Text

Proposed Tech Specs Re Shutdown Margins,Reactor Trip Sys & Heat Flux Hot Channel Factor
	ML20071L107
Person / Time
Site:	Millstone
Issue date:	07/22/1994
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20071L105	List: B14803, Application for Amend to License NPF-49,proposing Changes to Ts,Addressing Shutdown Margins,Reactor Trip Sys & Heat Flux Hot Channel Factor; ML20071L107;
References
	NUDOCS 9408020191
	Download: ML20071L107 (48)
	v • d • e

r

- '- - March 11, 1991 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS .

SECTION PAGE

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3/4.0 APPLICABILITY .............................................. 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - MODES 1 AND 2 ......................... 3/4 1-1 Shutdown Margin - MODES 3, 4, AND 5 LOOPS FILLED ........ 3/4 1-3 FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH FOUR LOOPS IN OPERATION ............... 3/4 1-4 FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH THREE LOOPS IN OPERATION .............. 3/4 1-5 FIGURE 3.1-3 REQUIRED SHUTDOWN MARGIN FOR MODE 4 ........ 3/4 1-6 FIGURE 3.1-4 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS FILLED ........................... 3/4 1-7 Shutdown Margin - Cold Shutdown -

Loops Not filled ............. ............. 3/4 1-8 FIGURE 3.1-5 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS 4RMNED T . 7.Y.T?............... 3/4 1-9 Moderator Temperature Coefficient ....................... 3/4 1-10 Minimum Temperature for Criticality...................... 3/4 1-12 3/4.1.2 BORATION SYSTEMS -

Flow Path - Shutdown .................................... 3/4 1-13 Fl ow Path s - Ope rati ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-14 :

Charging Pump - Shutdown ................................ 3/4 1-15 Charging Pumps - Operating .............................. 3/4 1-16 Borated Water Source - Shutdown ......................... 3/4 1-17 ,

Borated Water Sources - Operating . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height ............................................ 3/4 1-20 ,

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R0D .................. 3/4 1-22 Position Indication Systems - Operating ................. 3/4 1-23 l

l MILLSTONE - UNIT 3 iv Amendment No. Jp 60 0039 940B020191 940722 I PDR ADOCK 05'00423 i P PDR

March 11, 1991 l

REACTIVITY CONTROL SYSTEMS l

SHUTDOWN MARGIN - COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to l l

a) the limits shown in Figure 3.1-5 or the_llmits_sho_wn_in Figure 3.1-4%hure the valves shown ini

[

b)

(Specification 4.4.112 g g7- ]

APPLICABILIII: MODE 5 LOOPS NOT FILLED []* [$ '

ACTION: UC"'" " ** __-

Ed. With the SHUTDOWN MARGIN less than the above, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REOUIREMENTS w '

W1 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above: .

a. Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is imovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1) Reactor Coolant System boron concentration,

2) Control rod position,

3) Reactor Coolant System average temperature, c 4) Fuel burnup based on gross thermal energy generation, 1

(Inser4]

t i . t .2.1, 5) Xenon concentration, and k 6) Samarium concentration.

I .1.1.2.2 4 Valve 3CHS-V305 shall be verified closed and locked at least once) b ger31 days.j i

MILLSTONE - UNIT 3 3/4 1-8 Ameh$ne,nt No. 60 0007 s 3)

. - - - _ - . ..= . - . . - . _ - _ _

.... .. q i

Inserts to Page 3/4 1-8 I

Insert 3.1.1.2

b. With the CVCS dilution flow paths not closed and secured i: in position in accordance with Specification 3.1.1.2 (b) ,

immediately close and secure the paths or meet the limits shown in Figure 3.1-5 l

Insert 4.1.1.2.2 -

4.1.1.2.2 At least once per 31 days the following valves shall be l verified closed and locked. The valves may be opened on an i intermittent basis under administrative controls except as noted.

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ch 11, 19,9 SURVEILLANCE REQUIREMENTS (Con't)

Valve Number Valve Function Yalve Position

1. V304(Z-) Primary Grade Water Closed to CVCS

2. V120(Z-) Moderating Hx Outlet

3. Closed V147(Z-) BTRS Dutlet Closed

4. V797(Z-) Failed Fuel Monitoring Closed Flushing

5. V100(Z-) Resin Sluice, CVCS Cation Closed Bed Demineralizer

6. V571(2-) Resin Sluice, CVCS Cation Closed Bed Demineralizer

7. Vill (Z-) Resin Sluice, CYCS Cation Closed Bed Demineralizer

8. V112(Z-) Resin Sluice, CYCS Cation Closed Bed Demineralizer

9. V98(Z-)/V99(Z-) Resin Sluice, CVCS Mixed !

Closed l Bed Demineralizer e l

10. V569(Z-)/V570(Z-) Resin Sluice, CVCS Mixed Closed e Bed Demineralizer

11. V107(Z-)/V109(Z-)- Resin Slutce, CVCS Mixed Closed Bed Demineralizer

( 12. V108(Z-)/V110(Z-). Resin Slutce, CVCS Mixed Closed Bed Demineralizer

13. Po

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March 11, 1991 POWER DISTRIBUTION LIMITS 3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fg FOUR LOOPS OPERATING LIMITING CONDITION FOR OPERATION 3.2'2.1 F (Z) shall be limited by the following relationships:

n Fn (Z) s FhTP K(Z) for P > 0.5 P

RTP Fn (Z) s F g K(Z) for P s 0.5 0.5 RTP F the F limit at RATED THERMAL POWER (RTP) provided in thecoreoper$tinglimitsreport(COLR).

THERMAL POWER , and Where: P RATED THERMAL POWER Insert

( '3 . 2.2.1 K(Z) - the normalized Fn (Z) as a function of core height .

specified in the COLR.

APPLICABILITY: MODE 1.

i ACTIONi p_ . _ _

With F (Z) exceeding its limit:

i n

a. Reduce THERMAL POWER at least 1% for each 1% Fn(Z) exceeds the limit within 15 minutes and similarly reduce lhe 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 AT Trip Set-points have been reduced at least 1% for each 1% F g(Z) exceeds the limit, and *

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit re-quired by ACTION a., above; THERMAL POWER may then be increased provided Fn(Z) is demonstrated. through incore mapping to be within its ' limit.

l MILLSTONE - UNIT 3 3/4 2-5 l mendment A No. # ,60 0011 .

Insert to Page 3/4 2-5 (Page 1 of 2)

Insert 3.2.2.1 With F o (Z) exceeding its limit:

a. For RAOC operation with Fo( Z) outside the applicable limit specified in the COLR, perform one of the following actions:

(1) 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 Fo (Z) exceeds its limits. 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.

