ML20070M667

Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers

ML20070M667
Person / Time
Site:	Cooper
Issue date:	04/26/1994
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
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ML20070M663	List: ML20070M660 ML20070M667
References
NUDOCS 9405020374
Download: ML20070M667 (23)

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,

Attachment to NSD940428 APPENDIX B - MARKED-UP AFFECTED TECIINICAL-SPECIFICATION PAGES 9405020374 940426 PDR ADOCK 05000298 P

PDR

COOPER,

2AR STATION "P '[9<.f'/' k -

• ~

q

.w y4 e TABLE 3.2.F

== --

PRIMARY CONTAINMENT SURVEILIANC ATION %

All ' Y' Minimum Number Action Required When Instrument ofCoperable Minimum condition-Instrument I.D. No.

Range (Instrument ~ Channels Not Satisfied (1)

Reactor Vater Level NBI-LI-85A E-150)< to +604 i=W.~

2 A,B,C NBI-LI-85B

-150X to 460K /"6 Reactor Pressure RFC-PI-90A O y 1200 psig 2

A,B,C RFC-PI-90B X 1200 psig Drywell Pressure PC-PR-2A

-5 to 70 psig 2

A,B,C

[

PC-PR-2B

-5 to 70 psig

-PC-PR-1A 0 X 250 psig 2

F PC-PR-1B 0 f 250 psig Drywell Temperature PC-TR-50 50p)( 170*F 2

A,B,C A,B.C.D.E 50 ")( 350*F 2

A,B,C 44)X 300*F 4

Suppression Chamber / Torus PC-TR-21A 0 ( 400*F

.y

' Air Temperature PC-TR-23, Der 1 6 2 Suppression Chamber / Torus PC-TR-24, Det la to lh X 250*F 1 (2)

Note 2 Water Temperature PC-TR-25, Det 2a to 2h 0 )( 250*F Suppression Chamber / Torus 1-Water Level PC-LI-10 l-4X to +63) A f 2

A,B,C PC-LR-11 1-4X to +6M)t At PC-LI-12

-10k to +104 /m4e 2

A,B,C,E PC-LI-13

-10M to +1 @ /=6e PC-LR-1A 0 x 3'0GAv. -

2 F

PC-LR-1B 0 g 30'N h t Suppression Chamber / Torus PC-PR-20 0 g 2'psig-1 B,C Pressure g

Control Rod Position' N.A.

Indicating Lights 1

A,B,C,D h

< >t Neutron Monitoring N.A.

S.R.M.,

I.R.M.',

1 A,B,C,D v.-

LPax q:

af bi

& u4A s. m a.2.el #'M

• 0? n'~2 Wh,,=,?$$,?,"$Yhd k "!v& &~$ W hlC "

{

_,. _.. __ m.

Pc-,,,C m,m,

1=

2m 3, C y ;

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0 Various.

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STES FOR TABL.E 3.2.F-hMy ckeht.u d -f. u m ( AII W L o11owin5 actions.will be taken if the minimum number of operable instrument f

~1.

channels)asrequiredarenotavailable.pg hg.D 4.0 CAh

~

A.

From and after the da __ thac.one of these - parameters is reduced to one indication, continued 5perati.on31s permissible during the succeeding thirty days unless such(instrumTntaY1'o'n)is sooner made operable.

1 gcAcv.e. ton EQ.atcAts

~

B.

From and after the date t one of these parameters is not indicated in the control. room, continued {i6peration)is permissible du ing the succeeding seven days unless such @ enta_ti @ is sooner made perab C.

If the requirements of A and B above cannot be met, an orderly 6hutdow3r shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D.

These surveillance instruments are considered to be redundant to each other, 9

E.

In the event that both channels are inoperable and indication cannot be restored in six (6) hours. an orderlyQhutdown3 shall be initiated and the reactor shall be in Got Shutdog in six'(6) hours and in a'@oTd Shutdow]n condition in the following eighteen (18) hours.

F.

From and after the date that one of these parameters 'is reduced to one indication,.either restore the inoperabla component (s) to (operable) status within 30 days of the event, or prepare and submit a Special. Report to.the Commission outlining the action taken, the cause of the inoperability - and -

the plans and schedule for restoring the system to 6 parable?) status.

In the event that both channels are inoperable and indication cannot be restored in fourteen (14) days, an orderly shall be initiated.

2.

Each channel contains eight detectors.

.A channel is considered inoperable if two adjacent detectors are unmonitored by the. channel in question.

. E Act *8. foWE.O M C A h A.

From and after the. date ' that one channel becomes inoperable., continued c+ operatioib is permissible during the succeeding seven days unless sooner made B.

From and after the date that the second channel becomes inoperable, an l

orderly Q shall be initiated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless sooner. made M_

~

2A ve 3.

During periods when both. channe s are 1 operable, grab samples may.be taken to 4I"-

1 verify primary containment oxygen concentration.

1 Ma s' A kb We b b Webu Redt0A

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COOPER NUCLEAR STATION TABLE 3.2.H POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS

• All df'-

Miniinun Number of Action Required When Instrument Qerable_Instrumen" Camponent(0nerabt tty

~

Instrument ID Number Rance O'hannel s)

Is Not Assured Elevated Release Point (ERP)

RMP-RM-3B 1.00E-2 to 1 (Note 1)

A Monitor (High Range Noble l.00E+5 pc/cc Cas)

(Xe-133 Equivalent)

Turbine Building Ventilation RMV-RM-20B 1.00E-2 to 1 (Note 1)

A Exhaust Monitor 1.00Et5 pc/cc (Iligh Range Noble Gac)

(Xe-133 Equivalent)

Radwaste/ Augmented Radwaste RMV-RM-30B 1.00E-2 to 1 (Note 1)

A Exhaust Monitor 1.00E+5 pc/cc

-0 (liigh Range Noble Gas)

(Xe-133 I.

