Text

Proposed Changes to Tech Specs Pages 3/4 1-3,3/4 3-3, 3/4 3-4,3/4 3-5,3/4 3-8,3/4 3-9 & 3/4 9-2 Re Alarm to Alert Operators of Dilution Event
	ML20003D524
Person / Time
Site:	Calvert Cliffs
Issue date:	03/23/1981
From:	; BALTIMORE GAS & ELECTRIC CO.
To:	;
Shared Package
ML20003D518	List: ML20003D517; ML20003D524;
References
	NUDOCS 8103270602
	Download: ML20003D524 (10)
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-

REACT nliY COMiROL SY51 EMS SHUTDOWN MARGIN - Tava 1 OD j .. LIMITING CONDITION FOR OPERATION

,3.1.1.2. l The SHUTDOWNAM RGIN shaTT be > 3.0% ak/k. . . [

~ ~ " ' ~ ~ ~ - ~ ' ~ " ' ' ' ' ~ ~

APPLICABILITI5 MODE 5 gr. Pressurizer level ,> 90 inches from bottom of the pressurizer.

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I ACTION: -

a. With the SHUTDOWN MARGIN < 3.0% ak/L,. immediately initiate and continue boration at 3,~40 gpm.cf 2300 ppm boric acid solution or equivalent until the required SMUTDOWN MARGIN is restored. ,

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SURVEILLANCE REOUIREMENTS

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=- 4.1.1.1,lThe SHUTDOWN MARGIN shall be determined to be 3,3.0% Ak/k: .

[

.:::. :: i-. .

a. Within one hour after detection of an inoperable CEA(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 CEA(s) is ino.perable.

If the inoperable CEA is immovable or untrippable, the above

. requ. ired SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untri'ppable CEA(s).

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 facto rs :,. ' -;_ - .;

! 1. Reactor coolant system boron concentration,

- 2 '. CEA position,

3. Reactor coolant system average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon . concentration, and Samarium concentrat.i on.

6.

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CALVERT CLIFFS - UNIT 1 3/4 1-3 Amen'dment No. 48

'. REACTIVITY CONTROL. SYSTEMS' SHUTDOWN MARGIN - T,y, < 200 F _,

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LIMITING CONDITION FOR OPERATION W'

3.1.1.2,1The SHUTDOWN MARGIN shaTT be > AMIS ak/k . . l

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APPLICABILITY:. MODE 5

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4. Pressurtzer level '< 90 inches from bottom of the pressurizer and all sources of non-borated water < 08 gpm.

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ACTION: .

. . . __ E .

49

a. With the SHUTDOWN MARGIN < h:tS ak/k,. immediately initiate and continue boration at >.'40 gpm.of 2300 ppm boric acid solution or equivaient until the required SHUTDOWN MARGIN is restored. ,

l

.=:.

..b.t With the pressur$;ptr drained to < 90 inches and all sources of non-_

borated water > 60 gpm, immediately suspend all operations involving

~

.,. positive reactivity changes while the SHUTDOWN MARGIN is increased to

. . - compensate for the additional sources of non-borated water or reduce .

. - the sources of non-borated water to < 46 gpm. - ~ vy

- - - ' ~ - " - - --

i EEE

~' SURVEILLANCE REQUIREMENTS'~"

%:r>

EEEF .

! 4.1.1.2.t The SHUTDOWN MARGIN shal1 be. determined to be peOS ak/k: -

a. Within . . .ne hdur' after-ed' tection of an inoperable CEA(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 CEA(s) is inoperable.

If the inoperable CEA is immovable or untrippable, the above

- required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untri' pable p CEA(s).

b. At least once per .24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s- by consideration of the following I factors: - ; ,e

1. Reactor coolant system boron concentration,

- 2. CEA position,

3. Reactor coolant system average temperature,

4. Fuel burnup based on gross thermal energy generation,

5. Xenon . concentration, and Samarium concentration.

6. ,

4.1.1.2.E With the pressurizer drained to < 90 inches determine: _,

a. Within one hour and every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that the level ~

in the reactor co61 ant system is above the bottom of the hot leg nozzles, and E=E.

ss=

b. Within one hour and every 12 h,oyrs thereafter that the sources of non-borated water are < 40 'g'pm or the shutdown margin has compensated for the additional sources.

