

Figure 4 (Page 4 Cf 4)

, Full Incore System Error Adjusted imbalance Limits After 655 +/ 10 EFPD 110

- 110 l

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g _

__ 33 2,80 !,

24.6,80

- 80 70

-~-

t

- 70 I

I

.0 i

i 37.5,50,

4 27.9.50 g

Lg l;

4 PERMISSIBLE 40 --

REGION F 40 l

1 N

30 -

h30 i

20 --

- 20 10 -

- 10 37.5,0 27.9,0 3

0r q > y,7 o. o.g1 3 yo.,o.

L O oo;,oqm, quo ou ou oo ou mm ou o,

5045403530252015105 0 5 10 15 20 25 30 35 40 45 50 Indicated Axlal Power imbalance, %FP Eoch Div. = 1% FP Source Doc. FCF 86123628642 Referred to by Tech Spec 3.5.2 7 and 3.5.2.4.e.3

.,n._

n,

TR101 Res. 3 Page 19 of 35 Figure 5 (Pege 1 of 4)

Out of Core Detector System Error Adjusted imbal,ance Limits 0 To 75 +/10 EFPD

" O 'i 4

4 i

e i

i

. 110 i

19.4,102 9.2,103 i

l t

RESTRCTED

! 100 100 RESTRCTED 1

j REGloN asa ww i

l i

do,

,24J,92 15 le 92 l= 90 l

i k

1. T

.27.5, to f

g 16.5, to 28' i

t N

}

b70 70

/

f E

)

5 I

i 4

W

[

2:

I t

H 50 32.3,80 23A,80

se

• ~

b E

e i

3 i

i i

PERMESSLE

]

[33 i

i REGON to.

- 30

/

10 ~

10 O

,,,j,,,,

0 igno n.q,.nj on,,,o

,,o n,,

,u,

,n, n,

5046403830383015105 0 5 10 15 N 38 30 38 40 48 50 Indicated Axial Power imbalance, %FP Source Doc. B&W 861235288 01 Referred to by Tech Spec 3.5.2.7 and 3.5.2.4.e.3 l

e

1 TR101 i

Rn.1 Page 20 of M Figure 5 (Page 2 of 4)

Out of-Core Detector System Error Adjusted imbalance Limits 75 4./10 To 500 +/10 EFPD 110 a

i i

, i

. 110 l

+19.1,102 12.7.102 l

100 MitTMCTED T

g nicaoN I

RESTRCTED

! 100 meg l

i i

[

24.0,93 r

17.8e M

M g,

27.2, M

[

19.0,30 l

5 u

70,.

.k

, 70 O

.0 a w

i 00 g

21.3,80 f to 50 32.0,80

• 3 i

40 :

5 I

-5 i

Y 5

~"

esRussets 1

i REGION i

?

!- 10 to.

~

0.

i 0

n.

m.,

n.,

n n,.

n,,

n,,

,,n, no

,,n,,,,,

n,,

50 45 40 48 40 25.N.15 10 5 0 8 10 il 20 28 30 as 40 48 50 Indicated Axial Power imbalance, %FP Source Doc. B&W 861235288 01 Referred to by Tech Spec 3.5.2.7 and 3.5.2.4.e.3

TH l01 Figure 5 (Page 3 cf 4)

,,,,,,",73 2

Out-ol Core Detector System Error Adjested imbalance Limits 500 +/ 10 EFP3 to 655 +/- 10 EFPD 110

.-110 l

l l

h t

i

\\

18.1.102 1,3.6,102 l

l l

100 -

- RESTRICTED

[--

\\

RESTRICTED

- 100 RE0lON

}

RE0!ON se 0, Y2 15.8, og go -

1 l

- go j

l 1g.0,30

. g i

)

l

-- j

., 60 00

?

l n

TO g' ^

i-70 a

f 60

' 60 f

5 32.0.50 22.e,50 g

g l

PEN llLSIBLE j

40 - -

REGION

- - g

'c 40 5

i 30 -

' 30 f

20 -

f-20 10 -

3-10 3

32.0,0 22.8,O

-0 0 J p,.

1g

qo 31.p ooio,q,,1 uopoq.,opo.p o m o, ou um om 50 -45 40 35 30 25 20 15 10 5 0 5 10 15 20 25 30 35 40 45, 50 Indicated Axlal Power !mbalance, %FP Each Dhr = 1% FP Source Doc. FCF 861235288 02 Referred 10 by Tech Spec 3.5.2.7 and 3.5.2.4.e.3 TR101 i Figure 5 (Page 4 Cf 4) e.y 2E3i's Out-of-Core Detector System Error Adjusted Imbalance Limits After 655 +/- 10 EFPD 110 110 l I l J 13.6,102 13.6,102 2 31 100 - - RESTRICTED RESTRICTED - - 100 \\- REGION REGION i i 21.3,92 / 15.8.92 3 6 90 -- j

g!o l

l J 19.0,80 60 g 3- - 80 e i il ~ i-70 -g 70 'I j j 60 f 60 i 1 }i _ 22.8,50 _ 32.0 g EL f PERMISSIBLE E 40 REGION --k j - 40 3 i l l l i i j 1

- 30 1

i g 20 20 t 3 i i )- 10 10 -- - ' 5. ~ 32.0,0 22.8,0 5 J. ;,,

,;;;.,..,.,,,,,,;,,nio.,,,,,;,,,..,jiuig.,,;;,,,..