(2) Reduce THERMAL POWER 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 usy proceed provided the Overpower AT Trip setpoints have been reduced at least 1% for each 1% Fo (Z) exceeds the limit.

(3) Verify that the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load operation.

Where it is necessary to calculate the percent that Fo(Z) exceeds the limits for Items (1) and (2) above, it shall be calculated as th3 maximum percent over the core height (z) that Fo( z ) exceeds its limit by the following expression:

F "( z) x W(zi MP x K(z) -1 x 100 for P 2 0.5 F"(z) x W f z )'

E." x K ( z ) -1 x 100 for P < 0.5 0.5 -

6

?

r Insert to Page 3/4 2-5 (Page 2 of 2)

b. For base load operation outside the applicable limit specified in the COLR, perform either of the following actions: !

(1) Place the core in an equilibrium condition where the limit in 4.2.2.1.2.C is satisfied, and remeasure F "(Z), or (2) Reduce THERMAL POWER at least 1% for each 1% F,(Z) i exceeds the limit within 15 minutes and similarly r 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 l 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 AT Trip setpoints have been reduced at least 1% for each 1% F,(Z) exceeds the limit. The percent that F. exceeds its limit shall be calculated as the maximum percent over the core height (z) by the following expression:

~

F_"I 2 ) x W(z1.. l Io*" x K(z) -1 x 100 for P 1 APL" P

c. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWZR above the reduced limit required by ACTION a. or b., above; THERMAL POWER may then be increased provided aF (Z) is demonstrated through incore mapping to be within wN limit.

I I

5 1

6

** March 11, 1991 i

POWER SISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

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

l'

e. With the maximum value of F (z)

K(z) l ove the core height (z) increasing since the previous detemination !

of F (z), either of the following actions shall be taken: ,

(1) F N(z) shall be increased by 2% over that specified in Specifi- -

cItion 4.2.2.1.2c, or (2) F$(z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that the maximum value of :

F"(z)

K(z)

[

over the core height (z) is not increasing.

r. - ~ - - - - -

m

f. With the relationships specified in Specification 4.2.2.1.2c not '

being satisfied: .

(1) Calculate the maximum percent over the core height (z) that Fg (z) exceeds its limit by the following expression:

I F (z) x W(z) i -1 x 100 for P 2 0.5 p RTP 0 xK(z)

P MILLSTONE . UNIT 3 ,, - 3/4 2-7 .

< Amendment _No. Jp ,60 0012

I ,

.** ** March 11, 1991 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

F (z) x W(z)

-1 x 100 for P < 0.5 ;

p RTP O x K(z)

. 0.5 I . . >

(2) One of the following actions shall be taken: j (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 Fn(z) exceeds its limits as determined in Speci fication '4.2.2.1.2f. l . 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 ;

f (b) Comply with the requirements of Specification 3.2.2.1 for Fq (z) exceeding its limit by the percent calculated, or (c) Verify that the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load /

operation. -

y The limits specified in Specifications 4.2.2.1.2 4.2.2.1.2 i 4.2.2.1.2Dabove are not applicable in the foi owing core plane regions: -

l (1) Lower core region from 0% to 15%, inclusive. I (2) Upper core region from 85% to 100%, inclusive.

1 ND 4.2.2.1.3 Base load operation is permitted at powers above APL if the l following 'onditions are satisfied: )

l

a. Prig to entering base load operation, maintain THERMAL POWER above l

APL and less than or equal to that allowed by Specifica-tion 4.2.2.1.2 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 the target band limit 6,p target flux difference of Specification 3.2.1.1) during this time period. Base load operation g then ppitted providig THERMAL POWER is maintained between APL and APL or between APL and ,

MILLSTONE - UNIT 3 a 3/4 2-8 ~,kmendment.No.J#,60 os12 .

.,..... March 11, 1991 POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued)

. With the relationship specified in 4.2.2.1.4.c not being, satisfied, either of the following actions shall be taken:

(1) Place core in an equilibrium conditio where the limit in 4.2.2.1.2.C is satisfied, and remeasure F (z), or (2) Comply with the requirements of Specification 3.2.2.1 for Fn (z) exceeding its limit by the maximum percent calculated over the core height (z) with the following expression:

F"(z) x W(z)BL-1 ND '

RTP x 100 for P 1 APL O x X(z)

} P l

~

The limits specified in 4.2.2.1.4.

~

4.2.2.1.4.ec~ and 4.2.2.1.4.D l \

l f jf.

are not applicable in the following core plane regions:

(1) Lower core region 0% to 15%, inclusive.

(2) Upper core region 85% t 00% lusive.

or 4. 2.2. s. 4 4.2.2.1.5 When F0 (z f si measured or reasons other than meeting the require-ments of Specificat ons ).2.2.1.2, an overall measured F (z) shall be obtained from a power distribu ion map and increased by 3% to acckunt for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

l l

[

gSTONE-UNIT 3 3/4 2-11 ., Amendment No. # ,60

.- .'.* March 11, 1991 POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR - F n (Z)

THREE LOOPS OPERATING ,

LIMITING CONDITION FOR OPERATION 3.2.2.2 Fg (Z) shall be limited by the following relationships:

RTP F

F0 (Z) 5 0 [K(Z)] for P > 0.375 j P

RTP Fn (Z) 1 (F 0 ) [K(Z)] for P s 0.375 0.375 RTP limit at RATED THERMAL POWER (RTP) specified in F = The F theCOREOPEbTINGLIMITSREPORT(COLR).

THERMAL POWER , and a Where:

P = RATED THERMAL POWER tom K(Z) = the normalized F (Z) as a function of core height speci-1 9

fied in the COLR. l

{ 3'7'2. 2. .

APPLICABILITY: MODE 1. i CTION:

With Fq (Z) exceeding its limit:

a. Reduce THERMAL POWER at least 1% for each 1% Fn(Z) exceeds the !

limit within 15 minutes and similarly reduce lhe 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 t POWER OPERATION may proceed provided the Overpower AT Trip Set- :

points have been reduced at least 1% for each 1% Fn(Z) exceeds the limit. The Overpower AT Trip Setpoint reductibn shall be performed with the reactor in at least HOT STANDBY.

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit re-quired by ACTION a., above; THERMAL POWER may then be increased provided Fn(Z) is demonstrated through incore mapping to be within its limit.

i Millstone - Unit 3 3/4 2-12 I Amendment No. JJ.60 0011 .'

Insert to Page 3/4 2-12 (Page 1 of 2)

Insert 3.2.2.2 With Fo(Z) exceeding its limit:

l a. For RAOC operation with Fo( Z) outside the applicable

! limit specified in the COLR, perform one of the following actions:

(1) 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 Fo (Z) exceeds its limits. 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.

