ML20091L772

Proposed Tech Specs Re Hpic & RCIC Sys

ML20091L772
Person / Time
Site:	Quad Cities
Issue date:	01/21/1992
From:	COMMONWEALTH EDISON CO.
To:
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ML20091L761	List: ML20091L756 ML20091L772
References
NUDOCS 9201280222
Download: ML20091L772 (9)

Text

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ATTACllMENT 3 IMRKED_VE_PAGES f_0R PROPOSED _ CHANGES _10_ APPENDIX _A IECilNICAL SPEclEICATIONS _0E EACI LIILOP ERAT I NG _ LICENSES. DPR:29_ e nd _DPR:30 OVAD.CIIIES_SIATION DER 29 DPJ1:30 3.5/4.5-5 3.5/4.5-4a 3.5/4.5 7 3.5/4.5-6

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4. Containment cooling spray. loops. 4. During each 5 year period, an- b are required to be operable when air test shall be i Lthe

reactor, water temperature is the drywell spray:headers performed and on greater than 212*F and. 1 n reactor _startup from a cold prior-to- nozzles and a water spray test con- performed on the torus spray

~. dition.4 Continued reactor oper . header and nozzles.  :

ation"is: permitted provided that 'I

=

a saximum of one drywell spray '

loop may be inoperable for 30

days when-the reactor. water tem-perature is greater than 212'F.; l y

S 5.' Ifxthe" requirements of 3.5.B

, s- cannot be met. an orderly shut- ' ';

down'shall be initiated.:and the <

' reactor shall be in a cold shut-down condition within 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br />.

/

C. :HPCI Subsystem-

• C. HPCI Subsysten

1. ?The HPCI subsystem shall be- t

= operable whenever the-reactor Surveillance of.HPCI subsystem shall j

be performed as specified below with-pressure is: greater than:150- .the following limitations. .For item psig and fuel is in the -4.5.C 3, the plant is; allowed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; 1

-reactor vessel'.c in which to:successfully complete the -

,- -test once reactor vessel: pressure is 7 2.; iDuring_startup following=a1 refuel _

= yL adequate to perfore each test. .In- ,

outagefor anioutagecin which work . . addition,:the testing required by ites

". > :was. performed that-directly .affacts '4.5.C.3,aishall.be completed prior to  :

HPCI systes: operability,~if the -

exceeding 325 psig reactor vessel v testing requirements of 4.5.C. 1 : - pressure. : If HPCI is made. inoperable

-cannot-be. net. continued reac to perform overspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

.startup:is:not' permitted.EThe is allowed to complete the tests-before

HPCI-subsystem shall be: declared- exceeding 325 psig.

1 m -inoperable,:and the-provisions'of -

.1

~

<Epocification 3.5.C.4'shall be- Itent Frecuencyl Lieplemented.?

. , - 1. Valve Position- Every 31= days -

Except for the : limitations'of

3. :.

• 3.5.C.2, ifJthe: HPCI subsystem T 2. Flow Rate Test-Every 92 days' .

tis:made or:foundito be inoperable, -HPCI Puer shall.

m' ' continued reactor operation is deliver as least 4

persissible'only.during the suc - 5000 gpa against

..ceeding 141 days unless such sub- I a system head:cor- '

xsystes is sooner made:. operable,- -

responding to a provided that during.such 14 days" \ reactor vessel 1the automatic pressure relief: . _ pressure of >_ 1150 1

__subsystemsi the core spray sub- psig when-steam-is -

u 1 systems LPCI mode of.the:RHR. being' supplied to-

. system,,and the-RCIC system are -

the turbine at 920 i' operable.f Otherwise, the pro- to 1005'psig.

- z visions 'of specification;3.5.C;4 *

[ ;shall-beiimplemented.

• L L3.5/4.5-5 AmendmentNo.)86 L- .

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QUAD-CITIES  !

-OPR-29 ,

a when the reactor-is-pressurized' i

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iabove 90 psig with_ irradiated-

-fuel in the: reactor vessel, -

a' reactor, operation is-permissible Lonly during the succeeding 7 days

~

~ unless' repairs are made and- -

~ provided_that during such time the HPCI-subsystem is operable. ~'

3.