T Equivalent)

Primary Containment Gross RMA-RM-40A 1.0-1.0E+7 R/Hr.

2 (Note 1)

A Radiation Monitor RMA-RM-40B 0-1.0EF R Hr.

1-L Lee o,wi[4 Primary Containment "ydroge:'

PC-AN-il /0 I OI'to 30%

o - t o 7. -

2 (Notes 1 cr' 2)

B

{

~

2 2 Concentration Analyzer PC-AN-H /0 1I 0% to 30%

o t o y, 2 2 23 A^d h

MptA Crygts Other Post-Accident Monitoring Instrumentation is located in Table 3.2.F-Drywell' Pressure, PC-PR-1A and IB, Suppression Chamber / Torus Water Level PC-LR-1A and IB w

i e

w i

k a

4 y

- NOTES FOR TABLE 3,2.H G ridd ar_deO ~d. 4.r % (f l ( M 4f Action:

A.

With the number of W components less than - required by the minimum component (operabl3 requirements, initiate the proplanned alternate method of-monitoring D e appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,'and:

1)

Either restore the inoperable component (s) to status within 7 days of the event, or 2)

Prepare and submit a Special Report to the. Commission within 14 days.

following - the event outlining the action taken, the cause of the' paperability and the plans and schedule for restoring the system to status.

B.

The following actions will be taken if the minimum number of j

Qnstrument channels)as required are not(operablj; j >

1

~

1)

With the number of6perabld channels one less than the minimum' number of<l.

to (b6peITbTbj CoperabTD channels shown, restore the inoperable channel p

in at least g utdown within the next..[/

]

status within 30 days or be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

channelto(c 2)

With no dperablDchannels available, restore at least one O perab q status within 7 days or be in at least % o 3 within the: M

~

next I2 hours.

Notes:

[-

1.

These instruments _are_ required to beM at all times except when the-reactor is in (c.gld shutdo g or in the REFUEL mode during a Q eling outagg.

ct ndb; "e

-Q 2.

With two channels (operab@, the normal condition !c '!!th

 : =1 7

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3, ou,g g :o b w L,4 b,gt-.,3 p % J g e, c4%,,E ~ Arr A, ph.swrIn my L, W 6 verIC yetwy eenk,w.d oyy.

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-67b-0/22/02

COOPER EAR STATION PRIMARY CONTAINMENT URVEI

• ICE ENTAT Add

^

^

OS b N-TEST AND CALIBRATION FREQUENCIES Instrument Instrument I.D. No.

Calibration Frecuency Instrument Check Reactor Water Level NBI-LI-85A Once/6 Months-Each Shift NBI-LI-85B Once/6 Months Each Shift Reactor Pressure RFC-PI-90A Once/6 Months Each Shift RFC-PI-90B Once/6 Months Each Shift Drywell Pressure PC-PR-2A Once/6 Months Each Shift PC-PR-2B Once/6 Months Each Shift l'

PC-PR-1A Once/6 Months Each Shift PC-PR-1B Once/5 Months Each Shift Drywell Temperature PC-TR-5_03 Once/6 Months Each Shift Q S05 A.B.C.D.E ]-

Once/6 Months Each Shift h

Air Temperature Suppression Chamber / Torus' PC-TR-21A Once/6 Months Each Shift PC-TR-23, Det 1&2 Once/6 Months Each Shift Suppression Chamber / Torus PC-TR-24, Det la to lh once/6 Months Each Shift Water Temperature PC-TR-25,.Det 2a to 2h once/6 Months Each Shift Suppression Chamber / Torus PC-LI-10 Once/6 Months Each Shift Water Level PC-LR-ll Once/6 Months Each Shift PC-LI-12 Once/6 Months Each Shift PC-LI-13 Once/6 Months Each Shift PC-LR-1A Once/6 Months Each Shift PC-LR-1B Once/6 Months Each Shift Suppression Chamber / Torus PC-PR-20 /"###'

Once/6 Months Each Shift Pressure Y' I*E/* Y-E*//[

lt l.

wilt Control Rod Position N.A.

All 4 eleelA.

N.A.

Each Shift Neutron Monitoring (APRM)

N.A.

Once/ Week Each Shift-o lR

-~

~-

Priraary Containment Oxygen PC-AN/e3-H /02 AI Once/3 Months Once/ Day G

2 Concentration PC-ANfe9-H /0 -B-R once/3 Months once/ Day

}

2 2

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COOPER NUCLEAR STATION TABLE 4.2.11 CAllBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION

• Instrument Function Calibration U

Instrument ID Number Test Frecuency Frecuency Elevated Release Point (ERP)

Monitor (liigh Range Noble RMP-RM-3B Once/ Month once/ Cycle Cas)

Turbine Building Ventilation RMV-RM-20B Once/ Month once/ Cycle Exhaust Monitor (liigh Range Noble Cas)

Radwaste/ Augmented Radwaste RMV-RM-30B once/ Month once/ Cycle Exhaust Monitor (Iligh Range Noble Gas) h Primary Containment Gross RMA-RM-40A Once/ Month once/ Cycle d

T Radiation Monitors **

RMA-RM-40B onu /menefA Ou / c e /2 M

r Primary Containment I!yA ugs.