(2) Reduce THERMAL POWER 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 AT Trip Setpoints have been reduced at ;

least 1% for each 1% Fo(Z) exceeds the limit.

The Overpower AT Trip setpoint reduction shall be performed with the reactor in at least HOT STANDBY. l l

(3) Verify that ,,the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load operation.

~

Where it is necess-'ry to calculate the percent that F (Z) exceeds the limits for gtems (1) and (2) above, it shall be calculated as the maximum percent over the core height (z) that F(z) o exceeds its limit by the following expression:

~ ~

F2'( z ) x W(zi E " x K(z) -1 x 100 for P _> O.375 P ,

l

~ '

FJ'( z ) x W(zi F,," x K(z) -1 x 100 for P < 0.375 i 0.375 .

I

'h D

. \

....... . 1 Insert to Page 3/4 2-12 (Page 2 of 2)

b. For base load operation outside the applicable limit specified in the COLR, perform either of the following ,

actions: 1 (1) Place the core in an equilibrium condition where 1 the limit in 4.2.2.2.2.C is satisfied, and ,

remeasure F o"(Z), or 1 (2) Reduce THERMAL POWER 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 AT Trip Setpoints have been reduced at ,

least 1% for each 1% Fo(Z) exceeds the limit. The -

Overpower AT Trip Sotpoint reduction shall be l performed with the reactor in at least HOT STANDBY. !

The perhent that Fo exceeds the limit shall be calculated as the maximum percent over the core i height (z) that F (z) exceeds the limit using the I folloWing expression:

~ ~

F,"( z i x W( 2 ).

2.25 x K(2) -1 x 100 for P > APL" P

c. Identify and correct the cause of the out-of-limit condition prior to increas '.ng THERMAL POWER above the j reduced limit required by ACTION a. irr b., above; 1 THERMAL POWER may then be increased provided F o(Z) is I demonstrated through incore mapping to be within its limit.

I 9 %

y

.~ . , . . .

March 11, 1991

,,a POWER DISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS (Continued)

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

1. With the maximum value of M

F (z)

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

(1) F M(z) shall be increased by 2% over that specified in Specifica-tfon 4.2.2.2.2c, or M

(2) F (z) shall be measured at least once per 7 Effective Full Power DIys until two successive maps indicate that the maximum value of M

F(z)

K(z) .

ove'r the core height (z) is not increasing.

f. With the relationships specified in' Specification 4.2.2.2.2c not being satisfied.

(1) Calculate the maximum percent over the core height (z) that Fg (z) exceeds its limit by the following expression:

F"(z) x W(z)

RTP

-I x 100 for P 2 0.375 0 x K(z)

P 11 k

Millstone - Unit 3 3/4 2-14 diendment No. y , Jp ,60 0011 -

' March 11, 1991 POWER DISTRIBUTION LIMITS l

SURVEILLANCE REOUIREMENTS (Continued) w.

M ) -

F0(z) x W(z) i

~ -1 x 100 for P < 0.375 :

p RTP 0 xK(z) 0.375 (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 oF (z) exceeds its limits as [

determined in Specification 4.Z'.2.2.2f.l. 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 3.2.2.2 for Fg (z) exceeding its limit by the percent calculated, or (c) Verify that the requirements of Specification 4.2.2.2.3 for ;

( base load operation are satisfied and enter base load -

operation. .

\

The limits specified in Specifications 4.2.2.2.2[4

( K. .2.2.2.2) are not applicable in the, following core pfan.2.2.2.2e e regions:

(1) Lower core region from 0% to 15%, inclusive. l (2) Upper core region from 85% to 100%, inclusive. j 4.2.2.2.3 Base load operation is permitted at powers above APLND if the f following conditions are satisfied:

l

a. enterin9 base ' load operation, maintain THERMAL POWER above PriA5t and APL less than or equal to that allowed by Specifica- !

tion 4.2.2.2.2 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 the target band limit about the ;

target flux difference of Specification 3.2.1.2) during this time I period. ,

l I

Base load operation g then pitted providigg THERMAL POWER is maintained between APL and APL or between APL and 100% (whichev-er is most limiting) and F surveillance is maintained pursuant to nBi

( Specification 4.2.2.2.4. APE is defined as the minimum value of:

Millstone - Unit 3 3/4 2-15 AmdndmentNo.?7.,#,60 '

sons -

l

. , .. . . . March 11, 1991 POWER DISTRIBUTION LIMITS l SURVEILLANCE RE0VIREMENTS (Continued)

(1) Prior to entering base load operation after satis {ying Sec-tion 4.2.2.2.3, unless a full core flux map has been taken in the previous 31 Effective Full Power Days gth 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 sapping, and (2) At least once per 31 Effective Full Power Days.

e. . With the maximum value of (z)

K(z) over the core height (z) increasing since the previous detennination i of F (z), either of the following actions shall be taken: !

1 (1) F (z) shall be increased by 2 percent over that specified in 4 2.2.2.4.c, or (2) F (z) shall be measured at least once per 7 Effective Full Power D ys until 2 successive maps indicate that the maximum value of H

F0 II)

X(z) l over the core height (z) is not increasing.

With the relationship specified in 4.2.2.2.4.c not being satisfie ,

either of the following actions shall be taken:

(1) Place core in an equilibrium conditiqp where the limit in 4.2.2.2.2.c is satisfied, and remeasure F' (z), or f

(2) Comply with the requirements of Specification 3.2.2.2 for F (z) exceeding its limit by the maximum percent calculated over nthe ,

core height (z) with the following expression:

(

glistone - Unit 3 3/4 2-17 AdndmentNo.A7,pp,60

March 11, 1991 POWER DISTRIBUTION LIMITS 9

SURVElllANCE REQUIREMENTS (Continued) -

(z) x W(z)BL ND g -1 x 100 for P 2 APL p x K(z) ga M. The limits specified in 4.2.2.2.4. ,4.2. 2.2.4.eM not applicable in the following core plane regions:

e 4. 2.2.43 are (1) Lower core region 0% to 15%, inclusive.

(2) Upper core region 85% t usive.

Og 4.2.2.2.5 When F0 (z) ments of Specification,is measure (/for reasons other than meeting the require-3 4.2.2.2.2{ an overall measured F n (z) shall be obtained from a power distribution map and increased by 3% to acc' bunt for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

l i

i i

Millstone - Unit 3 3/4 2-18 Amendment No. 77, g ,60 0011

March 11, 1991 REACTOR COOLANT SYSTEM .

COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION

, J 3.4.1.4.2 Two residual heat removal (RHR) looos shall be OPERABLE

and at lengt one_ RHR ingp_shall be in operatipA**_ /The chemical and volume contro system (CVCS) shall be aligned to preclude Reactor Coolant System boron concentration reduction or the_SjiUTDOWN MARGIN of Specification 3.1.1.2 shall be met. f ~

APPLICABILITY: H0DE 5 with less than two reactor coolant loops filled.