-If the requirements _of Specifi- 3. A simulated automatic initiation i cation 3.5.D cannot be met',_an which. opens all pilot valves i

orderly shutdown shall be initi- shall be perfonned each re:-

ated and the reactor pressure ' fueling outage.

shall be reduced to 90 psig within?24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 4. When it is detemined that two 4 valves of the automatic pressure relief-subsystem are inoperable, ,

the-HPCI shall be demonstrated

to be operable immediately.

E. Reactor Core Isolation Cooling System E.

Reactor Core Isolatien Cooling System-1.) The RCIC system will;be operable Surveillance of the' RCIC system:shall

. whenever the reactor pressure is be performed:as specified below with

_ greater than 150 psig and fuel is the following limitations For item in the' reactor vessel. -l4.5.E.3..theplantisallowed12 hours '

in which to successfully complete the '

12.- During'startup following a refuel test once reactor vessel pressure is outagecor_an outage in which work adequate to perform each test.: In Lwas perforneo that directly affects addition,-'the testing required by ites' the.RCIC system _ operability, if . 4.5.E.3.a.shall: be completed prior to : ~

testing requirementsLof'4.5.E. jexceeding325psig.reactorvessel- ,'

cannot-be met,acontinued reae . pressuN. : If RCIC is ~made inoperable-

<startup;is not permitted. .The to perfom overspeed testing,' 24' hours - )

RCIC system 'shall

be. declared is-s110wed to complete the tests before +

. inoperable, and the provisions of exceeding 325 psig.-

Specification 3.5.E.4,shall be T implemented. Item Frecuency

73. . lExcept forithe 1 imitations of  : 1. - Valve Position Every 31Ldays i3.5.E.2, if the RCIC system.is made er.found to be inoperable, 2.; . Flow Rate Test -

Every 92 days ccontinued reactor. operation is RCIC Pumpishall-permissible'only during the suc ' ~ deliver at least.

=coeding-14Ldays-unless such sys-- 1 400 gps,against~.

-tem is sooner made. operable,

a. system head

~ provided1that during such 14 days- l corresponding to the HPCI system is operable. a reactor vessel

~0therwise, the' provisions of. pressure of > 1150

'Specificktion 3.5.E.4 shall-be psig when steam is implemented;

~3.5/4.5-7 Amendment No. ) N ]

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- QUAD-CIT!!5 DPR-30 C. HPCI Subsystem C. HPCI $ubsystem Surveillance of the HPCI subsystem shall be performed as specified below with the following limitations. For item 4.5.C.3, the plant is allowed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in which to successfully complete the test once reactor pressure is adequate to perform each test. .In addition, the testing required by item 4.5.C.3.a shall be completed prior to exceeding 325 psig reactor vessel pressure. If HPCI is made inoperable to perform overspeed testing, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is allowed to complete the tests before exceeding 325 psig.

lits LtentM,y

1. The HPCI subsystem shall be 1. Valve Position' Every 31 days operable whenever the reactor pressure is greater than 150 psig and fuel is in the reactor vessel.

2. During startup following a 2. Flow Rate Test - Every 92 days refuel outage or an outage in HPCI pump shall which work was performed that deliver at least directly af fects HPCI system 5000 ppm against operability, if the testing a systrm head requirements of 4.5.C 3.a cannot I corresponding be met, continued reactor to a reactor startup is not permitted. The vessel pressure HPCI subsystem shall be declared of 11150 psig when inoperable, and the provisions steam is being of $pecification 3.5.C 4 shall supplied to thc be implemented. turbine at 920 to 1005 psig.

3. .Encept for the limitations of 3. riow Rate Test - During 3.5.C.2, if the HPCI subsystem HPCI pump shall startup is'made or found to be deliver at least following inoperable, continued reactor 5000 gpm against a refuel operation is perinissible only a system head outage

'during the succeeding 14 days corresponding to or an outage

- unless such subsystem is sooner a reactor vessel in which work made operable, provided that pressure 6t: was performed during such 14 days the a. 1 300 psig that directly automatic pressure relief when steam is affects HPCI subsystem, the core spray being supplied system subsystems, LPCI mode of-the RHR to the turbine' operability.

system, and the RCIC system are at 250 to 325 operable. Otherwise, the psig, and

-provisions of Specification b. 2 1150 psig when 3.5.C 4-shall be implemented, steam.is being supplied tu the turbine at 920 to 1005 psig.