PC-AN-II/0 1 Once/ Month once/ Quarte p

2 2 O

Concentration @ alyzer w V PC-AN-ll /0 II

(" /

Om /SuAe 2 2 O'3 M Other Post-Accident Monitoring Instrumentation calibration requirements are in Table 4.2.F-Drywell Pressure.

PC-PR-1A and IB, Suppression Chamber / Torus Water Level PC-LR-1A and IB.

V I e k.

'^ f

.m m,-

mm.. m _ m

~

"CilAN!iEl CIA'LIBRATION 'shall consist of an electronic calibfation of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below g

10 R/hr with an installed or portable gamma source.

O' 3

Y

wggb 43I2.~ BASES (Cont'd):

~ ~ ~

.. - - -.... -.,.. ~ -

-. ~ ~.

F.

Primary-Containment Surveillance Information For each parameter monitored, as listed in Table 3.2.F. there are two (2) channels of Qnstrumentation} By comparing; readings between the two (2) channels, a near continuous surveillance of. instrument performance is available..

Any deviation in readings will initiate an early recalibration,. there-i by. maintaining the quality of the instrument readings.

The operability of the reactor water level instrumentation in Tables 3/4.2.F ensures that' sufficient information is available to monitor'and assess accident-

j situations.

G.

-Recirculation Pump Trip j

The recirculation pump trip has been.added as a means of limiting the con-sequences of-the unlikely occurrence of a failure to scram during an-antici--

pated transient. The response of.the plant to this postulated event' falls-within the envelope of study events given in General Electric Company Topical Report..NEDO-10349, dated. March, 1971.

H.

Post-Accident Monitoring i

The post-accident monitoring h umentation] supplements existing dnatru- )

that was designed to monitor primarily the normal operational.

t ranges of these parameters. Post-accident monitoringCins_trumentatiog

~

provides information for the ranges that may exist dur1ng the extreme conditions postulated'to occur during jand af ter some accidents.

g U" Y k y g m [ P s y.n.

1.

Alternate' Shutdown Capability p

j v

The purpose of the Alternate Shutdown System is to provide the. capability'to. shut i

down the plant in the unlikely event of a fire which disables the' controis and j

C1nstrumentatioirynecessary'to shut down the plant from the' control room.- As..

( g, documentiid in the CNS Response co.10CFR50, Appendix R,f " Fire Protection' of. Safe,

r Shutdown Capability," Volume III, there are five-areas of the plant that-

_ p' necessitate altcrnate shutdown capability in accordance with Section III.G.3 of Appendix R.

Those areas'are:

the control room, the cable' spreading room, the'

[

cable expansion room, the auxiliary relay room and the northeast corner of the-Reactor. Building 903' elevation..

l The Alternate Shutdown (ASD) System provides a means of controlling'the High

]

Pressure Coolant Injection (HPCI), Automatic Depressurization' (ADS), Residual Heat -

l',

+

Removal (RHR) Torus Cooling, and _ Reactor Equipment Cooling Systems ' independent of ?

),

the five plant areas requiring alternate shutdown...Using'the alternate shutdown" z

+

system, the plant can be cooled down and depressurized' independent ofJa fire in'any. Ll

~

,of the five plant areas necessitating ASD capability.

h l

i REFERENCES

'C' Ib~;

1.

" Low-Low Set Relief Logic System and Lower MSIV Water Level Trip for Cooper Nuclear Station", NEDE 22197, December 1982, General Electric Company.

c t

.87a-

r New Paragraph for BASES, 3.2.H-The' Primary Containment

' Hydrogen / Oxygen Concentration--

Analyzers are utilized to monitor primary containment hydrogen and oxygen concentrations during both normal plant operations

.and post-accident.

By. allowing the utilization of this.-

INSTRUMENTATION

'o n an intermittent -basis during normal operations, the applicable surveillance requirements.for checking hydrogen and oxygen 'are satisfied while ensuring the availability of the INSTRUMENTATION for continuous monitoring. ((.

post-accident.

Intermittent sampling

'of hydrogen i

I j concentrations during normal plant operations is permitted by NUREG-0737, Item II.F.1.6.

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LIMITING CONDITIONS FOR OPERATION.

SURVEILLANCE REQUIREMENTS 4.7 A.4 (cont'd.)

- p-

-3.7.A.4 (cont'd.)

.c.

The total leakage between the dry-

"U "E cyc h each vacuum "C"

breaker valve shall-be visually'in-well and suppression chamber shall j

be less than the equivalent leakage 4 SPected to insure proper maintenance nd. operation of the position indication through a l di, eter orffice.

switch.

The differential pressure set-c point shall be verified.

d.

Priortoleactorstartup)aftereach d.

Ifspecifications3.7.A.4.a.b,>rcg refueling, a leak test of the drywell.

cannot be met, the situation siall t Suppression chamber structure be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the shall be conducted to demonstrate reactor will be placed in a e 1d that the requirement of 3.7.A.4.c Cyghqtdowri conditio37within the sub-is met.

seqiient 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

M ()

C.

5.

Oxygen Concentration

5..

Oxygen concentration a.

The p " r m e h r oxygen con-a.