CALVERT CLIFFS - UNIT 1 _

3/4 1-3 __

Amendment No. 48

q jp qy;p-C i .-

g . TABLE 3.3-1 (Continued)_

G g REACTOR PROTECTIVE INSTRUMENTATION

-t .

n .

C' -

- HINIMUM i

TOTAL N0. CilANNELS CllANNELS APlLICABLE 3 . . ..

FUNCTIONAL UNIT 0F CilANNELS TO TRIP OPERABLE H0 DES ACTION

'/

E 11.' Wide Range Logaritinic Neutron -

-i Flux Monitor .

a. Startup and Operating--Rate 1, 2 and *

~

of Change of Power - liigh 4 : 2(d) ..

3(f) 27

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b.' Shutdowr)' ri sc :A-4 . 0 O

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2 3's) 3, 4, 6 I,'. vi 9 3

r

~ c .- SL Wn~ ~ 6:/&fr A4~ ,C.. : ~- -

. 12, Reactor Protection System .

i .6 1 : ,- 6 1, 2

4

Logic Matrices 3. .

'13. Reactor Protection System 4/Hatrix 3/ Matrix 4/Hatrix 1, 2* 4 Logic Matrix Relays R

14. Reactor Trip Dreakers 8 6 0 1, 25' 4 8

t 0

. l-TABLE 3.3-1 (Continued) h ..

2"_. TABLE NOTATION _

I 1r With the protective. system trip breakers in the closed position and -!l the CEA drive system capable of CEA withdrawal. I f'

The provisions of Specification 3.0.4 are not applicable. ,

(a) Trip may be bypassed below 10-4 of RATED THERMAL POWER; bypass shall '

be automatically removed when THERMAL POWER is > 10' of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 685 psia; bypass shall .be -

automatically removed at or above 685 psia.

l (c) Trip may be b'ypassed'below 15% of RATED THERMAL POWER; bypass

! shall be automatically removed when THERMAL POWER is > 15% of'-

RATED THERMAL POWER.

(d) Trip may be bypassed below 10-4% and above 12% of RATED THERMAL l POWER. ,

_ (e) Trip may: be bypassed during testing pursuant to Special Test Excep-i.

EE

=-

tion 3.10.3. -

l (f). There shal;l be at least two decades of overlap between the Wide =

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~ Range Logarithmic Neutron Flux Monitoring Channels and the Power Range Neutron Flux Monitoring Channels. ;

ran N V:Je .6 - fuw (L wi s < 4 . // L a ,A ..:J s w:14 e ah,w y M s:H */er_f, ne suudoe d least M w:<..J-< LaGr 6 f:each is - 4:e.</ :, He en f of a. :., ,2 .,e f. 1 1 -.- w :...

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u ACTION STATEMENTS '

ACTh0N1 - With the' number of channels OPERABLE one less than required by the Minimum Channels OPERABLE recuirement,

! restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . For the purposes >

of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall '

then'be either restored to OPERABLE status or placed in

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the tripped condition. !

ess.

L, =

l 3/4 3-4 , Amendment No. 48 CALVERT CLIFFS - UNIT 1 I

l l

9 a.'4-nre Ga s ad !!tc 1c C- To-

1

,,,,,;,,,,, TABLE 3'.3-1 (Continued) .

,. ACTION STATEMENTS EE

~~

- s. .

~b. Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the .

inoperable channel.

- c. ( The Minimum Channels OPERABLE requirement is met;

_ however, one additional channel may be bypassed fer up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance

- . on that channel provided the other inoperable channei

[_ is placed in the tripped condition.

~

ACTION 3 - With the number' of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compli-

= - ance with the SHUTDOWN MARGIN requirements of Specification

- 3.1.1.1 or 3.1.1.2, as applicable, within I hour and a.t least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. :

With the number of channels OPERA 5LE one less than recuired ACTION 4 -

' by the Minimum Channels OPERABLE requirement, be in HOT

' STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be L'.

== . ;

== .

bypassed for up to I hour for surveillance testing per .