4 If the requirements uf , 4. Simulated Each refueling Specification 3.5.C.1, 3.5.C.2 Automatic outage or 3.5.C 3 cannot be met, an Actuation Test orderly shutdown shall be initiated, and the reactor 5 Logic System Each refueling pressure shall be reduced to functional outage c150 peig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Test 1746j -

3.5/4.5-4a Amendment No.

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^;o  : QUAD-CITIC5 DPR-30 E. ; Reactor Core Isolation Cooling System E. Reactor Core Isolation Cooling System SurveillanceoftheRClksystemshall be perfomed as specified below with the following limitations.- for item 4.5.t.3. the plant is allowed 12' hours in which to successfully

. complete the test once reactor vessel F pressure is adequate to perform eacS ,

, tett, in additior the testino-  !

required by' item 4.5.E.3.a shall be-completed prior' to exceeding 325 psig reactor vessel pressure. .lf RCIC is-made inoperable to perforir overspeed ,

testing -24 hours is allowed to .

complete the tests before exceeding l 325 psig.

lism fiteut0Iy .

1.; The.RCIC system will be operable 1. Valve Position Every 31 days '

whenever the reactor pressure is 4 greater than 150 psig and fuel .

_ Els in the reactor vessel.>

~

C 2. During startup following a 2. Flow Rate-Test - Every 92 Aays refuel' outage or an outage in 'RCIC pump shall

. which work was performed that' deliver at least directly af fects RCIC sy,*em 400 gpm against

• operability.-if the testing- , a system head requirements of 4.5.E.3.a cannot  !  : corresponding-s

-be met. continued reactor to a reactor-

'startup is not pemitted. : The - vessel pressure . <

, -RCIC system shall be-declared- of 11150 psig when '

inoperable. and the provisions steam is being

-of Specification 3.5.E. shall . supplied to.the.

' be implemented. '

. ' turbine at 920 to- _

-_1005 psig. _;

3. -Except for'the limitations of~,

~

3. ' Flow Rate Test - During 3.5,E.2, if'the RCIC system is 'RCIC pump shall. startup .

made or found to be inoperable, deliver at.least following t icontinued reactor operation is - -400 gpm against a refuel permitted only during the= a system head -. outage .

- > ' succeeding 14 days valess.such corresponding to- or an outage <

system is sooner made operable, - a reactor vessel 1 .in which work' -

Jprovided that during such 14. (pressure of ^ . was performed .

days the HPCI system _is - a.:1 300'psig that directly +

--operable.E 0therwise, the. -when staam is' affects RCIC '

. provisions of,Spectficatien being supplied system .

3.5.E.4 shallie implemented. to the turbine operability. '

tat 250 to 325 psig.--and .

b. 1 1150 psig when

_ steam is beinge

, i supplied to the i

+ "

. turbine at.920 to 1005 psig.

14 . Iff the requ(rements of - _ . 4.. Simulated. - rach refueling' l >

~

Specification 3.L E.1, 3.5.E.2 Automatic- -- outage

-or 3.5.E.3 cannot be met, an. ' Actuation Test orderly shutdown 4 hall be. .

' initiated and the reactor? 5._ Logic.5ystem Each refueling

-pressure shall-be reduced to- Functional- outage 4 <150 pst; within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Test 1746j '

• 3.5/4.5-6 Amendment No.

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1 ' ATTACHMENT 4 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION FOR ,

} PROPOSLO AMEN 0 MENT.

-The proposed changrs outilned in this-amendment request would change the action-provisions'of Technical Specification (TS) 3.5.C.2 for the High Pressure Cool _ ant _ Injection (HPCI) system-and 3.5.E.2 for the Reactor Core '

Isolation Cooling (RCIC) system to reduce the likelihood of. unnecessary plant

. transients and challenges to safety systems caused by forced shutdowns related ,

to 6nt unanticipated flow-performance testing failure while at noimal operating i i

rtactor pressure. .The proposed amendment would change the action provisions of Surveillance Specifications 4.5.C.3.a and b for HPCI and 4.5.E.a and b for RCIC to a limited action provision applicable to the failure to demonstrate

-the required-low reactor' pressure testing of Surveillance Specifications 4.5.C 3.a and 4.5.E.3 a only. Failure to meet the requirements of  :

Surveillance Specification 4.5.0.3.b and 4.5.E.3 b (flow rate testing of a

HPCI or RCIC system at normal operating pressure) would fall under the

' jurisdiction of current Action Specification (s) 3.5.C.3 and 3.5.E.3, which t provides a-14_ day allowable outage time with compensatory measures in place.