~ 0 0 50 40 -35 30 25 20 15 10 5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axlal Power Imbalance, %FP Each Div. = 1% FP Source Doc. FCF 861235288 02 Referred to by Tech Spec 3.5.2.7 and 3.5.2.4.e.3 4 RS 1 1 2 4 5 M 7 s 0 o M 0 eo D D 0 D 0 0 f u e

3 -

.i::-

• [: ::

igfj; r r c 5 ij: i 5-r e e 0 d D 4 1 l >l i. I ,. i l RE R t o 5 o c i 2 ES i b. 0 g 9 y B i ,1 2 lG T 4 I R OI T & 4 5 IIi l ,7 1 I N C 4 2 T 5 0 E W e I 3 8 ,8 D c 9 i E h8 n0 0 s r 6 d a [i 2 S-2 i 1 r i 1 s 7 i o p c5 i P e2 a2 g R R l / ,2 r M c3 32 e E t 5 0 1 i An F [ i i M

1. 0 5 8 d1 i

E 2 O di 5 GI i i Tjmg I S 8 A-i O S i u u 2 -0 x1 g NI o i 6 B s u r 71 0 5 e m _e L 7t a a l 5 i E 6 n i 3 o0 i ~ dI d P i i + i n (P 5 w i /mc a 2 e5 C5g3 # o .] 1 ua5 y.s g .n i t. i s 1 o i i 1 i 0 br g i r } l El 1 ae e 4 Im0 i ,8 i 7 e i aS 1 i Fny o 3' a ,i 1 1 2 i Date )4 b g 1 l 5 i Pcs f 0 la2 n 4 3 0 c2 ,6 ,2 Lm ,e 2 8 i 5 i 0 0 9 l' m i %0 gi 7 . R 3 5 RE i u t i 0 ES FS IGT s S i R P i OI i 0 N C 4 T E 5 g D 4 i i 5 i J

-l

~ _

ij: ii ~ :i; $:_:::i:_ j; 0 t 2 4 5 M O' 7 g 1 0 o 0 o 0 0 0 0 Pa ge 2 T 3 RR oe f 1 3.s 0 521 i 4 RS 1 1 m = 5 7 8 9 0 1 1 eo 0 0 0 0 0 0 0 0 0 f u e r r e e 0 E ~::5. ji i5:

i 33:

c 5 ig ~:2 r .n d D 4 R t o 5 o 1 RE 2 ES ob.c n 4 9 0 p l G T R y B ,1 2 O C n T & 3 5 4 2 IN T 0 ,7 1 E 5 u eW n 8 ,8 D c E I 1 0 9 h8 n0 i 2 r 6 S-d n p c5 o P 1, 7r 2 o i 1 5r M e2 a2 E / 7, n c3 R R [ ,2 + t 0 E /Ai F 5 3 2 e-i GI n n M 1 di 8 d1 0 ; 1j i S 5 8 umg I 5 u OS 2 A-n N S 0 su u 2 -0 1 .71 x0 r u L n E e i 3 o0 Ttem a a l 5 g odi 6 n n d P 5I n (P n . M,.g3 # o C3i g m OI u $ 'A 0mc 0 5 w a n o 2 e5 br g o r n 1 + ae e 4 1 I 1 0 / l .e m i \\ ,3 aS 2 n 1 3 b5 g 1 0 ny o 1 o a 0 a3 ,n 2 cs f l Eet 2 e )4 1 u 5 n n F L ,9 Pim c2 0 9 1 2 5 7 ,e ,7 ,1 2 Dm n 3 R %0 5 3 IqE i n t u 0 0 S aT s F3 i mC 5 R P n, 4 T 0 o E n D 45 o n 5 0

f. ::EE 5!

i "E:--:

i:::i:

5,

0 1 a 3 s 7 8 9 1 3 0 0 o o 0 0 0 0 3 0 0 Pa g e 2 T 4 R R o e f3.s 1 0 521 TR101 Rn.2 Figure 6 (Page 3 6f 4) re ndu Minimum incore System Error Adjusted imbalance Limits 500 +/; 10 EFPD to 655 +/- 10 EFPD 110 - 110 l l l 13.6,10,2 ,9.4,,102 I 100 ~ RESTRICTED - I RESTRICTED - _L 100 REQlON REGIDN i 19.0,92 11.4,92 i 90 ; l 7 - 90 80 14.3,80 i-80 g i a 70 - - -t j }-70 I i 60 . - 60 I 4 l 26.3,50 50 7 17.9,50 l E i i 4 I PERMISSIBLE E i 4 ~ REGION --h

f. 40 40 3

i 3 i i 30

30 i

] 20

20 i

i 4 10 -- 10 l 26.3,0 l 17.0,0 0 =0 ,,.j. ,jm r p .g .,. qmm mmpm, ,m.,..mqmm m..,.m....p.m 50 -45 40 35 30 25 20 15 10 -5 0 5. 10 15 20 25 30 35 40 45 50 indicated Axial Power imbalance, %FP Each Div. = 1% FP Sou ce Doc. FCF 861235288-02 Referred to by Tech Spec 3.5.2.7 and 3.5.2.4.e.3 TR101 Rn,2 Figure 6 (Page 4 cf 4) rw x an Minimum incore S'ystem Error Adjusted imbalance Limits After 655 +/- 10 EFPD 110 _ I I II I j _ 110 i 9.4,102 9.4,l102 i 100 _ RESTRICTED l I REGION RESTRICTED - 100 ~ i REGION ~ i 90 i / 16.4,92 11.4.92 .- 90 21.9.60 __ / ,_ 14.3,80 ~ 80 at e u 70 d ~. - 70 8 -- 4 60 c 60 , 26.3,50 g 17.9,50 g i 2 REGION -- 1 ~ PERMISSIBLE E 40 - - I _ 40 I 5

30

~. 30 I _h 5 20 I z 20 10 - 10 i 2 I 5 26.3,0 17.9,0 5 0 ~, J..;'.m ,g p j g. q. ,.op .,i.uogo.q.m....q.u.go 0 .o .in 50 45 35 -30 25 20 15 10 -5 0 5 10 15 20 25 30 35 40 45 50 Indicated Axial Power imbalance, %FP, Each Div. = 1% FP Source Doc. FCF 86-123528842 4 ~ J Referred to by Tech Spec 3 5.2.7 and 3.5.2.4.e.3 4 d v e- i l 1 Figure 7 (Page 1 of 2) LOCA Limited Maximum Allowable Linear Heat Rate Mark-88 Fuel 19 (32000.18) 18 B-ft 17 \\'. 4-n l 6-ft 16 10-n g y u .15 E c l a 14 13 12 (60000.11.6) i i i gg 0 10000 20000 30000 40000 50000 60000 ~ Bumup, mwd /mtU 4 Source Doc. B&W 51-1234870 06 eto:. tbr cadi )000 munu fei excess..r S. w: ;.g Referred to byTech S@. 3.5'2~8 ' 40 " "'/"t"' l liscarly try 0.075 KW/rt. "'e linear heut raic M..w2 shall le reduca Figure 7 (Page 2 of 2) LOCA Limited Maximum Allowable Linear Heat Rate Mark-89 Fuel 19 (39000,18) 18 4-R s g7 - 6 8-I10-ft 4,8.10-ft twt 16 .l 2-R c h ~ .15 a: x-a 14 i 13 (57000,12.6) 12 ~ 11. O .10000 20000 30000 40000 50000 60000 Bumup, mwd /mtU Source Doc. B&W 51-1234870-06 Note: ibr each 1000' mv tu in exuss or 5 Referred to ty Tech Spec 3.5.2.8' 40,000 MVatu, the linmr. heat rate j shaI1 he reduced Imear1y by 0.075 m/ft. g A2_ UGS .m s m ._m. .___m_.__ . _ ~.. TR 101 Res. 2 Page 29 et 35 Figure 8 AXIAL POWER IMBALANCE PROTECTIVE LIMITS Thermal Power Level, % 120 -43 A,112.0 37A,112.0 1 ACCEPTABLE' 4 PUW OPERATION . 100 -43.8, 89.3 37A,80.3 58.5, 80.4 9 ACCEPTABLE 80 53 D,80.4 ' 3 ANO 4 PUW OPERATION 43 2,62.0 h 37A,622 583,57.8 ~~ 4 53.0,57.8 ACCEPTABLE. 2,3 AND 4 PUW OPERATION 4o 58 3,30.4 53 4,30.4 . 20 1 I I I I I I I I I I I I I I -80 70 -60 50 -40 -30 20 10 0 10 20 30 40 50 60 70 80 Axial Power Imbalance, % EXPECTED MNIMUM CURVE REACTOR COOLANT FLOW UbM 1 139.8 x 10E + 6 2 104.5 x 10E + 6 Source Doc. BWNT 861234922-01 3 68.8 x 10E + 6 TR 101 Res. 2 Page 30 of 35 Figure 9 PROTECTION SYSTEM MAXIMUM ALLOWABLE SETPOINTS FOR AXIAL POWER IMBALANCE Thermal Power Level, % _ _ 120 30A 108.0 24.5,108.0 ! ACCEPTABLE j4PUW - 100 l OPERATION l mi a 1.900 30.0,80.6 24.5,80A a i !' ACCEPTABLE ! 3 AND 4 POW 50.0,70.0 ! OPERA M 46A 70,0 l.: 1 i a t 3 -30A 53.1 24.5,53.1 j jACCEPTABLE i i2,3 AND 4 PUW 50.0,42.6 l OPERA N l 45.0,42.6 l -e i t i i i i 50.0,15.1 i M 45.0,15.1 i $ :i im 9 9 = 2