After completion of the startup test centration shall be measured and E)K.Tc A program and demonstration of plant Ar~~N recorded at least twice weekly.

V fD EL-electrical output, the p._,

s m.

.FW@

ntmosphere shall be reduced gg gg

'=*

to less than_4% oxygen with nitrogen dh)Wfb

. N'"##"

ring 6eactor power opera on with.:::: :

-'--[- -.: above sspyr.ustw Cksome k.

==

^ 1 ^-

100 psig, except as specificd in 3.7.A.5.b.

Ap cy, b.

The quantity of' liquid nitrogen in b.

Within the 24-hour period subsequent the liquid' nitrogen storage tank shall to placing the reactor in the Run ode.

be determined twico per week when the following aghutdowi), the cc.tc;r ;.c.-t l

v lume requirements of 3.7.A.S.c are atmosphere oxygen Eoncentration shall f

g ($

be reduced to less than 4% by volume in effect.

and maintained in this condition.

L De-inerting ym,mence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to aTahutdown) l c.

When the i.tn.,-..;

atmosphere oxygen l

concentration is required to be less than 4%, the minimum quantity of. liquid nitrogen in the liquid nitrogen storage tank shall be 500 gallons.

d.

If +h+--specifications - J 3.7. A.5.a.

c cannot be met, an orderly shutdown g

shall be initiated and the reactor shall be in a6Bd shutdown condition) within.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Me m_ _

x.

--_m s.,.m.s.m are a plicabic dur m-hv r dontinuous ietween the dates of

. :, ' ^ 2 n /. ;w a, u u...

.) s. _

_ /27/22

.164 ~.

o

_l

c3 or ca de h.

e M

b 3.7.A & 4.7.A BASES (ce it' d) bhprimarycontainment is normally slightly pressurized during periods of actor hPOWE( operatiod Nitrogen used for inerting could leak out of the containment but air

~

could not leak in to increase oxygen concentration.

1..

da : ntri=:nt i; fill:d W

.ng:- :: S: wi :?

_. u m..n i.. -d;d

-r-rm M-least twice _ a weekJ-tMoxygen concentration v111 tm y o% gen eow.ledh mi.14,ug luirm.Med, determined 2: MN

=

p,M@ gua,

ee M.,, "Th 3. 2. H -

/

The 500 gallon conservative lim t on tne nicrogen stora5e cans assures tnac-acequate time is available to get the tank refilled assuming normal plant operation.

The estimated maximum makeup rate is 1500 SCFD which would require about 160 gallons for a 10 day makeup requirement. The normal leak rate should be about 200 SCFD.

3.7.A.6 & 4.7.A.6 LOW-LOW SET RELIEF FUNCTION The low-low set relief logic is an automatic safety relief valve (SRV) control system designed to mitigate the postulated thrust load concern of subsequent actuations of during certain transients (such as inadvertent MSIV closure) and small and n

in ermediate break loss of-coolant accident (LOCA) events.

The setpoints used in Section 3.7.A.6.b are based upon a minimum blowdown range to provide adequate time between valve actuations to allow the SRV discharge line high water leg to clear,

__::=

1.-

coupled with consideration of instrument inaccuracy and the C

.wab e isolation setpoint.

The as-found setpoint for NBI-PS-51A, the pressure switch controlling the opening of RV-71D, must be 6 1040 psig.

The as-found closing setpoint for NBI-PS-51B must be at least 90 psig less than 51A, and must be 2 850 psig.

The as-found setpoint for NBI-PS-51C, pressure switch controlling the opening of RV-71F must be s 1050 psig.

The as-found closing setpoint for NBI-PS-51D must be at least 90 psig below Sic, and must be 2 850 psig.

This ensures that the analytical upper limit for the opening setpoint (1050 psig), the analytical lower limit on the closing setpoint (850 psig) and the analytical limit on the blowdown range (2 90 psig) for the Low Low Set Relief '

Function are not exceeded. Although the specified instrument setpoint tolerance 'is i 20 psig, an instrument drift of i 25 psig was used in the analysis to ensure set oints..The opening-adequate margin in determining the valve opening and closin netpoint is set such that, if both the lowest set non-LLS and the hi est'sec the LLS R-will of the two LLS @ drif t 25 psig in the worst case direct ons, still control suose Likewise, the closing setpoint is set to ensure the LLS @ quent @ actuations. closing setpoint remains above the MSIV 90 psig blowdown provides adequate energy Aase from the vessel to ensure time for-r the water leg to clear between subsequent (S/RV)actuations.

3.7.B & 3.7.C STANDBY GAS TREATMENT SYSTEM AND SECONDARY CONTAINMENTfpowC_QAu cy, y

v The secondary containment is desi ned to minimize any/fround level release of k[ building provides Caicondary containment adioactive ciate rials which migncve it from _a sergus accident.

The reactor uring(reactor'bveratTonlwhen the drywell is sealed and in service.

The reactor building provides(primary containmentlvhen the

_ reactor _ ir/Thutvdown]and the drywell is open, as during refueling.~ Because the-]

sellO#U secondary 'containmeTnt is an integral part of the complete containment s ys tem,-

Qg_nniury conta2nmentJis required at all times thacGirimary containment]is required as durin5 and during movement of Ioads which could potentially 7 irradiated /[hfSlinG'.

46 s well uel in the secondary containment. Gecondary containment?may 'e.

_u o

pu c s damage roken for short periods of time to allow access to the reactor _ building roof to

[performnecessaryinspectionsandmaintenance.