ACTION:

a.

With less than the above required RHR loops OPERABLE, iirc:Jiately initiate corrective action to return the required RHR lcops to l OPERABLE status as soon as possible. l b.

With no RHR loop in operation, suspend all operations involving a '

reduction in boron concentration of the Reactor Coolant System and immediately loop initiate corrective action to return the required RHR to operation.

c. With the CVCS dilution flow paths not closed and secured n position, imediately close and secure the paths or satisfy the q SHUTDOWN MARGIN of Specification 3.1.1.2.

SURVEILLANCE RE0VIREMENTS 4.4.1.4.2.1 Specificati. The required RHR loops shall be demonstrated OPERABLE pursuant to on 4.0.5.

4.4.1.4.2.2 At least one RHR loop shall be determined to be in operation and i circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

~

(4.4.1.4.2.3 At least per 31 days the following valves shall be verified closed and locked.

administrative controlThe valves may be opened on an intermittent basis under, y ,

0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other RHR loop is OPERABLE and in operation.

- The RHR pump may be deenergized for up to I hour provided: (1) no opera-tions are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 108F below saturation temperature.

gSTONE-UNIT 3 3/4 4-6 Amendment No. 60

March ll, 1991 SURVEILLANCE REOUIREMENTS (Con't)

,/

Valve ber Valve Function Yalve P ion

1. V304(Z Primary Grade Water Closed to CVCS '

2. V120(Z-) Moderating Hx Outlet

3. Closed V147(Z-) BTRS Outlet Closed

4. V797(Z-) Failed Fuel Moni ing Closed Flushing S. V100(Z-) Resin Sluicp, CVCS Cation Closed Bed Demipefalizer

6. VS71(Z-) Resin,STulce, CVCS Cation Closed

7. Alemineralizer Vill (Z-) es n Sluice, CVCS Cation Closed Bed [Ugmineralizer

8. V112(Z-) Resin 1]uice, CVCS Cation Closed

9. Bed Demineralizer V98(Z-)/V99(Z- Resin Slutte CVCS Mixed Closed Bed Deminerh,4zer i

10. VS69(Z-) 70(Z-) Resin Sluice, YYCS Mixed Closed 6

11. Bed Demineralize)

V107 /V109(Z-)- Resin Sluice, CVC ixed Closed

12. Bed Demineralizer 8(Z-)/V110(2-). Resin Sluice, CYCS Mi ed Closed Bed Demineralizer

\

3etc TE TH's PA

(

MILLSTONE - UNIT 3 3/44-6a 0036 Amendment No. 60

3/4.9 REFUELING OPERATIONS II' I

, 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure met; either: that the more restrictive of the following reactivity conditions is

a. A K,ff of 0.95 or less, or b.

A boron concentration of greater than or equal to 2600 ppm.

4. t .1. 2. 2. i Additionally, secured the CVCS valves of Specification 4:4rh472 3 shall be closed and in position. i APPLICABILITY: MODE 6.*

ACTION:

a. With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater

i than or equal to 6300 ppm boron or its equivalent until K is i

reducedtolessthanorequalto0.95ortheboronconcentratYokis j rectored to greater than or equal to 2600 ppm, whichever is the more

( restrictive.

b. 4.1.1.2,z With any of the CVCS valves of Specification 4.4.1.4.2.3 not closed ** and secured in position, immediately close and secure the valves.

{

j SURVEILLANCE REOUIREMENTS 4.9.1.1.1 be determined prior to:The more restrictive of the above two reactivity conditions shall' a.

Removing or unbolting the reactor vessel head, and

b. -

1 Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within tha reactor vessel. ,

4.9.1.1.2 The boron concentration of the Reactor Coolant System and the refueling 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . canal shall be determined by chemical analysis at least once per 4.9.1.1.3 N. I .1. 2. 2.

The CVCS valves of Specification -4:471.4.2.0 shall be verified closed and locked at least once per 31 days.

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with

( the head removed.

- Except those opened under administrative control. '

MILLSTONE - UNIT 3 0025 3/4 9-1 ' Amendment No. g ,60 I

_ _ _ _ _ _ _ _ __ _ _ - - - - - - - - - i

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN o

A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T In MODES 1 and 2, the most restrictive condition occurs at EOL with TV9 at no load operating temperature, and is associated with a postulated stMriline break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a

minimum transient. SHUTDOWN MARGIN of 1.3% AK/K is required to control the reactivity Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions.

In MODES 3, 4 and 5, the most restrictive condition occurs at BOL, associated with a boron dilution accident. In the analysis of this accident, a minimum g

SHUTDOWN MARGIN as defined in Specification 3/4.1.1.2 is required to allow the i operator to total 15loss minutes from the initiation of the Shutdown Margin Monitor alarm of SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting requirement and is consistent with the accident analysis assumptions. The required SHUTDOWN MARGIN is plotted as a !

function of RCS critical boron concentration. L 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT 1

The limitations on moderator temperature coefficient (MTC) are provided I to ensure that the value of this coefficient remains within the limitino condition assumed in the FSAR accident and transient analyses. ~

The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC, value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.

m -

3

% \o&m c.bsd d A reprd VAw, m M S (wA Ac Q M t

wa\ pru eh pi% cd eccdttha bem &W% o( We Rdr

{ 4ckd Sp% bg prd &j k of u4rdd ux.kr 4c % Ro hlLLSTONE - UNIT 3 B 3/4 1-1 0026 ~ 'Amencment No. 29.50

March 11, 1991 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOL ANT LOOPS AND COOLANT CIRCUL ATION The plant is designed to operate in MODES I and 2 with three or four '

reactor coolant loops in operation and maintain DNBR greater than the design limit during all normal operations and anticipated transients. With less than the required reactor coolant loops in operation this specification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In MODE 3, three reactor coolant loops, and in Mode 4, two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident; however, a single reactor coolant loop provides sufficient heat removal capacity if a bank withdrawal accident can be prevented, i.e., by opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop for removing decay heat; or RHR loop provides sufficient heat removal capability but single failure considerations require that at least two loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators /

as a heat removing component, require that at least two RHR loops be OPERABLE. />

The locking closed of the required valves G Mode 5 (with the loops not filled) will preclude the possibility of uncor.crolled boron dilution of the Reactor Coolant~~~~~

System by preventing flow to ine RCS of unborated water.