These changes have been-reviewed-by CECO, and we believe that they do not

.present a--signifi. cant hazards consideration. The basis for our determination sis ~ documented aslfollows:

MSIS_ EOR _N0_SIGNIEICANLHAZARDS 00NSIDERATION CECO.has (valuated this propused amendment and determined that it involves no

'significant hazards = consideration. In accordance with the criteria-of 10 CFR 50.92 (c) 0. proposed-amendment:to an operating license involves no significant

. hazards considerations-if-operation _'of the facility, in accordance with-the

, proposed amendment, would not:'

-1. Involve a.significant increase-in the probability or consequences of

, an accident previously evaluated because: ,

IIDL8

The proposed change would limit the action provisions of~TS 3.5.C.2 to require entry into the Action Specification of_TS 3.5.C.4-(24 hour-shutdown and pressure reduction)-only upon failure to

meet the low reactor' pressure flow rate testing provisions of TS 4.5.C.3.a for the HPCI. system and not upon failure to meet the normal operating

< ' pressure-flow rate test of TS 4.5.C 3.b. _No accident. initiator or

. precursors =are changed.by the-proposed change, and by reducing-the-likelihood of plant transients and challenges to safety systems, the realistic probability of a Reactor Coolant Pressure Boundary failure

--accident as previously-evaluated is not altered as a result of the proposeo change to:TS 3.5.C.2. Therefore, the proposed change would in no-_way-significantly increase the probability _of an accident previously evaluated.

/sc1:1209:43

_ . m ._ _ _. . . _ _ __ __

. The unavailability of the HPCI system during a design basis accident is within the design assumptions for ECCS component operation. The proposed change to TS 3.5 C.2 would not change or alter the design assumptions used in the limiting basis LOCA concurrent with the worst single failure. In the accident analysis, the HPCI single failure is bounded by-the battery failure case which assumes two failures (11.e., battery and HPCI). The recirculation suction line break with battery failure is the limiting DBA break /fallure combination satisfying the requirements of 10 CFR 50, Appendix K. The proposed change to TS 3.5.C.2 does not change the compensatory action provisions of current TS 3.5.C.3, which include that RCIC remain operable to perform a similar function; nor will the proposed amendment extend the Allowabie Outage Time be extended beyond the 14 days as previously approved. Therefore, the proposed amendment to change TS 3.5.C.2 would not significantly affect the consequences of an accident previously evaluated.

ITEM _D The proposed change to TS 3.5.E.2 would in the same way reduce the likelihood of plant transients and challenges to safety systems and therefore in no way alters the accident initiators or precursors that could result in a Reactor Coolant Pressure Boundary failure accident as previously evaluated. A unit shutdown and reduction in pressure to < 150 psig would still be imposed should the low reactor pressure test of TS 4.5.E.3.a fall. The current remedial actions of TS 3.5.E43 would apply should RCIC fall to meet the required flow rate at normal operating pressure. Therefore, deleting the requirement that would lead to unnecessary cycling would in no way significantly increase the probability of an accident previously evaluated.

RCIC system ability to provide makeup coolant to the reactor pressure vessel during an isolation accompanied by a loss of feedwater is used to evaluate plant retionse to transient events. However, the-RCIC system is not an Emergency Core Cooling system and no credit is taken in the safety analysis for RCIC operation. Therefore, the. proposed change to limit the action provision of TS 3.5.E.2 concurrent with the compensatory action of current TS 3.5.E.3, which requires that HPCI be opeiable to perform a similar function, cannot significantly affect the consequences of an accident previously evaluated.