/ 7M E G E 7P1 4ficAf, s

3 Rggemiol The Standby cas Treatment System consists of two, distinct subsystems, each W6E containing one exhaust fan and associated filter train, which is designed 'to filter and-exhaust the reactor building atmosphere to the stack during secondary containment isolation conditions.

Both Standby Gas Treatment System fans are designed to l automatically start upon containment isolation nd to maintain the reactor-building pressure to the design 4gative pressure so t t all leakage should be in leakage.

Should one subsystem f 1 to start, the redun nt subsystem is designed to start l putnmntically.

Each o the two fans has 100 pe ent capacity.

Se*f N

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Attachment to NSD940428 APPENDIX C - REVISED AFFECTED TEC11NICAL SPECIFICATION PAGES j

i

+

v.

COOPER NUCLEAR STATION TABLE 3.2.F PRIMARY CONTAINMENT SURVEILIANCE INSTRUMENTATION

• J_

Minimum Number Action Required '

of OPERABLE When Minimum Instrument INSTRUMENT Condition Instrument I.D.

No.

Rante CHANNELS Not Satisfied (1)

Reactor Water Level-NBI-LI-85A

-150 to +60 inches 2

A,B,C 1:01-LI-85B

-150 to +60 inches Reactor Pressure RFC-PI-90A 0 to 1200 psig 2

A,B,C RFC-Pi-90B 0 to 1200 psig Drywell Pressure PC-PR-2A

-5 to 70 psig 2

A,B,C PC-PR-2B

-5 to 70 psig PC-PR-1A 0 to 250 psig 2

F PC-PR-1B 0 to 250 psig 2

Drywell Temperature PC-TR-503 50 to 170*F 2

A,B,C PC-TI-505 A,B,C,D,E 50 to 350*F Suppression Chamber / Torus PC-TR-21A 0 to 300*F 2

A,B,C T

Air Temperature PC-TR-23, Det 1&2 0 to 400*F Suppression Chamber / Torus PC-TR-24, Det la to lh 0 to 250*F 1 (2)

Note 2 Water Temperature

. PC-TR-25, Det 2a to 2h 0-to 250*F Suppression Chamber / Torus Water Level PC-LI-10

-4 to +6 feet 2

A,B,C PC-LR-ll

.-4 to +6 feet a

PC-LI-12

-10 to +10 inches 2

A,B,C,E PC-LI-13

-10 to +10 inches y

PC-LR-1A 0 to 30 feet.

.2 F

PC-IR-1B 0 to 30 feet f

Suppression Chamber / Torus' PC-PR-20 0.to 2 psig 1

B,C Pressure Control-Rod Position-N.A.

Indicating Lights 1

A,B,C,D

!i' Neutron Monitoring.

N.A.

S.R.M.,

I.R.M.,

.1 A,B,C,D

~

LPRM 0 to 100% power i

Notes:

• Other' Primary Containment Surveillance Instrumentation is located in Table 3.2,H-Primary Containment Hydrogen /0xygen-Analyzer w

tn Y

~

v w

w

+

l w.

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.2 NOTES FOR TABLE 3,2.F minimumnumberofOPERABLEINSTRUMENT[

1.

The following - actions will be taken if the CHANNELS as required are not available.

A.

From and after the ~date that one of these parameters is reduced to - one. l indication, continued REACTOR POWER OPERATION is permissible during

the, succeeding thirty days unless such INSTRUMENTATION is sooner made OPERABLE.

. l --

B.

From and after the date that one of these parameters is not indicated in the control room, continued REACTOR ' POWER OPERATION is permissible during - the.' !

succeeding seven days unless such INSTRUMENTATION is. sooner made OPERABLE.

l-C.

If the requirements of A and B above cannot be me t,- an orderly f SHUTDOWN l' shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D.

These surveillance' instruments are considered to be redundant to each other.

E.

In the event that both channels are inoperable and indication cannot = be restored in six (6) hours, an orderly SLUTDOWN ~ shall' be initiated.' and the j.

reactor shall~be in HOT SHUTDOWN in six (6) hours and in a COLD SHUTDOWN; [

condition in the following eighteen (18) hours.

7 F.

From and after the date that one of these parameters is reduced. to one.

l indication, either - restore the inoperable component (s) to OPERABLE status within 30 days of the event, or prepare and submit a Special Report ; to ' the -

Commission outlining the action taken, the cause of - the.noper bility and the plans and schedule for restoring the system to OPERABLE'_ status. ' In the l-event that both channels are inoperable and indication cannot be-restored in fourteen (14) days, an orderly SHUTDOWN shall be' initiated.-

l-2.

Each channel contains eight detectors.

A channel-is considered' inoperable if two:

adj acent detectors. are unmonitored by the channel in question.

A.

From-and after the date that one channel becomes inoperable,. continued --

REACTOR POWER OPERATION is permissible during the succeeding seven idays -l unless sooner made OPERABLE.

B.

From and after the date that the second channel becomes inoperable, an-orderly SHUTDOWN shall be initiated within ' 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless : sooner made-l-OPERABLE.

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'c TABLE 3.2.H

]

POST-ACCIDENT MONITORING INSTRUMENTATION REQUIREMENTS

• Minimum Number of Action Required When-._

Instrument OPERABLE INSTRUMENT Component OPERABILITY-l.

Instrument

-ID Number Rance CHANNELS Is Not Assured l

Elevated Release Point-(ERP).