~ /

The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity Coolant System.

changes during boron concentration reductions in the Reactor The reactivity change rate associated with boron ' reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting an RCP with one or more RCS cold legs less than or equal to 350*F are provided to prevent RCS pressure transients, caused 3 by energy additions from the Secondary Coolant System, which could exceed the !

I limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either: .

(1) restricting the water volume in the pressurizer and thereby l providing a volume for the reactor coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of l each steam generator is less than 50*F above each of the RCS cold leg l temperatures.

1 i

i MILLSTONE - UNIT 3 B 3/4 4-1 Amendment No. 7,60 0029 !

Docket No. 50-423 B14803 l Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Shutdown Margin, Reactor Trip System, and Heat Flux Hot Channel Factor Retyped Up Pages 9

4 July 1994 l

l a

INDEX LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRENENTS SECTION EASE 3/4.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Shutdown Margin - MODES 1 AND 2 . . . . . . . . . . . . . . 3/4 1-1 Shutdown Margin - MODES 3, 4, AND 5 LOOPS FILLED ..... 3/4 1-3 FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH FOUR LOOPS IN OPERATION ............. 3/4 1-4 FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH THREE LOOPS IN OPERATION . . . . . . . . . . . . . 3/4 1-5 FIGURE 3.1-3 REQUIRED SHUTDOWN MARGIN FOR MODE 4 . . . . . . . . . . 3/4 1-6 FIGURE 3.1-4 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS FILLED . . . . . . . . . . . . . . . . . 3/4 1-7 Shutdown Margin - Cold Shutdown -

Loops Not Filled ..................... 3/4 1-8 FIGURE 3.1-5 REQUIRED SHU160WN MARGIN FOR MODE 5 WITH RCS LOOPS NOT FILLED ................. 3/4 1-9 l Moderator Temperature Coefficient . . . . . . . . . . . . . 3/4 1-10 Minimum Temperature for Criticality . . . . . . . . . . . . 3/4 1-12 3/4.1.2 B0 RATION SYSTEMS Flow Path - Shutdown ................... 3/4 1-13 Flow Paths - Operating .................. 3/4 1-14 Charging Pump - Shutdown ................. 3/4 1-15 Charging Pumps - Operating ................ 3/4 1-16 Borated Water Source - Shutdown . . . . . . . . . . . . . . 3/4 1-17 Borated Water Sources - Operating . . . . . . . . . . . . . 3/4 1-18 3/4.1.3 M0VABLE CONTROL ASSEMBLIES Group Height ....................... 3/4 1-20 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN IN0PERABLE FULL-LEliGTH R0D ......... 3/4 1-22 Position Indication Systems - Operating . . . . . . . . . . 3/4 1-23 NILLSTONE - UNIT 3 iv Amendment No. pp, pp 0206

REACTIVITY CONTROL SYSfENS SHUTDOWN NARGIN - COLD SHUTDOWN - LOOPS NOT FILLED LINITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to a) the limits shown in Figure 3.1-5 or l b) the limits shown in Figure 3.1-4, with the chemical and volume !

, control system (CVCS) aligned to preclude reactor coolant system ,

boron concentration reduction. ;

APPLICABILITY: MODE 5 LOOPS NOT FILLED f ACTION:

P

a. With the SHUTDOWN MARGIN less than the above, immediately initiate and l l continue boration at greater than or equal to 33 gpm of a solution '

containing greater than or equal to 6300 ppm boron or equivalent until i the required SHUTDOWN MARGIN is restored. l

b. With the CVCS dilution flow paths not closed and secured in position in accordance with Specification 3.1.1.2(b), immediately close and secure the paths or meet the limits shown in Figure 3.1-5. l ;

SURVEILLANCE REQUIRENENTS l 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above:

a. Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acce) table with an increased allowance for the withdrawn worth of t1e immovable or untrippable control rod (s); and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months h" consideration of the following factors:

1) Reactor Coolant System boron concentration,

2) Control rod position,

3) Roactor Coolant System average temperature,

4) Fuel burnup based on gross thermal energy generation, NILLSTONE - UNIT 3 3/4 1-8 Amendment No. pp, ,

0209 j l

1 l

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

REACTIVITY CONTROL SYSTENS SURVEILLANCE REQUIRENENTS (Continued)

5) Xenon concentration, and

6) Samarium concentration. !

4.1.1.2.2 At least once per 31 days the following valves shall be verified closed and locked. The valves may be opened on an intermittent basis under ;

administrative controls except as noted. ;

Valve Number Valve Function Valve Position i

1. V304(Z-) Primary Grade Water Closed to CVCS !

2. V120(Z-) Moderating Hx Outlet Closed

3. V147(Z-) BTRS Outlet Closed i i

4. V797(Z-) Failed Fuel Monitoring Closed Flushing

5. V100(Z-) Resin Sluice, CVCS Cation Closed i Bed Demineralizer r

6. V571(Z-) Resin Sluice, CVCS Cation Closed -

Bed Demineralizer ;

7. V111(Z-) Resin Sluice, CVCS Cation Closed !

Bed Demineralizer !

8. V112(Z-) Resin Sluice, CVCS Cation Closed !

Bed Demineralizer

9. V98(Z-)/V99(Z-) Resin Sluice, CVCS Mixed Closed l Bed Demineralizer !

10. V569(Z-)/V570(Z-) Resin Sluice, CVCS Mixed Closed Bed Demineralizer

11. V107(Z-)/V109(Z-) Resin Sluice, CVCS Mixed Closed Bed Demineralizer .

12. V108(Z-)/V110(Z-) Resin Sluice, CVCS Mixed Closed Bed Demineralizer t

13. V305(Z-)* Primary Grade Water Closed ;

to Charging Pumps i

i i

This valve may not be opened under administrative controls. !

NILLSTONE - UNIT 3 3/4 1-8a Amendment No.

0208

O G

6 8y 10.00 4

o -

9.00 q e.00

<a 7.00 O (2358. 5,930)

B.00 (1395, 5.494) -

a y

l "*

r s . 4.00 g

)

I w 3.00 2.00

i. - m 1.0 . ,

k R 0.00 o

{ 400 000 1200 1600 2000 2400 2000 g

g RCS CRITICAL BORON CONCENTRATION (ppm)

FIGURE 3.1-5 REQUIRED SHUTDOWN NARGIN FOR N0DE 5 WITH RCS LOOPS NOT FILLED l

POWER DISTRIBUTION LINITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F,JZ)

FOUR LOOPS OPERATING LINITING CONDITION FOR OPERATION 3.2.2.1 Fo(Z) shall be limited by the following relationships: ll yam f o(2) s P K(2) for P > 0.5 -

p*aw Fa(Z) S K(Z) for P s 0.5 0.5 Fgre - the Fo limit at RATED THERMAL POWER (RTP) provided in the core operating limits report (COLR).

