Text

Proposed Tech Spec Changes,Defining Refuel Condition & Clarifying Various Sys During Refuel & Shutdown Conditions
	ML20138J369
Person / Time
Site:	Millstone
Issue date:	10/16/1985
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20138J349	List: B11689, Application for Amend to License DPR-21,revising Tech Specs to Define Refuel Condition & Operability Requirements of Sys During Refuel & Shutdown Conditions.Fee Paid; ML20138J369;
References
	NUDOCS 8510290324
	Download: ML20138J369 (22)
	v • d • e

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Docket No. 50-245 i

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a Attachment No. 2 4

Millstone Nuclear Power Station, Unit No.1 Proposed Revision to Technical Specifications e

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October,1985 a

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FF Refuel Condition

%e reactor is in the Refuel Condition when all of the following conditions are met:

1) All Control. Rods are. fully inserted or the Refuel Interlocks are operable with no more than one rod not fully inserted.

'2) h e reactor mode switch is in the refuel. position.

3) % e Reactor Coolant Temperature is <200*F.

4) W e Reactor Vessel is vented.

NOIE: It is permissible to perform the Refuel Interlock Functional Check, and still be considered in the Refuel Condition.

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P-LIMITING OCNDITIN FOR OPERATIm SURVE:IIDN0: REQUIRENENT 3.4 SPANmY LICUID O[NINOL SYSIIM 4.4 STANmY LIOUID O[ nil 0L SYSIIM Applicability:

Amlicability:

Applies to the operating status of the starrby liquid control Applies to the periodic testing requirenents for the systen.

stanty liquid control systen.

miective:

Ib assure the availability of the standby liquid control Ib verify the cperability of the standby liquid control systen.

systen.

Specification:

A.

Nonnal Operaticn A.

Normal Operaticn During periods when fuel is in the reactor, the liquid The cperability of the stan ty liquid cxmtrol poison systen shall be cperable except when the reactor is system shall be verified by performance of the in the Gold Shut & wn or Refuel Conditicn and following testing:

Specification 3.3.A is met arx! except as noted in Specificaticn 3.4.B below.

1.

At least once per mmtk Dsnineralized water shall be recycled to the test tank. Purp mininm flow rate of 32 gpn shall be verified against a systen head correspcnding to a reeactor vessel pressure of 1225 psig.

2.

At least once durirn each coeratirn cycle a.

Manually initiate cne of the two standby liquid anntrol systars and purp denineralized water into the reactcr vessel at or near cperating pressures.

This test checks explosicn of the charge 3/4 4-1 associated with the tested systen, pttper operaticn of the valves and purp capacity. The

LIMITING ENDITIm Em OPEPATIm SURVEIIDME RBQUIRDEfr B.

Operation with Incperable Otnpanents replaoament charges to be installed will be selected frun the sate batch as thme tested.

Frun ard after the date that a redandant cotponent is P.oth systats shall be tested and irspected, made or fond to be imperable, Specification 3.4.A includirg each explosim valve in the murse shall be considered fulfilled, provided that:

of two geratirg cycles.

1.

The catponent is retumed to an operable omditim b.

Marually initiate each syston, except the within 7 days or explosicn valve and ptstp solution in the l

2.

A written report shall be sutmitted to the Nuclear Regulatory Connission when the traintenance to c.

Test that the settirg of the systen pressure restore the canpcrunt to cperable conditim will relief valws is bet >een 1350 and 1450 psig.

last larger than 7 days.

Ibr errata sheet dtd 10-7-70*

3/4 4-2

LIMITDG CINDITIW FtR OPERATICN SURVEIIIANCE Rf0UIRENENT 4.

Frcm and after the date that one of the IICI purps 3.

During each five-year period,an air test shall is made or fourd to be incperable for any reason, be performed on the drywell spray headers ard reactor cperation is permissible only durirg the ncezles.

succeedirg 30 days unless such purp is sooner made (perable, provided that chrirg such thirty days the B.