RMP-RM-3B 1.00E-2 to 1 (Note 1)

-A Monitor (High Range Noble 1.00E+5 pc/cc Gas)-

(Xe-133 Equivalent)

Turbine Building Ventilation RMV-RM-20B 1.00E-2 to 1 (Note 1)

.A Exhaust Monitor 1.00E+5 g/cc (High Range No.319 Cas).

(Xe-133 A

. Equivalent)

Radwaste/ Augmented Radwaste RMV-BM-30B 1.00E-2 to 1 (Note 1)

A Exhaust Monitor 1.00E+5 pc/cc (High Range NobleLGas)

(Xe-133

?

Equivalent)

Primary Containment Gross RMA-RM-40A 1.0-1,0E+7 R/Hr.

2 (Note 1)

A Radiation Monitor RMA-RM-40B 1.0-1.0E+7 R/Hr.

-Hydronen

'Oxycen J.

' Primary Containment <

- PC-AN -H /0 1 0% to 30%

0 to 10%

2 (Notes 1, 2, and 3) B 2 2

-)

. Hydrogen /0xygen Concentration Analy=er PC-AN-H /0 II -

0% to 30%

0 to 30%

2 2 Notes: ~*. Other Post-Accident Monitoring Instrumentation is located in Table 3.2.F-

-l -

'Drywell-Pressure, PC-PR-1A and lB, Suppression Chamber / Torus Water Level PC-LR-1A and.13 L

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NOTES FOR' TABLE ~3.2.H

'j

' Action:

A.

With the number of OPERABLE compdt$ent a less - than required by the. minimum l-component OPERABLE cequirements, initiate the preplanned' alternate method. of. l l

monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:

1)

Either restore the inoperable component (s) to OPERABLE status within1j.

7 days of the event, or 2)

Prepare and submit a Special Report to the Commission within 14'. days following the event outlining the action taken, the cause.' of the inoperability and the plans and schedule for restoring. the system to OPERABLE status.

.l.

B.

The following actions will be taken' if the minimum number of OPERABLE INSTRUMENT CHANNELS as required are not OPERABLE:

1)

With the number of OPERABLE channels one less than the minimum number !-

of OPERABLE channels shown, restore the inoperable channel to OPERABLE I I

status within 30 days or be in at least HOTSHUTDOWNwithinthenext~[

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3 2)

With no OPERABLE channels available, restore at least one channel to-l

~

OPERABLE status within 7 days or be in at least ' HOT SHUTDOWN within - l-the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'l Notes:

1.

These instruments are required to be OPERABIE ~ at all times except when.the 'l1 reactor is in COLD SHUTDOWN or in the REFUEL mode during a~ REFUELING OUTAGE,

l 2.

With two channels OPERABLE, the normal condition may include ' sampling intermittently.

3.

During periods when both oxygen analyzer ' channels are_ inoperable,. grab-[

samples may be taken to verify primary containment oxygen concentration.

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COOPER NUCLEAR STATION TABLE 4.2.F PRIMARY CONTAINMENT SURVEILLANCE INSTRUMENTATION *'

=f. "

TEST AND CALIBRATION FREQUENCIES Instrume-Instrument I.D. No.

Calibration Frequency Instrument Check Reactor Water Level NBI-LI-85A

.Once/6 Months Each Shift NBI-LI-85B Once/6 Months Eacit Shift Reactor Pressure RFC-PI-90A Once/6 Months Each Shift RFC-PI-90B Once/6 Months Each Shift Drywell Pressure PC-PR-2A Once/6 Months Each Shift PC-PR-2B Once/6 Months Each Shift PC-PR-1A Once/6 Months Each Shift PC-PR-1B Once/6 Months Each Shift Drywell Temperature PC-TR-503 Once/6 Months Each Shift.

PC-TI-505 A,B,C,D,E Once/6 Months Each Shift l'

- 'h Suppression Chamber / Torus PC-TR-21A Once/6 Months Each Shift Air Temperature PC-TR-23, Det 1 & 2 Once/6 Months Each Shift

' Suppression Chamber / Torus PC-TR-24, Det la to lh once/6 Months Each Shift Vater Temperature PC-TR-25, Det 2a to 2h Once/6 Months Each Shift Suppression Chamber / Torus

'PC-LI-10 Once/6 Months Each Shift 4

i Water Level PC-LR-ll Once/6 Months Each Shift L

PC-LI-12 Once/6 Months Each Shift PC-LI-13 Once/6 Months Each Shift PC-LR-1A Once/6 Months Each Shift g

L PC-LR-1B Once/6 Months Each Shift

]

Suppression Chamber / Torus PC-PR-20 Once/6 Months Each Shift li Pressure b

J Control Rod Position N.A.

N.A.

Each Shift Neutron Monitoring (APRM)

N.A.

Once/ Week Each Shift-

[

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' Notes: *- Other Primary Containment Surveill'nce' Instrumentation calibration-requirements'are in.

a

= Table 4.2.H A Primary.. Containment Hydrogen / Oxygen Concentration-Analyzer.