THERMAL POWER Where: P= RATED THERMAL POWER, and K(Z) - the normalized Fo(Z) as a function of core height specified in the COLR. ;

APPLICABILITY: MODE 1.

ACTION:

With Fo(Z) exceeding its limit:

a. For RAOC operation with Fo(Z) outside the applicable limit specified :

in the COLR, perform one of the following actions:

(1) 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 Fo(Z) exceeds its limits. Within i 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints to these modified t limits. :

l l

l MILLSTONE - UNIT 3 3/4 2-5 Amendment W. pp, pp, !

0210 t

POWER DISTRIBUTION LINITS LINITING CONDITION FOR OPERATION (Continued)

(2) Reduce THERMAL POWER at least 1% for each 1% Fo(Z) exceeds the i 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 AT Trip Setpoints have been reduced at least 1% for each 1%

Fo(Z) exceeds the limit.

(3) Verify that the requirements of Specification 4.2.2.1.3 for base lotd operation are satisfied and enter base load operation.

Where it is necessary to calculate the percent that Fo(Z) exceeds the limits for items (1) and (2) above, it shall be calculated as the maximum percent over the core height (Z) that Fo(Z) exceeds its limit by the following expressicn:

-1 x 100 for P a 0. 5

x K(Z) p

)* -1 x 100 for P < 0. 5 0.5 ,

b. For base load operation outside the applicable limit specified in the COLR, perform either of the following actions:

(1) Place the core in an equilibrium condition where the limit in 4.2.2.1.2.C is satisfied, and remeasure Fs(Z), or MILLSTONE - UNIT 3 3/4 2-6 Amendment No.

0210

POWER DISTRIBUTION LINITS LINITING CONDITION FOR OPERATION (Continued)

(2) Reduce THERMAL POWER 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 AT Trip setpoints have been reduced at least 1% for each 1%

Fo(Z) exceeds the limit. The percent that Fo exceeds its limit shall be calculated as the maximum percent over the core ,

height (Z) by the following expression: ;

t

'* * "' -1 x 100 for P ;t APL "

'* x K(Z)

c. Identify and correct the cause of the out-of-limit condition prior i to increasing THERMAL POWER above the reduced limit required by '

ACTION a or b, above; THERMAL POWER may then be increased provided Fo(Z) is demonstrated through incore mapping to be within this limit.

i SURVEILLANCE REQUIRENENTS l 1

4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 For PAOC operation, Fo(Z) shall be evaluated to determine if Fo(Z) i is within its limit by:

t

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

map at any THERMAL POWER greater than 5% of RATED THERMAL POWER. ;

b. Increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

Verify the requirements of Specification 3.2.2.1 are satisfied.

NILLSTONE - UNIT 3 3/4 2-7 Amendment t JP,pp, l 0210

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

. I POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRENENTS (Continued) l l

c. Satisfying the following relationship: [

I Ff(Z) s F*"" x K(Z) for P > 0.5 i PxW(Z)

Ff(Z)$ F*"" x K(Z) for P s 0.5 ;

W'Z)x0.5 .

tl where Fs(Z) is the measured Fo(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FS'" is the Fo limit, 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 distribution transients encountered

~

during normal operation. FS", K(Z), and W(Z) are specified in' the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.6. ;

d. Measuring F"o(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) l was last determined,* or (2) At least once per 31 Effective Full Power Days, whichever occurs ;

first. .

e. With the maximum value of :

Ff(Z)

K(Z) over the core height (Z) increasing since the previous determination i of Fs(Z), either of the following actions shall be taken: .

(1) Fs(Z) shall be increased by 2% over that specified in Specifi- !

cation 4.2.2.1.2c, or

During power escalation at the beginning of each cycle, power level n.4y be increased until a power level for extended operation has been achieved and power distribution map outlined.

NILLSTONE - UNIT 3 0210 3/4 2-8 Amendment No. pp, pp. )

l POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

(2) F#(Z) shall be measured at least once per 7 Effective Full !

Power Days until two successive maps indicate that the maximum l value of ;

Ff(Z)

K(Z) i over the core height (Z) is not increasing.

f. The limits specified in Specifications 4.2.2.1.2c and 4.2.2.1.2e above are not applicable in the following core plane regions: l (1) Lower core region from 0% to 15%, inclusive. l (2) Upper core region from 85% to 100%, inclusive. ;

4.2.2.1.3 Base load operation is permitted at powers above APL"D if the following conditions are satisfied: l

a. Prior to entering base load operation, maintain. THERMAL POWER above ;

APL" and less than or equal to that allowed by Specifica- {

tion 4.2.2.1.2 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 the target band limit about the l target flux difference of Specification 3.2.1.1) during this time j period. Base load operation is then permitted providing THERMAL POWER is maintained between APL" and APL" or between APLND and 100%

(whichever is most limiting) and Fo surveillance is maintained !

pursuant to Specification 4.2.2.1.4. APL" 1.; defined as the !

minimum value of:

APL" = F*" ' x K(Z) x 100% i Fl(Z) x W(Z),

l over the core height (Z) where: F#(Z) is the measured Fo(Z) increased by the allowances for manufacturing tolerances and mea-surement uncertainty. The Fa limit is FST". W(Z)a is the cycle- .

dependent function that accounts for limited power distribution ;

transient encountered during base load operation. F$'", K(Z), and !

W(Z)n are specified in the COLR as per Specification 6.9.1.6.

MILLSTONE - UNIT 3 3/47.-9 Amendment No. JP, pp, l 0210

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRENENTS (Continued)

b. Durin APL" g base then theload operation, conditions of if4.2.2.1.3.a the THERMAL shall POWER is decreased be satisfied before below reentering base load operation.

4.2.2.1.4 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" .

b. Increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

Verify the requirements of Specification 3.2.2.1 are satisfied.

c. Satisfying the following relationship:

Ff(Z) s F*"" x K(Z) for P > APL""

P x W(Z) ,

where: FU(Z) is the measured Fo(Z). FS'" is de Fo limit, the normalized Fo(Z) as a function of core height. P is the e relative THERMAL POWER. W(Z)g is the cycle-dependent function that accounts for limited power distribution transients encountered during base load operation. FS'", K(Z), and W(Z)a are specified in the COLR as per Specification 6.9.1.6.

d. Measuring Fy(Z) in conjunction with target flux difference determi-nation according to the following schedule:

(1) Prior to entering base load operation after satisfying Sec-tion 4.2.2.1.3 unless a full core flux map has been taken 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 mapping, and (2) At least once per 31 Effective Full Power Days.