M 4

a

a

= 5 'i' I i i I I I 1 1 1 I I 80 70 60 50 40 30 -20 10 0 10 20 30 40 50 60, 70 80 Axial PowerI' balance, % m Source Doc. BWNT B6-1234922-01 l _------_u TR 101 Rn.2 Page 31 of 35 Operating Limits Not Required by Technical Specifications 1 9 4 9 i TR 101 Rn. 2 Page 32 of M 1. Core Minimum DNBR Oneratine IImle (

Reference:

BAW-2250)

The core minimum DNBR value as measured with the NAS Thermal

{

Hydraulle Package (Display 1 or 4) should not be less than 2.02 (102% ICDNBR).

)

2.

Mnvirnum Allowable Laent I Iname Han* Rat 1.imite.

i

(

Reference:

T.S. 2.1 Bases) i L

The maximum allowable local linear heat rate limit is the minimum i

LHR that will cause centerline fuel melt in the rod. This limit is the basis for the imbalance portions of the Axial Power Imbalance i

Protective Limits and Setpoints in Figures 8 and 9 of the COLR, i

respectively. The limit is fuel design-specific; the value for the most l

. limiting fuel design in the current core is used for monitoring as~given i

below:

o BWET Mark-B8/B8V a

LHR to melt = 20.5 kW/ft i

3.

. Minimum Boron N:chd for Cold h* dawn

(

Reference:

51-1240408-00)

The minimum boron levels needed in the B MT and RBASTs e

i to achLve cold shutdown conditions throughout the cycle is the equivalent of at least 1052 ft.3 of 8,700 ppm boron.

j b

TR101 Rev. 2 Page 33 of J5 DNBR-Related Bases Descriptions 4

e e

e 4

4 TR 101 Rev. 3 Page 34 of 35 4

1.

Enwer-to-Mow Trip setaalaen The nuclear overpower trip setpoint based on RCS How (power /now or nux/now tdp) for the current cycle is 1.08. This setpoint applies to four, three-and two-pump operation as described in T.S. Table 2.3-1 and Figure 9 of the COLR.

The power / Hew trip, in combination with the axial power imbalance trip, provides steady-state DNB protection for the Axial Power Imbalance Protedive Limit (Figure 8). A reactor trip is initiated when the core power, axial power pealdag and reactor coolant now conditions indicate an approach to the DNBR limit. The power /now trip also provides transient protection for loss of reactor coolant now events, such as loss of one RC pump from a four RC pump operating condition.

Power level and reactor now rate combinations for four, three-and i

t two-pump operating conditions are as follows:

1.

Trip would occur when four reactor coolant pumps are operating if power level is 108 percent and now rate is 100'

. percent, or power level is 100 percent and now rate'is 92.5 percent.

2.

Trip would occur when three reactor coolant pumps are operating if power level is 80.6 percent and now rate is 74.7 percent or power level is 75 percent and now rate is 69.4 percent.

3.

Trip would occur when one reactor coolant pump is operating in each loop total of two pumps operating) if power lev:1 is 53.1 percent and now rate is 49.2 percent or pow:c level is 4' 9 percent and now rate is 45.3 percent.

The power level trip and associated reactor power / axial power imbalance boundaries are reduced by the power-to-Gow ratio as a i

percent (1.08 percent) for each one percent now reduction.

1

.~.

TR101 Rn,2 Page 35 of J5 2.

Desien Nuclear Power Peaking Factors J

(

Reference:

T.S. 2.1 Bases)

The design nuclear power peaking factors given below define the reference design peaking condition in the core for operation at the maximum overpower. These peaking factors serve as the basis for the pressure / temperature core protection safety limits and the power-to-flow limit that prevent cladding failure due to DNS overheating.

e Nuclear Enthalpy Rise llot Channel Fglor (Radial-Local Peakina Factor). FN6H FNn 1.714

=

e Axial Flux Shane Peakina Factor. FNz FNz= 1.65 (cosine) e

~ Total Nuclear Power Peaking Factor. FN, FN

= FNAH x FN z

FN

= 2.828