F L

COOPER NUCLEAR STATION TABLE 4.2,H-CALIBRATION FREQUENCY FOR POST-ACCIDENT MONITORING INSTRUMENTATION

• Instrument Function Calibration Instrument ID Number Test Frecuency Frecuency Elevated Release Point (ERP)

Mcnitor (High Range Noble RMP-RM-3B once/ Month once/ Cycle Gas)

Turbine Building Ventilation RMV-RM-20B Once/ Month once/ Cycle Exhaust Monitor-

.(High Range' Noble Cas)

Radwaste/ Augmented Radwaste RMV-RM-30B Once/ Month once/ Cycle Exhaust Monitor-

{

(High Range Noble Gas)

Primary Containment Cross RMA-RM-40A Once/ Month Once/ Cycle

. 4 Radiation Monitors **

RMA-RM-40B Once/ Month once/ Cycle Y

4 Primary Containment PC-AN-H /0 I Once/ Month once/ Quarter 2 2 Hydrogen / Oxygen PC-AN-H /0 II Once/ Month once/ Quarter 2 2 Concentration Analyzer ***

7 5.'

Notes:

Other Post-Accident' Monitoring Instrumentation calibration. requirements are in Table 4.2.F-Drywell Pressure. PC-PR-1A and 1B, Suppression Chamber / Torus Water Level PC-LR-1A and IB.

C11ANNEL CALIBRATION shall consist of an electronic. calibration of the. channel, not including the detector, for range. decades above 10 R/hr and a one point calibration check of the detector below

.'10 R/hr.with an installed.or portable gamma. source.

Instrument check required once/ day.for the oxygen portion of the inservice analyzer.

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t 3.2 PASES (Cont'd)

F.

Primary Containment Surveillance Information For each parameter monitored, as listed'in Table 3.2.F. there are two (2) channels of INSTRUMENTATION.

By comparing readings oetween: the two - (2) 4hannels, a near 'l -

continuous surveillance of instrument performance is available.. Any deviation in readings will initiate an early recalibration, thereby maintaining the quality'ofL the instrument readings.

The operability of the reactor water level INSTRUMENTATION in Tables 3/4. 2.F ' l '

ensures that sufficient information is available ' to monitor and assess = accident situations.

G.

Recirculation Pumn Trin

^

The recirculation pump trip has been added as a means of limiting the consequences.

of the unlikely occurrence of a failure to scram during an anticipated' transient.

The response of the plant to this postulated event falls within the envelope.of study events given in General Electric Company Topical Report, 'NEDO-10349, dated March, 1971.

H.

Post-Accident Monitoriny The post-accident monitoring INSTRUMENTATION supplements existing INSTRUMENTATION-l' that was designed to monitor primarily the normal operational ranges of. these parameters.

Post-accident monitoring INSTRUMENTATION provides information for the. l i;

ranges that may exist during the extreme conditions postulated to occur during.and-after some accidents.

- r The Primary containment Hydrogen /0xygen Concentration Analyzers are utilized to monitor primary containment hydrogen and oxygen concentrations during both normal plant operations and post accident.

By allowing the utilization.of this INSTRUMENTATION on an intermittent basis during normal operations, the-applicable-survaillance requirements for checking hydrogen and oxygen are satisfied, while ;

ensuring the availability of. the INSTRUMENTATION for continuous monitoring post-accident.

Intermittent sampling of hydrogen concentrations. during. n'ormal:

pl.mt operations is permitted by NUREG-0737 Item II.F.1.6.

1

$lternate Shutdown Canability The pu pose of the Alternate Shutdown System is to provide.the capability to ' shut down the plant in.the unlikely event of a' fire which disables the. controls) and INSTRUMENTATION - necessary to shut. down the plant from the e control ' room.

As l documented in the CNS Response to 10CFR50, Appendix R," Fire Protection of Safe Shutdown Capability,"' Volume III, there are five areas - of. the plant that necessitate alternate shutdown capability in accordance with 'Section III.G.3 of Appendix R.

Those areas -are:

.the control room, the cable spreading room,. the cable expansion room, the auxiliary relay room and 'the - northeast corner of the-it Reactor Building'903' elevation.

of controlling the High The Alternate Shutdown (ASD) System - provides a means Pressure Coolant Injection (HPCI), Automatic Depressurization (ADS). Residual Heat :

Removal (RHR) Torus Cooling, and Reactor Equipment Cooling Systems independent of the five plant. areas requiring alternate shutdown.

Using the alternate shutdown system, the plant can be cooled down and depressurized independent 'of a fire ;in any of the five plant areas necessitating ASD capability.

REFERENCES 1.

" Low-~ Low Set Relief Logic System and Lower MSIV Water Level Trip for - Cooper

'j Nuclear Station", NEDE 22197,. December 1982, General Electric Company.

l 1

-87a-J'J L

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9 LTMTTTMC rnNDTTinNS FnR OPFRATinN CUPVFTT.TANrF PFnnTPFMENTS 3,7.A 4 (cont'd.)

4.7 A.4 (cont'd.)

c.

The total leakage between the c.

Once each OPERATINC-CYCLE, each l drywell and suppression chamber vacuum breaker valve shall be shall be less than the equivalent visually inspected to insure l

1eakage through a 1 inch diameter proper maintenance and operation orifice.

of the position indication switch.

The differential pressure setpoint shall be verified.

d.

If specifications 3.7.A.4.a, b,

or d.

Prior to REACTOR STARTUP after.l c cannot be

met, the situation each refueling, a leak test.of the shall be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> drywell to suppression chamber or the reactor will be placed in a structure shall be conducted to l

COLD SHUTDOWN CONDITION within the demonstrate that the requirement subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

of 3.7.A.4.c is met.

S.

Oxymn Concentration 5.