NILLSTONE - UNIT 3 3/4 2-10 Amendment No. pp, JP, 0210 l

(

b POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

e. With the maximum value of Fy(Z)

K(Z) over the core height (Z) increasing since the previous determination '

of Fs(Z), either of the following actions shall be taken:

(1) Fs(Z) shall be increased by 2% over that specified in 4.2.2.1.4.c, or (2) F#(Z) shall be measured at least once per 7 Effective Full !

Power Days until 2 successive maps indicate that the maximum i value of Ff(Z)

K(2) over the core height (Z) is not increasing.

f. The ;11mits specified in 4.2.2.1.4.c and 4.2.2.1.4.e are not applicable in the following core plane regions: ,

(1) Lower core region 0% to 15%, inclusive.

(2) Upper core region 85% to 100%, inclusive. ;

4.2.2.1.5 When Fo(Z) is measured for reasons other than meeting the require- ,

ments of Specifications 4.2.2.1.2 or 4.2.2.1.4, an overall measured Fo(Z) shall l be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement t uncertainty. l I

l l

l MILLSTONE - UNIT 3 3/4 2-11 Amendment No. pp, JP, 0210

POWER DISTRIBUTION LINITS HEAT FLUX HOT CHANNEL FACTOR - FJZ)

THREE LOOPS OPERATING LINITING CONDITION FOR OPERATION 3.2.2.2 Fo(Z) shall be limited by the following relationships:

paw.

Fa (Z) s [K(2)] for P > 0.375 P

paw f o(2) s 0.375

[K(2)] for P s 0.375 FS'" - The fo limit at RATED THERMAL POWER (RTP) specified in the CORE OPERATING LIMITS REPORT (COLR).

Where: P, POWER ,ng RATED THERMAL POWER K(Z) - the normalized Fo(Z) as a function of core height speci-fied in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With Fo(Z) exceeding its limit:

a. For RAOC operation with Fo(Z) outside the applicable limit specified in the COLR, perform one of the following actions:

(1) 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 Fo(Z) exceeds its limits. 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.

(2) Reduce THERMAL POWER 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 gIgLSTONE-UNIT 3 3/4 2-12 Amendment No. 59, pp,

POWER DISTRIBUTION LINITS LINITING CONDITION FOR OPERATION (Continued)

POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1% Fo(Z) exceeds the limit. The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.

(3) Verify that the requirements of Specification 4.2.2.1.3 for base load operation are satisfied and enter base load operation.

Where it is necessary to calculate the percent that Fo(Z) exceeds the limits for items (1) and (2) above, it shall be calculated as the maximum percent over the core height (Z) that Fo(Z) exceeds its limit by the following expression:

-1 x 100 for P2 0. 37 5

, x X (Z)

#' -1 x 10 0 for P< 0. 37 5 0.375 '

b. For base load operation outside the applicable limit specified in the COLR, perform either of the following actions:

(1) Place the core in an equilibrium condition where the limit in 4.2.2.2.2.C is satisfied, and remeasure Fs(Z), or I (2) Reduce THERMAL POWER at least 1% for each 1% Fa(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 AT Trip i Setpoints have been reduced at least 1% for each 1% Fo(Z) l exceeds the limit. The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.

The percent that Fo exceeds the limit shall be calculated as the maximum percent over the core height (Z) that Fo(Z) exceeds the limit using the following expression:

l NILLSTONE - UNIT 3 3/4 2-13 Amendment No.

0210

POWER DISTRIBUTION LIMITS LINITING CONDITION FOR OPERATION (Continued)

Z) x M Z)"' -1 x 10 0 for P X APL '*

2.25 y ggg) p i

c. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a or b, above; THERMAL POWER may then be increased provided i Fo(Z) is demonstrated through incore mapping to be within its limit.

f SURVEILLANCE REQUIRENENTS ;

4.2.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2.2 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 at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. Increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2.2 are satisfied.

c. Satisfy the following relationship:

Ff(Z)s F" x K(Z) for P > 0.375 PxW(Z)

F*" x K(Z) for P $ 0.375 Ff(Z) s #(Z) x 0.375 where F#(Z) is the measured Fo(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FS'" is the Fo limit, 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 distribution transients encountered during normal operation. FSTP, K(Z), and W(Z) are specified in the COLR as ,

per Specification 6.9.1.6. )

l l

NILLSTONE - UNIT 3 3/4 2-14 Amendment No. JJ, 77, l I 0210

. . .-. ~ . . . __ -. i

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRENENTS (Continued)

I

d. Measuring F%(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.

e. With the maximum value of Fy(Z)

K(Z) over the core height (Z) increasing since the previous determination of FT(Z), either of the following actions shall be taken:

(1) F5(Z) shall be increased by 2% over that specified in Specifica-tion 4.2.2.2.2c, or (2) F5(Z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that the maximum value of Ff(Z)

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

f. The limits specified in Specifications 4.2.2.2.2c and 4.2.2.2.2e 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.

During power escalation at the beginning of each cycle, the power level may be !

increased until a power level for extended operation has been achieved and power distribution map obtaitied. .

1 MILLSTONE - UNIT 3 3/4 2-15 Amendment No. 77. JP, JP l 0210

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.2.3 Base load operation is permitted at powers above APL" if the following conditions are satisfied:

a. Prior to entering base load operation, maintain THERMAL POWER above APL" and less than or equal to that allowed by Specification 4.2.2.2.2 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 the target band limit about the target flux difference of Specification 3.2.1.2) during this time period.

Base load operation is then providing THERMAL POWER is maintained between APL" and APL ,permittedor between APL" and 100% (whi most limiting) and Fo surveillance is maintained pursuant to Specification 4.2.2.2.4. APL" is defined as the minimum value of:

APL" = F*"" x K(Z) x 100%

F;(Z) x W(Z),

over the core height (Z) where: F$(Z) is the measured Fo(Z) increased by the allowances for manufacturin tolerances and measurement uncertainty. The Fo limit is FS". g W(Z)g is the cycle-dependent function that accounts for limited power distribution transient encountered during base load operation. FS'", K(Z), and W(Z)g are specified in the COLR as per Specification 6.9.1.6.

b. Durin APL" gthen basethe loadconditions operation, ifofthe THERMALshall 4.2.2.2.3.a POWER is decreased be satisfied below before reentering base load operation.

4.2.2.2.4 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" .

b. Increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2.2 are satisfied.

