ML20084Q477

Proposed Tech Spec Change Request 139,Rev 1,providing Revised Definition of Operable Addressing NRC Position Re Support Equipment Consideration When Determining Operability

ML20084Q477
Person / Time
Site:	Three Mile Island
Issue date:	05/11/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20084Q462	List: ML20084Q460 ML20084Q470 ML20084Q477
References
NUDOCS 8405210288
Download: ML20084Q477 (10)

Text

I I. TECHNICAL SPECIFICATION CHAPOE REQUEST (TSCR) NO.139 Rev.1 This revision replaces TSCR 139 Rev. O in its entirety.

The Licensee requests that the attached changed pages replace pages 1-2, 3-1, 3-19, 3-21, 3-22, 3-25, 3-27 and 3-43 of the TMI-l Tecnnical Specifications as amended throtgh amendment 91.

II. REASON FOR CHAtEE By letter dated December 30, 1983 tne NRC requested that GPUN propose a Technical Specification (TS) change addressing the definitions of Operaole to replace our TSCR 95 which was witndrawn. This TSCR provides a revised definition of Operaole (proposed page 1-2) whicn aodresses the NRC position that stoport equipment must ce considered when determining operaollity. In addition action requirements are specified to assure that at least one train of ESAS equipment is operable or tne unit is shutoown promptly.

III. SAFETY EVALUATION JUSTIFYING CHAtCE This TSCR is administrative in nature since it clarifies operaoility considerations ano action guidance. .

This TSCR resolves tne definitions of operable issued in a manner

, consistent with the Westinghouse standard Technical Specifications (STS).

The Westinghouse STS specify methods to confirm operability (proposed TS 3.7.2.C) of at least one system and actions to be taken (proposed TS 3.0.1) in tne event at least one success path for ESAS is unavailable.

Operating Logs document equipment operaallity in accordance with existing administrative proceduras.

Based on tne above tnere is a oeneficial effect on safety since tnere will ce more complete guicance for tne operator to follow when equipment is out of service.

IV. NO SIG4IFICANT HAZARDS CONSIDERATIONS This change is administrative in nature and serves to codify a philosophy already in use. The change represents a strengthening of requirements.

Therefore, no plant design, operation, modifications or safety analysis are involved and thus there are no significant hazards considerations.

V. IMPLEMENTATION We request- that tne amendment approving tnis TSCR oe made effective 45 days after receipt, to allow for necessary proceoural revisions to oe put in place.

VI. AMENOMENT CLASSIFICATION (10 CFR 170.22)

This TSCR is adninistrative in nature and is therefore a Class Il License Admendment subject to a fee of $1,200.00. A check for this amount was forwarded with our letter of March 28, 1984, (5211-84-2069).

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140F.- Pressura is d2 fined oy Specification 3.1.2. A rafueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemolies and/or control rods.

1.2.7 REFUELING OPERATION An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel nead is removed.

1.2.8 REFUELING INTERVAL Time between normal refuelings of tne reactor, not to exceed 24 months without prior ' approval of the NRC.

1.2.9 STARTUP The reactor shall be considered in the starttp mode when tne shutdown margin is reduced with the intent of going critical.

1.2.10 Tgyg TAVG is defined as tne arithnetic average of tne coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating if such a distinction of loops can be made. ,

1.2.11 HEATUP - COOLDOWN MODE The heatup-cooldown mode ls tne range of reactor coolant temperature greater than 2000F and less than 525oF.

1.2.12 STATION, UNIT, PLANT AND FACILITY Station, unit, plant, and facility as used in these tecnnical specifications all refer to TMI Unit 1.

1 ~. 3 OPERABLE A system, suosystem, train, component or device shall oe OPERABLE or have OPERABILITY when it is capaole of performing its specified function (s) and when all necessary attendant instrumentation, controle,; electrical power, cooling or seal water, luorication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capaole of performing their. related sy] port.

function (s) .

-1.4 FROTECTION INSTRUMENTATION LOGIC 1.4.1 D4STRUMENT CHANNEL An instrument channel is the combination of sensor, wires, aaplifiers and output devices which are connected for the purpose of measuring the value of a process variable for~ tne purpose of observation, control and/or protection. An instrumentation channel may oe either analog or digital.