Surveillance of the (bntainnent Cboling Subsysters renaining. active corponents of the LICI ard shall be performed as follows:

contairment coolirg subsysten and all active cuupccents of both core spray subsystens ard both 1.

Energency Service Mter Subsysten Testing:

energency power sources required for operaticn of such corponents if rn external source of power were Itan Frequency available shall be cperable.

a.

Punp & Valve Ibr surveillance 5.

A maxinun of one drywell spray locp may be Operability Ibquirenent 4.13 incperable for 30 days when reactor water tatperature is greater than 21:PF.

6.

If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be' initiated ard the reactor shall be in the Gold Shutrbwn or Ibfuel Conditicn within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B,-

Contairment (boling Subsystets 1.

Dccept as specified in 3.5.B.2, 3.5.B.3, 3.5.F.6, 3.5.F.7 and 3.5.F.8, both contairment cooling subsystats shall be cperable whenever irradiated ftel is in tha reactor vessel.

3/4 5-3

LIMITING CENDITIN KR OPERATIm SURVEIIDNT RBOUIRENENT 5.

Frun and after the date that one containnent cooling subsysten is made or found to be incperable for any C.

Surveillance of FHCI Subsysters shall be performed reascn, reactor operaticn is pennissible only during as follows:

the anw=11ng four days provided that all active corpments of the other ocntainnent cooling 1.

Item Freauency subsysten, both mre spray subsystors ani both energency power sources for operation of such a.

Purp and valve Per Surveillance catponents if no external source of power were cperability Requirenent 4.13 available, shall be operable.

6.

If the requiratent of 3.5.B cannot be net, an orderly shutdown shall be initiated ard the reactcr shall be in tle Cold Shutchwn or Refuel otnditicn within 24 b.

Sinulated Autanatic Every refueling hours.

Actuation 'Ibst outage C.

EhCI Subsysten 2.

Once a week the quantity of water in the w4nex2te storaje tank shall be lagtjed.

1.

Except as specified in 3.5.C.3 belcw, the EhCI subsysten shall be operable whenever the y ecolant tarperature is greater than 330T and irraliated fuel is in the reactor vessel.

2.

'Ibere shall be a mininun of 225,000 gallms of water in the ccrdensate storage tank for qwraticn of the FWH.

3/4 5-5

e LIMITING GNDITIW FT OPERATIN SURVEIUANCE REGUIlOfNT 3.

Fran ard after the date that the ENCI subsysten is D.

Surveillance of the Autanatic Pressure Belief Subsystan made or found to be inoperable for any reason, shall be perfcnned as follows reactor cperaticn is pennissible only.during the succeeding seven days unless such subsystem is 1.

Durirg each operating cycle, the following s nll somer made operable, provided that chrity such be perfonned:

seven days all active cunoeits of the Autanatic pressure Iblief Subsysten, the core spray a.

A sinulated autoaatic initiation of the systen subsystens, UCI subsysten, and islatim condenser throughout its operating segexxe but excitdes systan are cperable.-

acbal valve opening, ard 4.

If the requirements of 3.5.C cannot be met, an b.

With the reactor at low pressure, each relief orderly shutdown shall be initiated ard the reactor valve shall be manually cyaned until valve coolant tarperature shall be less than 330*P within operability has been verified by torts w.ter 24 hourc.

level instrunentation, or by an audible disdarge detected by an individtal located D,

Autanatic Pressure Relief (APR) Subsystats outside the torus in the vicinity of each relief line.

1.

Except as specified in 3.5.D.2 below,the APR subsysten shall be cperable whenever the reactcr coolant temperature is greater than 330*P and irradiated fuel is in the reactor vessel.

3/4 %

r LIMITING OWDITIm Em OPERATIW SURVEIIIANCE RECUIREMENT 2.

Fron ard after the date that me of the four 2.