2. Create the possibility of a new or different kind of accident from L any previously evaluated because:

l lIEM_A The proposed change to TS 3.5.C.2 does not change the design intent of the HPCI system nor are any physical-plant changes proposed by the amendment request. ECCS performance without the availability of HPCI as a postulated failure has been previously evaluated and found to be acceptable. No new or different modes of operation, other than those already evaluated, are introduced by the proposed change to TS 3.5.C.2, therefore, there is no possibility of a new or different kind of accident from any previously evaluated.

/scl:1209:44

- 3 -

EDLD The proposed change to TS 3.5.E.2 for the RCIC system does not result in any physical plant changes, nor does the proposed change to TS 3.5.E.2 involve any new or different operating modes of operation, therefore, there is no possibility of a new or different kind of accident from any previously evaluated.

3. Involve a significant reduction in the margin of safety because:

IIIM_A The proposed change to TS 3.5.C.2 makes no change to the accident or transient analysis of the plant. Plant operations and safety are improved by not imposing unnecessary shutdowns and challenges to plant safety systems. The current compensatory measures of TS 3.5.C.3 are not changed by the proposed amendment; nor is any established safety limit, operating limit or design assumption affected by the proposed amendment. Therefore, the proposed change does not involve a reduction in a margin of safety.

UDLD The proposed change to TS 3.5.E.2 makes no change to the accident or transient analysis of the plant nor are plant operations made less conservative. Plant o)erations and safety are improved by not imposing unnecessary slutdowns and challenges to plant safety systems. The compensatory measure which requires that HPCI remain operable will not be changed nor will the Allowable Outage Time be

! extended beyond the previously approved 14 days. No established safety limit, operating limit or design assumption is altered by the proposed amendment. Therefore, the proposed change does not involve a reduction in a margin of safety.

/sc1:1209:45

$ ATTACHMEN1 5 ENVIRONMENTAL ASSESSMENT FOR PROPOSED AMENDMENT The proposed changes to the QCNPS Technical Specifications (TS) involve the change to the Action provisions of Technical Specification (TS) 3.5 C.2 for the High Pressure Coolant Injection (HPCI) system and 3.5.E.2 for the Reactor Coro Isolation Cooling (RCIC) system to reduce the likelihood of unnecessary plant transients and challenges to safety systems caused by forced shutdowns and unnecessary reactor cycling related to an unanticipated flow-performance testing failure. The proposed change is consistent with Studard Technical Specifications in permitting reactor startup to continue upon successful completion of the low pressure flow rate test while allowing compensatory measures to permit a 14 day allowable outage time of a single high pressure injection system, once normal operating reactor pressure is achieved.

Commonwealth Edison has evaluated the proposed amendment in accordance with the requirements of 10 CFR 51.21 and has determined that the amendmerit meets the requirements for categorical exclusion as specified by 10 CFR 51.22(c)(9).

The proposed amendment to TS 3.5.C.2 for the HPCI system does not change the types of effluents or increase the amount of effluents that may be released offsite. The proposed change to TS 3.5.C.2 would not change or alter the design assumptions used in the limited basis LOCA, concurront with the worst single failure, Therefore, the proposed amendment to change TS 3.5.C.2 would not significantly affect the consequences (including the types or amounts of effluents released offsite) of an accident previously evaluated.

The proposed change to TS 3.5.E.2 for the RCIC system does not change the types of effluents or increase the amount of effluents that may be released offsite. The RCIC system is not considered an Emergency Core Cooling System (ECCS) and no credit is taken for RCIC operation in the safety ane'ysis.

-Therefore the proposed amendment, concurrent with the compensatory action requiring that the=HPCI system be operable to perform a similar fLnction, would not significantly impact the-consequence (including the types or amounts of effluents released offsite) of an accident previously evaluated.

The proposed changes-do not significantly affect individual and cumulative occupational radiation exposures. The revised action statements would allow continued operation upon the successful completion of a low pressure flow performance test followed by the failure of a normal operating pressure flow permance test. Individual and cumulative occupational rediation exposures would not be significantly affected since the radiation levels in the areas surrounding the HPCI and RCIC systems are independent of the operational status of the reactor.

In conclusion,the p,oposed amendment will not result in any increase in environmental consequences beyond those already accepted by the NRC in the Final Environmental Statement.

/sc1:1209:46