1.4.2 REACTOR PROTECTION SYSTEM The reactor protection system is shown in Figures 7-1 and 7-6 of the FSAR. 'It is that combination of protection channels and associated circuitry which 1-2 i

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3. LIMITING CONDITIONS FOR OPERATION 3.0 GENERAL ACTION REQUIREENTS 3.0.1 When a Limiting Condition for Operation is not met, except as provided in action called for in the specification, within one hour action shall be initiated to place the unit in a condition in which the Specification does not apply by placing it, as applicable, in :

1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. '

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the sucsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under tne action requirements, the action may be taken in accordance with the time limits of the specification as measured from the time of failure to meet the Limiting Condition for Operation. /Wplicability of these requirements is stated in the individual Specifications.

Specification 3.0.1 is not applicaole in COLD SHUTDOWN OR REFUELING SHUT 00WN. P BASES This specification delineates tne action to be taken for circumstances not directly provided for in the action requirements of individual specifications and whose occurrence would violate tne intent of the specification.

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m 3.1 REACTOR COOLANT SYSTEM 3.1.1 . OPERATIONAL COMPONENTS

'Acolicability Applies to the cperating status of reactor coolant system components.

Objective To specify those limiting conditions for operation of reactor coolant system components which must be met to ensure' safe reactor operations.

Specification 3.1.1.1- Reactor Ccolant Pumps

a. Pump combinations permissible for given power levels shall be as shown in Specification Table 2.3.1.

b. Power operation with one idle reactor coolant pump'in each loop shall be restricted to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the reactor is not returned to an acceptable RC pump operating combination at the end of the 24-hour period, the reactor shall be in a hot shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. The baron concentration in the reactor coolant system shall not be reduced unless at least one reactor coolar.t pump or one decay heat removal pump is circulating reactor coolant.

3.1.1.2~ Steam Generator

a. Both steam generators shall be operable whenever the reactor coolant average temperature is above 2500F.

3.1.1.3 Pressurizer Safety Valves

a. The reactor shall not remain critical unless both pressurizer code safety valves are operable with a lif t setting of 2500 psig f,1%.

b. When the reactor is subcritical, at least one pressurizer code cafety valve shall be operable if all reactor coolant system openings are closed, except for hydrostatic tests in accordance with ASME Boiler and Pressure Vessel Code,Section III.

3-la Amendment No. 47 (12-22-78)

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1  ; 1.1 >'EJF AND ?UMIFICATION AITD Ch*ECCM, ADDITICN SYS~IG Ateli:abilit .-

% Applies to the operatienal status 'of the =akeup and purification and the

~ che=1:al. addition systa=s.

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Obi eetive.

To provide fer' adequate be ation under all operating cc:iitices to ass =e ability to bring the reactor to a coli shutdows ec ditie=.

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Sbecificatien -

The. reactor shall'not be critical unless, the following cc:ditic=s are =et:

3.2.1 Two makeup and purification pu=ps are operable except as specified in 3.3.2 Specification 3.0.1 applies.

-3.2.2 A source. of concentrated beric acid solutic=, in additics v to the borated water storage tank, is available a=d opera '- N s can be either:

a. The borie acid mix tank containing at least the equivale:: of

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'906 ft3 of 8700 pp: boren as boric acid sclution v'.th a te=perature of at least 100F above the crystal 11:ation te=perature. Syste=

piping a=d valves necessa:/

to establish a flow path frc= the tank j

to the =akeup and purification syste:-shall also be operable and shall have at least the sa=e te=peratee require =ent as the boric acid =ix ta=k. One associated boric acid p=p shall be' operable.

b. ~ A reclained boric acid storage t*-V centaining e. least the

equivale

it of 906 ft 3 of 8700 p,=0 boron as beric acid solution with a ta=perature of at least _10 F above the crfstalli:stics te=perature. Systes piping and valves necessary to establish a flow path frc= the ta=k to the -=Veup a=d purificetion syste=

shall also be-operable and shall have at least the sa=e te=perature One ass::iated require =4nt as the recla1=ed beric acid t d.