When it is determined that one safety / relief valve

. relief / safety valves of the autanatic pressure relief of tM autanatic pressure relief subsystan is subsysten is mMe or found to incperable when the inoperable the actuation logic of the runaining APR reactor coolant temperature is above 330*F with valves ard MCI subsysten shall be demnstrated to irradiated fuel in the reactor vessel, reactor be cperable imnediately ard daily thereafter.

cperaticn is permissible only during the suo edirg seven days unless repairs are completed and the E.

Surveillance of the Isolatim Gardenser Systan shall be subsysten mach fully operable ard provided that perfonred as follows:

during such tirre the runainirg autanatic pressure relief valves, BCI subsysten, and gas turbine 1.

Isolatim Ccrrbnser Systan Testirg:

generator are cperable.

a.

The shell side water level and temperature 3.

If the requirerent of 3.5.D carrot be rmt, an orderly shall be diecked daily.

shutdown shall be initiated ard tM reactor oJolant torperature shall be less than 330*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

E.

Isolation Cmdenser Systan 1.

khenever the reactor molant teTperature is greater than 330*F and irradiated fuel is in the reactor vessel, the isolaticn ccrdenser shall be cperable except as specified in 3.5.E.2 ard the s!wll side water level stall be greater than 66 indes.

3/4 5-7

c LIMITING C[NDITIN KR OPERATIN SURVEIIIANCE RDOUIRDETT 2.

Frun ard after the tine that the Isolation Onkmser b.

Sinulated autanatic actuation and functional is made or fourd to be irrperable, for any reason, systan testing shall be performd durirg each power cperatim shall be restricted to a noxinun of refuelirg outage or whenever nnjor repairs are 40% of full power, i.e., (804 FW ) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months orpleted on the systan.

until such tine tre Isolation r is mtumed to service provided that all active cnTponents of the c.

The systen heat renoval capability shall be core sprzy subsystens ard IKI subsysten are detennined once every five years, operable.

d.

Calitrate vent lire raliation nonitors 3.

If the requirements of 3.5.E cannot be met, an quarterly.

orderly shutcbwn shall be initiated and the reactor coolant tarperature shall be less than 330*F within e.

Motor operated valves shall be tested per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

surveillance requiratent 4.13.

F.

Mirtinn Core ard Contairitent (boliro Systan Availability F.

Surveillance of Gore and Contairinent Cooliru Systan 1.

Ex pt as specified in 3.5.F.2, 3.5.F.3, 3.5.F.7 ard 1.

'Ibe surveillance requiratents for rormal operation 3.5.F.8 below, both eTergency power sourms shall be are in Section 4.9.

operable whenever irradiated fuel is in the reactor.

3/4 'H3

LIMITING GNDITICN KR OPERATIW SURVEIIIAN8 REOJIRDENT 2.

Frau and after the date that the diesel generator is made or found to be inoperable for any reason, continued reactor cperation is permissible cnly during the am% ding seven days provided that the gas turbine generator, EW.7, Autanatic Pressure Relief Subsysten, all cortponents of the low pressure cnte cooling ard the contairment cooling subsystens shall be cperable.

3.

Frau ard after the date that the gas turbine generator is made or found to be irrperable for any reason, crmtitued reactor cperation is permissible only during the succeeding four days provided that the diesel generator, all corponents of the APR subsystem, all empments of the Icw pressure core cooling ard amtairnent cooling subsystems shall be cperable.

4.

If the requirerents of 3.5.F.1 annot be met, an orderly shutdown shall be initiated ard the reactor shall be in the Cbld 9mtdown or Refuel ccrdition within 24 h ars.

5.

Any c3rbinaticn of irrperable crmponents in the core and crntainnent cooling systans shall rot defeat the capability of the renaining operable u.mp1uits to fulfill the core ard omtaiment cooling functions.