Oxyren Concentration a.

After completion of the startup a.

The drywell and pressure test program and demonstration of suppression chamber.

oxygen plant electrical

output, the concentration shall-be measured drywell and pressure suppression and recorded at least twice l

weekly.

chamber atmosphere shall be reduced to less than 4% oxygen,

with nitrogen gas during REACTOR POWER OPERATION with REACTOR VESSEL PRESSURE above 100 psig, except as specified in 3.7.A.S.b.

b.

Within the 24-hour period b.

The quantity of liquid nitrogen in subsequent to placing the reactor the liquid nitrogen storage tank a

shall be determined twice per week in the RUN mode following SHUTDOWN, the drywell and pressure when the volume requirements of suppression chamber atmosphere 3.7.A.5.c are in effect.

oxygen concentration shall be reduced to less than 4% by volume and maintained in this condition.

De-inerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

prior to a SHUTDOWN.

c.

When the drywell and pressure suppression chamber atmosphere oxygen. concentration is required to be less than 4%,

the minimum quantity of liquid nitrogen in the liquid nitrogen storage tank shall be 500 gallons, d,

_f specifications 3.7.A.S.a, b, or c

cannot be

met, an orderly SHUTDOWN shall be initiated and the reactor shall be in a COLD SHUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

-164-

__x. a

1, 3.7.A & 4.7.A BASES (cont'd)

-The primary containment is normally slightly pressurized during periods of REACTOR POWER OPERATION.

Nitrogen used for inerting could leak out of the containment but air could not leak in to -increase oxygen concentration.

Primary containment oxygen concentration will'be determined at least twice a week. Specifications for oxygen concentration monitoring instrumentation are located -in Table 3.2.11.

The 500 gallon conservative limit on the nitrogen storage tank assures that adequate time is available to get the tank refilled assuming normalE plant operation.

The estimated maximum makeup rate' is 1500 SCFD which would require about 160 gallons for a 10 day makeup requirement. 'The normal leak rate should be about 200 SCFD 3.7.A.6 & 4.7 A.6 LOW-LOW SET RELIEF FUNCTION The low-low set relief logic is an automatic safety relief valve. (SRV) control.

system designed to mitigate the postulated thrust load concern of L subsequent The-l-actuations of SRVs during certain transients (such as inadvertent MSIV clorure) and small and intermediate break loss-of-coolant accident (LOCA) events.

setpoints used in Section 3.7. A.6.b are based upon a minimum blowdown range to provide adequate time between valve actuations to allow the SRV discharge line i

high water leg to clear, coupled with consideration of instrument inaccuracy and the MSIV isolation setpoint.

ll The as-found setpoint for NBI-PS-51A, the pressure switch controlling the opening of RV-71D, must be s 1040 psig.

The as-found closing setpoint for NBI-PS-51B must be at least 90 psig less than 51A, and must be 2 850 psig.

The as-found setpoint for NBI-PS-51C, pressure switch controlling the opening of.RV-71F must. be 5 1050 psig.

The as-found closing setpoint for NBI-PS 51D must be at: least 90 psig below Slc, and must be 2 850 psig.

This ensures that the analytical upper-limit for the opening setpoint (1050 psig), the analytical. lower limit on the closing setpoint (850 psig) and the analytical limit on the~ blowdown range _ (2 90 psig) for the Low-Low Set Relief Function are not exceeded.

Although - the specified instrument setpoint tolerance is i 20 psig, an instrument drift of.i.

25 psig was used in the analysis to ensure adequate margin in determining the valve opening and closing setpoints.

The-opening setpoint is set such that, if '

both the lowest set non-LLS SRV and the highest set of. the two LLS SRVs drift.

25 psig in the worst case directions, the LLS SRVs will still control subsequent SRV actuations.

Likewise, the closing setpoint is set to ensure the LLS: SRV closing setpoint remains above the MSIV low pressure trip.

The 90 psig blowdown provides-adequate energy release from the vessel to ensure time for the water' leg to clear between subsequent SRV actuations.

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3.7.B 6 3.7.C STANDBY CAS TREATMENT SYSTEM AND SECONDARY CONTAINME3T The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident.

The reactor building provides SECONDARY CONTAINMENT INTEGRITY during REACTOR POWER OPERATION 1

when the drywell is-sealed and in service.

The reactor building provides PRIMARY CONTAINMENT INTEGRITY when the reactor is SHUTDOWN and _ the drywell is open, as -

during a REFUELING OUTAGE.

Because the secondary containment is an integral part of the complete containment system, SECONDARY CONTAINMENT INTEGRITY is required at all times that PRIMARY CONTAINMENT INTEGRITY is required as well as during refueling, and during movement of loads which could potentially damage irradiated-fuel in the secondary containment.

SECONDARY CONTAINMENT INTEGRITY may be broken l for short periods of time to allow access to the reactor building roof to perform necessary inspections and maintenance.

The Standby Gas Treatment System consists of two, distinct subsystems, each containing one exhaust fan and associated filter train, which is designed to-filter and exhaust the reactor building atmosphere to the stack during secondary containment isolation conditions.

Both Standby Gas Treatment System fans are designed to automatically start upon a Group 6 containment isolation signal and to l

maintain the reactor building pressure to the design negative pressure so that all.

leakage should be in-leakage.

Should one subsystem fail to start, the redundant subsystem is designed to start automatically.

Each of the two fans has 100 percent capacity.

!1 4

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