._ Specification 4.3.1.1. -

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Q 5~ CALVERT CLIFFS - UNIT 1 3/43-5 e- ,m ---

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II }i l! Wll' TABLE 4.3-1 (Continued)_

9 h REACTOR PROTECTIVE lilSTRUMENTATION SURVEILLANCE REf)UIREMENTS -

Fi .

c, I >- CllAllHEL H0 DES IN WillCil C CilANNEL . CllANNEL FUNCTIONAL SURVEILLAtlCE

j -

,CilECK CALIBRAT10H_ TEST REQUlitED

"' FUNCTIONAL UNIT . 1 i., a:..,,,,.,. ,

S R(5) S/U(1) 1, 2, 3, 4 -

Wide : Range Logaritimile Heistron:.. ;

'i' ' ..f t, -

E 11. . ,

F 5 and

A

Flux Honitor - ';, y, ,5: : ,

a Nb l- * .- t, r i. ' '# ,, . '

12.. Reactor Protection System H and S/U(1) - 1, 2 N.A. N.A.

Logic Hatrices .

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.13,' Reactor Protection System '. 1, 2 H.A. fl. A. H and S/U (1) 5: Logic Matrix Relays J... ,

H 1, 2 and

R 14. Reactor Trip ilreakers ;' ii; N.A. H.A. ..

ton ' e :e.

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TABLE 4.3-1.(Continued)

TABLE NOTATION L

With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(1) -

If not performed in previous 7 days.

t (2) -

Heat balance only, above 15% of RATED THERMAL POWER; adjust

" Nuclear Power Calibrate" potentiometers to make the nuclear

, power signals agree with calorimetric calculation if absolute difference is > 1.5%. During PHYSICS TESTS, these daily i calibrations of nuclear power and AT power may be suspended j provided these calibrations are perfonned upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

l (3) -

Above 15% of RATED THERMAL P0 ER, recalibrate the excore i detectors which monitor the AXIAL SHAPE INDEX by using the incore detectors or restrict THERMAL POWER during subsequent operations to < 90% of the maximum allowed THERMAL POWER level

_ with the existing Reactor Coolant Pump combination.

EEE E (4) -

Above 15% of RATED THERMAL POWER, adjust "aT Pwr Calibrate" -

potentiometers to null " Nuclear Pwr - AT Pwr". During PHYSICS TESTS, these daily calibratio'ns of nuclear power and aT power j may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to pro-

. ceeding to the next major test power plateau.

(5) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

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=-

G.

,CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No. 6

i 3.9.2 As a minimum, two source range neutron flux monitors shall be operating, each with continuous visual indication in the control room and one with audible indication in the containment and control room. At least two source range neutron flux monitors shall have alarms capable of alerting the coerator at least 30 minutes before criticality in the event of an inadvertant boron dilution.

APPLICABILITY: MODE 6.

l l

ACTION:

a. With less than 2 source range flux monitors operable, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

l

b. With less than two source range flux monitor alarm functions operable.

monitor RCS boron and/or at least two WRLC signals at a frequency such that the operator will be alerted at least 30 minutes before critiricality is reached in the event of an inadvertant boron dilution.

c. The provisions of Specification 3.0.3 are not applicable.

1

~

REFUELING OPERATIONS INSTRUMENTATION, .

~

LIMITING CONDITION FOR OPERATION <

x

1.9.2 minimum, two source range neutron flux monitors s e o perating, e with continuous visual indication in the room i.nd one with aud indication in the containment an trol room .

~

APPLICABILITY: MODE 6. -

ACTION:

. s ; ,- ;- -: - , ' :- .

k ith the requiremehts of above spec cation not satisfied, insnediately suspend operations involvin RE ALTERATIONS or ositive react y dhanges. The provisions of p ification

..0.3 are applicable. y ,

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SURVEIll.ANCE REQUIREMENTS

~

7_ _ , ._. .

4.9.2 Each source range neutron flux monitor shall be demonstrated OPERABLE by perfonnance of- -

a. A CHANNEL FUNCTIONAL TEST at least once per 7 days.

b. A CHANNEL FUNCTIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial

! start of CORE ALTERATIONS, and l

l c. A CHANNEL CHECX at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS.

l oL AJJada.6f s/ '~t%< abru setpi.J f. 's;z ree- A4 &* MedeW y+p.s a+ fou?~o~a )<.~ sv A, s.

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C; CALVERT CLIFFS - UNIT 1 3/4 9-2

- - _ . - , __ _ . .-

ML20003D524

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