3/4 H

e LIMITING RNDITIW KR OPERATICN SURVEILLANCE REQUIREMENT microcuries per gran DOSE ECUIVAUNr I-131 chrity any continuous period of time longer than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or is greater than 4.0 microcuries per gran have the reactor in the Cold Shutdown or Refuel Condition within 24 h mrs.

b.

khen the reactor is in the STARIUPADr STANmY or RN nub with tM reactor coolant at any tmperature or in the SUIIDN node with tM averaje reactor coolant temperature greater than 21f F, the reactor coolant specific activity stull be limited to less than 100/T microcuries per gran total activity.

Een the reactor is in the SIARIUPAUr SINEY or RN nuie with tM reactor coolant at any taperature or in the SUID0hN nnh with tM averaje reactor coolant tmrerature greater than 21fF, if the reactor coolant specific activity is greater than 100/E microwries per gran have the reactor in the Cold Stutim or Ibfuel Cordition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3/4 6-2b

e e

LIMITDG (IEDITICN KR OPERATICN SURVEIIl#CE R8QUIREMNT G.

Jet PLmp G.

Jet Ptmps 1.

hhenever the mactor is in tle StartupAbt Standby 1.

Whenever there is a recirculation flw with the or Run mode, all jet ptmIn shall be intact ard all reactor in the startup/ hot stardby or run nodes, operating jet ptmps shall be operable. If it is jet ptmp integrity and cperability shall be chtermined that a jet ptmp is irrperable, an orderly checked daily by verifying that the follwim two shutdown shall be initiated ard the reactor shall be crrditicns do not occur sinultaneously:

in the Cold Shutdown or Refuel Ccrdition within 24 Murs.

a.

The meirculaticn ptsp flow differs by note than 10% fran the established speed-flow 2.

Flcw irdicaticn frun each of the twenty jet ptrps characteristi shall be verified prior to initiation of mactor startup frun a cnid shutcbwn conditicn.

b.

The indicated total care flm is nore than 10% greater than the core flow value derived 3.

The indicated core flow is the sum of the flow frun established power-core flcw indicaticn frun each of the twenty jet ptnps. If relationshirn.

flow irdicaticn failure occurs for two or note jet ptmps, imnediate corrective acticn shall be taken.

2.

Additicnally, when operating with one If flow irdicatico cannot be obtaimd for at least recirculaticn pur:p with the equalizer valve nireteen jet ptmps, an orderly shutdown shall be closed, the diffuser to lower plerun differential initiated within 12 Nurs and the mactor shall be pressure shall be checked daily, ard the in the (bld Shutdown or Ibfuel Omdition within 24 differential pressure of any jet ptmp in the idle

hcurs, loop shall not vary by nore than 10% frun established patterns.

H.

Recirculation Ptmp Flow Misnatch 3.

The baseline data required to evaluate the 1.

hherever Mth recirullaticn ptsts are in operation, ccviitions in Specificaticn 4.6.G.1 ard 4.6.G.2 punp speois shall be maintained within 106 of each will be aquired each cperatim cycle.

other when power level is greater than 80% and within 15% of each other when pmer level is less H.

Recirculaticn PLmp Flcw Mismatch than 80%.

1.

Recirculation ptmp speed shall be checked daily for misnatch.

3/4 6-10

e LIMITING 030lTIm KR OPERATIN SWVEHUNCE BEQUIRB6TT 2.

If Specification ' 3.6.H.1 camot be met, me recirculaticn pap shall be tripped. Operation with a sirgle recirculation pmp is permitted for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the recirullation pap is axxer made cperable.

If the gap camot be made operable, the reactor shall be in the 031d shutdown or Iefuel Ocrdition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

'Ihe reactor shall not be cperated unless the equalizer valves are closed.

4.

With the acae switch in the starttp/ hot stanty or run m@, cperation without forud cirullaticn shall rot be permitted.

I i

I 3/4 6-11

e LIMITING C[NDITIN KR OPEFATIm Sl;RVEIIIANCE IEQUIRENENT 3.6.I SNLE ERS 4.6.I SNUBBEI6 1.