NILLSTONE - UNIT 3 3/4 2-16 Amendment No. # , pp, pp 0210

l l

POWER DISTRIBUTION LINITS SURVEILLANCE REQUIRENENTS (Continued) ,

i l

c. Satisfying the following relationship: l

' Ff(Z) $ F*"" x K(Z) for P > APL""

P x W(Z) , i i

where: F%(Z) is the measured Fa(Z). The FS'" is the Fo limit, the :

normalized Fa(Z) as a function of core height. P is the relative W(Z)g is the cycle-dependent function that accounts

~

THERMAL POWER.

for limited power distribution transients encountered during base load :

operation. FS", K(Z), and W(Z)a are specified in the COLR as per Specification 6.9.1.6. :

i Measuring FY(Z) in conjunction with target flux difference determina-

~

d.

tion according to the following schedule: i (1) Prior to entering base load operation after satisfying Sec- l tion 4.2.2.2.3, unless a full core flux map has been taken in the ;

previous 31 Effective Full Power Days with the relative THERMAL ,

POWER having been maintained above APL"D for the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to .

mapping, and .

l (2) At least once per 31 Effective Full Power Days.

e. With the maximum value of l Ff(z)

K(z) i i

over the core height (Z) increasing since the previous determination i of F$(Z), either of the following actions shall be taken-l (1) FT(Z) shall be increased by 2 percent over that specified in !

4.2.2.2.4.c, or i

l NILLSTONE - UNIT 3 3/4 2-17 Amendment No. 77, JP, pp, l 0210 l

.. ___.-_____i

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

(2) F5(Z) shall be measured at least once per 7 Effective Full Power Days until 2 successive maps indicate that the maximum value of F;(Z)

K(2) over the core height (Z) is not increasing.

f. The limits specified in 4.2.2.2.4.c and 4.2.2.2.4.e are not applicable in the following core plane regions:

(1) Lower core region 0% to 15%, inclusive.

(2) Upper core region 85% to 100%, inclusive.

4.2.2.2.5 When Fo(Z) is measured for reasons other than meeting the require-ments of Specifications 4.2.2.2.2 or 4.2.2.2.4, an overall measured Fo(Z) shall l be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

l l

)

MILLSTONE - UNIT 3 3/4 2-18 Amendment No. 77, pp. 77. l 0210 L.

REACTOR COOLANT SYSTEN COLD SHUTDOWN - LOOPS NOT FILLED LINITING CONDITION FOR OPERATION f

3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE

and at ;

least one RHR lcop shall be in operation.** l APPLICABILITY: MODE 5 with less than two reactor coolant loops filled.

f ACTION: [

a. With less than the above required RHR loops OPERABLE, immediately t initiate corrective action to return the required RHR loops to 3 OPERABLE status as soon as possible. !

b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR ,

loop to operation.

SURVEILLANCE REQUIRENENTS ;

4.4.1.4.2.1 The required RHR loops shall be demonstrated OPERABLE pursuant !

to Specification 4.0.5.

4.4.1.4.2.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

t l

0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other RHR loop is OPERABLE and in operation.

- The RHR pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided: (1) no opera- !

tions are permitted that would cause dilution of the Reactor Coolant System !

boron concentration, and (2) core outlet temperature is maintained at least t 10*F below saturation temperature.

NILLSTONE - UNIT 3 3/4 4-6 Amendment No. pp. ,

0215

THIS PAGE INTENTIONALLY DELETED l

i NILLSTONE - UNIT 3 3/4 4-6a Amendment No. J7 0215

s .. .

3/4.9 REFUELING OPERATIONS I 3/4.9.1 BORON CONCENTRATION LINITING CONDITION FOR OPERATION 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:

a. A K.,, of 0.95 or less, or

b. A boron concentration of greater than or equal to 2600 ppm.

t' Additionally, the CVCS valves of Specification 4.1.1.2.2 shall be closed and l secured in position.

APPLICABILITY: MODE 6.*

ACTION:

4

a. With the . requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or ,

positive reactivity changes and initiate and continue boration at ,

greater than or equal to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or its equivalent until K,,, is reduced to less than or equal to 0.95 or the boron concentration is >

restored to greater than or equal to 2600 ppm, whichever is the more e restrictive. !

b. With any of the CVCS valves of Specification 4.1.1.2.2 not closed ** l and secured in position, immediately close and secure the valves, j i

SURVEILLANCE REQUIRENENTS t

4.9.1.1.1 -The more restrictive of the above two reactivity conditions shall be ;

determined prior to: l

a. Removing or unbolting the reactor vessel head, and i

b. Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per i 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l 4.9.1.1.3 The CVCS valves of Specification 4.1.1.2.2 shall be verified closed l and locked at least once per 31 days.

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

1

- Except those opened under administrative control.

NILLSTONE - UNIT 3 3/4 9-1 Amendment No. pp, pp, i 0218 l

. l. h' ~

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable .

limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. ;

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,y,. In MODES I and 2, the most restrictive condition occurs at E0L with T ,, at no load operating ;

temperature, and is associated with a postulated steam line break accident and :

' resulting ' uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% AK/K is required to control the reactivity :

transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this ;

limiting condition and is consistent with FSAR safety analysis assumptions. 1 In H0 DES 3, 4 and 5, the most restrictive condition occurs at BOL, associated with a boron dilution accident. In the analysis of this accident, a minimum SHUTDOWN MARGIN as defined in Specification 3/4.1.1.2 is required to allow the operator 15 minutes from the initiation of the Shutdown Margin Monitor alarm to total loss of SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting recuirement and is consistent with the accident analysis assumption. The requirec SHUTDOWN MARGIN is plotted as a function of RCS critical baron concentration.

The locking closed of the required valves in MODE 5 (with the loops not filled) will preclude the possibility of uncontrolled boron dilution of the Reactor Coolant System by preventing flow of unborated water to the RCS.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided ;

to ensure that the value of this coefficient remains within the limiting i condition assumed in the FSAR accident and transient analyses. i The MTC values of this specification are applicable to a specific set of !

plant conditions; accordingly, verification of MTC values at conditions other !

than those explicitly stated will require extrapolation to those conditions in !

order to permit an accurate comparison.

The most negative MTC, value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.

MILLSTONE - UNIT 3 B 3/4 1-1 Amendment No. 77, JP 0217

3/4.4 REA.G. TOR COOLANT SYSTEN BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate in MODES 1 and 2 with three or four reactor coolant loops in operation and maintain DNBR greater than the design limit during all normal operations and anticipated transients. With less than the required reactor coolant loops in operation this specification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In MODE 3, three reactor coolant loops, and in Mode 4, two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident; however, a single reactor coolant loop provides sufficient heat removal capacity if a bank withdrawal accident can be prevented, i.e., by opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two RHR loops be OPERABLE.

The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting an RCP with one or more RCS cold legs less than or equal to 350*F are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either: (1) restricting the water volume in the pressurizer and thereby providing a volume for the reactor coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50*F above each of the RCS cold leg temperatures.

1 l

MILLSTONE - UNIT 3 B 3/4 4-1 Amendment No. 7, S ,

0218 j

ML20071L107

Text

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