Tne snubbers listed in Tables 3.6.1.a ard 3.6.1.b are Each snutter shall be duu si. rated CPERABT by required to protect the reactor coolant systen or other performance of the followirn augnented inservice safety related systers cr corponents.

inspection sujuu.

2.

Durirg all nodes of operaticn except Gold Shutdown and 1.

11sual Inspectim Refuel Crndition, all snubbers shall be cperable.

All snutters shall be visually inspected in 3.

If a snubber is determined to be inoperable, crntinued accordance with the followirg schedule.

reactor cperatim is permissible cnly (12 ring the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months follcwing such determinaticn unless the snutter is

of Sntibers Ebund sooner rmimi, made (perable, or an ergineerirg Irgrrable During evaluaticn determired the sigported systat/carponent to Inspection m n2 ring Next Fequired be cperable with the incperable snubber.

Inspectim Interval Inspecticn Interval 4.

If the requirenents of 3.6.I.2 ard 3.6.I.3 cannot be 0

18 tronths 125%

met, an orderly shut &wn shall be initiated ard the 1

12 months 125%

reactcr shall be in the Cold Shut &wn or Refuel 2

6 months +25%

(bndition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

3,4 124 days 125%

5,6,7 62 days 125%

5.

If a snubber is determined to be irrperable while the

>8 31 days 125%

reactor is in the Stutdown or Refuel Omditicn, the j

snubber shall be male cperable or replaced prior to The required inspecticn interval shall not be reactor starttp.

lergthened rnore than ene step at a time.

6.

Snubbers may be ailed to or deleted frun safety related Snutters may be categorized in two groups, systers without pricr Liceme Amerdnent to Tables mechanical and hydraulic. Each grcop may be 3.6.1.a and 3.6.1.b provided that safety evaluations, divided into two sikgratos; those amessible and doeurentaticn, and reportirg are provided in accordance tMee inac ssible during reactor cperatim.

with 10 GR 50.59 ard that a prqned revision to Tables Each group ard subgrotp may be inspected 3.6.1.a ard 3.6.1.b is included with the next License independently in amordance with the above Prerdnent Ikquest.

schedule.

3/4 6-12

a e

LIMITDG GNDITIm FCR OPERATIm SURVEIIDEE RE0UIREMENT d.

At least one of the two existing narrow range c.

Torus water level instrunentation shall torus water level monitoring systans shall be be calibrated once per 6 ntnths if both cperable whenever primary cxntaintent is systats are operable, required, except as specified in 3.7.A.l.e.

d.

Torus water level instrunentation shall e.

If the torus water level monitorirg systan is be calibrated once per nonth if cnly one disabled and cannot be restored in six (6) systen is operable.

hours, an orderly shutdown shall be initiated and the reactor shall be in Gold Shutdown or 2.

Drywell to Sumressicn Ontber Differential Refuel Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the Pressure level nonitorirg systen is node cperable.

a.

'Ibe differential pressure between the 2.

Drywell to Sumressicn Chatber Differential Pressure drywell and suppression charber shall be remrded cnce per shift.

a.

Differential pressure between the drywell and suppressim darber shall be maintainal equal to or greater than 1.0 psid, exwpt as specified below.

(1) 'Ihe differential pressure shall be established within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of enterirg the

_RUN node, and may be reduced to less than 1.0 psid 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to a scheduled stutdown.

(2) 'Ihe differential pressure nay be reduced to less than 1.0 psid for a maxinun of four (4) trurs during required cperability testin] of the torur/ reactor buildirg and drywell/ torus vacusn breaxers, and durirg ventirg ard purgirg of the containrent.

3/4 7-3

LIMITING (INDITIN EIR OPERATIN SURVEIIIAN0: R8QUIREMNT (3) Differential pressure may be less than 1.0 psid for b.

Drywell to torus differential pressure a period not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for purpose of instrwentation shall be calibrated once per nonth conictirg a drywell entry, if cnly cne systan is operable.

(4) If the provisions of (1) and (2) above cannot be c.

The drywell to torus differential pressure met, the differential pressure shall be restored instnmentation shall be calibrated once per six within the a%mt six (6) hour period or the nonths if both systans are operable.

provisions of 3.7.A.7 shall apply.

b, At lest one (1) drywell to torus differential pressure nonitoring systan shall be operable whenever primary contairinent is required, ex pt as specified in 3.7.A.2.c.

c.

If the drywell to torus differential pressure nmitoring systen is disabled and cannot be restored in six (6) hours, an orderly shutrbwn shall be initiated ard the reactor shall be in the Cb1d Shutxbwn or Refuel Conditicn within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless the differential pressure nonitoring systen is made cperable.

3/4 7-4

O e

d LIMITDC ENDITICN Em CPERATKN SURVEIURCE Rf0JIIUMNT b,

Up to two (2) of the ten (10) suppression charber-drywell (3)

At least two (2) of the suppression chamber-drywell vxuun breakers may te determimd to be irrperable prurided vacuan breakers shall be inspected inclu11rg intemal that they are secured, or known to be in the closed emponents. If seating or friction deficiencies am roted pcsiticn.

such that Specification 3.7.A.5 could not be tret, all vamun breakers shall be inspected includirg internal c.

If Specificatim 3.7.A.5.a or b cannot be tret, the situation co'pomnts ard deficiencies corrected.

shall be cormeted within 24 tours, or tM reactor shall be plmed in tM Cb1d Shutdown or Ibfuel Oandition within the afwvyvmt 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3/4 7-11

a r

LIMITDC (DOITICN KR OPERPTIN SURVEIUANCE RECUIRI%f 6.

Oxygen concentratim:

6.

Oxygen concentration:

a.

After azipleticn of the starttp test prugau and menever inerting is required, the p-imary contairunent demonstration of plant electrical output, the oxygen canoentraticn shall be measured arrl recorded on a primary mntairunent atmosphere shall be raboed to weekly basis.

less than 4% amygen with nitrogen gas whenever the reactor omlant pressure is greater than 90 psig and during reactor power operaticn except as specified in 3.7.A.6.b cr 3.7.A.6c.

b.

Within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period s*mqwmt to placing the reactor in the Run made following a shutdown, the contairment atumphere oxygen concentraticn shall be rechoed to less than 4% by volune and maintained in this ariditicn. Deinertiro may otmmence 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to a shutdown.

c.

Oxygen concentration may be greater than 4% by voltane for a period not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months for purpcees of cxnbetirg drywell entries relatirg to testirg, surveillance, or maintenance cn equipnent inportant to safety.

7.

If the specifications of 3.7.A cannot be net, initiate an orderly shutrbwn and have the reactor in the (bid Shutxtwn or Ibfuel (bndition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3/4 7-12

a 4

e LIMITDC ONDITICN KR TEPATICN SUREII1ME PEUIIGHE C.

Secanthry Ortairrent d.

Each cirt:uit shall be cperated at least 15 mirutes per nmth and operated as required to 1.

Secordary cxmtairnent integrity as defimd in naintain the relative htsnidity in the charmal Sectico 1 shall be maintained durirg all modes of bed at or belm 70%.

plant operation except wten all of the follwirg ccrditicns are net.

3.

a.

At least cnce per cperatiro cycle, autanatic initiation of each branch of the stardby gas a.

'Ihe rextor is in the (b1d Shutckwn Ocrditicn treatment systen shall be (kronstrated.

ard Specificaticn 3.3.A is net.

b.

At least cnce per cperatiry cycle manual b.

"Ihe nel Cask or Irradiated Ebel is not beiry cperability of the bypass valve for filter awed within the Ibactcr Buildirg.

coolirg shall be ckumstrated.

c.

When cne cirujit of the stanty gas treatrent systen becxres inoperable the other ciruait shall be daust. rated to be cperable inmediately and daily thereafter.

C.

Secondary Contairrent 1.

Secondary cmtairnent surveillance shall be perforned as irdicated belm:

a.

A secordary ctntairnent capability test shall be corducted after isolatiry the reactor buildirg ard placirn either stan br gas treatnent systen filter train in cperation.

Such test shall demonstrate the capability of the secondary cmtairmmt to maintain a 1/4 inch of water vacurn with a filter train fim rate of rot nere than 1100 scfm. Semndary cxntairrent 3/4 7-13

O

'2 LIMITDG CCNDITIm KR TERATIm SURVEIIIANCE REQUIREMNT D.

Primary Ontairment Imlation valves capability shall be dmonstratal at three or more points within the containment 1.

Durirg reactor power cperating conditions, all prior to fuel mowment and may be isolaticn valves listed in Table 3.7.1 ard all denonstrated tp to 10 days prior to fuel instnment line flow check valves sha13 be operable movement.

Sectniary contairment except as specified in 3.7.D.2.

capability need not be demtnstrated more than once per cperating cycle unless damage or nodifications to the secordary contairment have violated the integrity of the pressure retaining boundary of that structure.

D.

Primary Contairment Isolation Valves 1.

'Ihe primary cxntairment isolation valves surveillance shall be performed as follows:

a.

At least once per operating cycle the operable isolaticn valves that are power cperated and a2tanatically initiated shall be tested for sinulated autanatic initiaticn and closure tirres.

b.

At least once per operating cycle the instnment lire flow ched valves shall be tested for proper cperaticn.

c.

At least cnce per quarter:

1)

All norraally cpen powervrated isolation valves (ex pt for the main stewi-line power v rated isolaticn valves) shall be fully c1ceed and reopened.

3/4 7-14 1

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o 2

LIMITDG 000ITIOi KR OPERATICN SLRVEIIIANCE: MUJIIDETr 2.

In the event any imlaticn valve specified in Table

2) With the reactor power less than 75% of 3.7.1 bea2ms ir4wtsle, reactor power cperation nay rated, trip main stean imlaticn valves continue provided at least cm valve in each line having (one at a time) and verify closure time.

m irytsle valve is in the made acquding to the i mlated condition.

d.

At least cnce per nonth, the main stean-line powervrated imlation valves shall be 3.

If Specification 3.7.D cannot be net, initiate an exercised by partial closure and

<=*mW orderly shutcbwn and have reactor in the (b1d 9ut&wn reopening.

or Refuel (bndition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

Whenever an imlation valve listed in Table 3.7.1 is operable, the position of at least one other valve in each line having an inoperable valve shall be recorded daily.

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LIMITDG GEDrrICN KR CPERATIN SLRVEIURCE RECUIRDmr 4,

If 3.a abow canrot be fulfilled, pla the reactor in g.

The fire punp diesel engine shall be demostrated Hot Standby within tle mxt 6 inurs and in Cold Shutdwi CRPABIE:

cc Refml Otniiticn within the follcwiry twnty-four (24) hours.

1.

At least cnce per 31 days by verifyirg:

(a) The fml storaje tank contaim at least 125 gallais of fuel,ard (b) 'Ihe diesel starts fran mbient omditicns and operates for at least 20 mirutes.

2.

At least or per 92 days by verifyiro that a smple of diesel fwl frun the fm1 storage tank, cbtained in acmrdance with ASIM-0270-65, is within acceptable limits specified in Table 1 of ASIM-0975-74 with respect to viscx:sity, water cmtent ard salirent.

3.

At least cnce per 18 mcnths bj:

(a) Subjectirg the aieml to an inspecticn in acardance with pooeedures pmpared in crnjunctim with its nanufacturer's reomendaticns for the class of servi and 3/4 12-3 l

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ML20138J369

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