reclai=ed boric acid pu=p shall be operable. ,

c.- With neither the boric acid mix tank nor the reclaimed boric acid

. storage tank OPERABLE, restcre one source to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HCfr SHUPDOWN within'the next 6 hourg and borated to a SHUrDOWN MARGIN erIuivalent to 1% delta k/k at 200 F; restore a concentrated boric acid source to OIERABLE status within the next 7 days or be in COLD SHUIDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

.? ares ,

The =akeup a=d purification syste= and che= ice.1 additics syste=s provide centrol of the reacter coolant boro: concentration. (1) This is cor= ally a::c=plished by using any of the three maheup and purification pu=ps in series with a boric acid pu=p associated with the boric acid =ix tank or a reclai=ed boric acid pu=p associated vith a reclai=ed boric acid storage t* * . The alternate =ethed cf boratics vill be the use 'of the =akeup and purifier. tics pu=ps taking suction dire :17 from the berated water stcrage ta=k. (2)

Anar.imant No. 50 March 16, 1979 3-19

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- 3. 3.. L DERGE CY CORE C00 LING. REACTOR BUIIDIf"G DE2GENCY COOLING AND L- EEACTOR SUILDING S??AY SYSTE'S

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' W "' Aeolicability Applies to the operating status of the energency core cooling, reactor building e=ergency cooling, and reactor ouilding spray systems.

Objective

- i To define the conditions nece'ssary to assure immediate availability of the '

e=ergency core cooling, reactor building emergency cooling and reactor building l spray systems.

Suecification ,

3.3 1 The reactor shall not be made critical unless the following conditions are met:

'3.3.1.1 Injection Systems

a. The borated vater storage tank shall contain a mini =un of 350,000 gallons of water having a =ini=um concentyation of -

2,270 pps boren at a te=cerature not less than LO F.

Specification 3.0.1 applies.

b. Two makeup pumps are operable in the engineered safegaards mode

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powered frcm independent essential busses. Specification

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3.0.1 applies.

.Jh. c. Two decay heat removal pu=ps are operable. Specification 3.0.1 applies,

d. Two decay heat re= oval coolers and their cooling vater supplies are operable. (See Specification 3.3.1.h) Specification 3.0.1

. applies.

e. Two B'JST level instrument channels are operable.

f. The two reactor building su=p isolation valves (DHV6A/B) shall be either =anually or remote-=artaally operable.

Specification 3.0.1 applies. I 3.3.1.2 Core Floeding System 3

a. Two core flooding tanks each containing 10ho ! 30 ft of torated water at 600 + 25 taig shall be available. Specification -

3.0.1 acolies7

b. Core flooding tank boron concentration shall not be less than 2,270 pps boren.

c. The electrically operated discharge valves from the core ficed tank vill be assured open by administrative control and position indication lamps on the engineered safeguards status panel.

Respective breakers for these valves shall be open and con-spicuously marked. Specification 3.0.1. applies.

-r- d. One core flood tank pressure instru=entation channel and one core flood tank level instrumentation channel per tank shall

]( be operable.

headsent No. 21 (9-15-76) 3-21 ,

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_,;g e. Core flood tank-(CFT) vent valves CF-V3A and CF-Y33 shall be closed and the breakers to the CFT vent valve retor operators shall be tagged open, except when ad.justinc core f lood tank level and/or pressure Specification 3.0.1 applies. l 3.3.1.3 Reactor Buildine Soray System and Reactor Buildine Emeroency Cooline System ,

The f ollowing cernpenents must be operable:

a. -Two reactor building spray pu::ps and their associated spray nozzles headers and two reacter building emergency cooling f ans and associatec cooling units (one in each train). Specification 3.0.1 applies. l

b. The sodium hydroxide (NaOH) tank level shall be maintained at G feet + 6 inches lower than the BWST level as measured by the BWST/NaOH tank diff' eren*:ial pressure indicator. The NaOH . tank concentration shall be 10.0 + .5 weight percent (%).

c. All manual valves in the discharge lines of the

- sodium bydroxide tank shalI be locked ope'n.

3. 3.1. l. Cooline Water Systems Specification 3.0.1 applies. l

) . a. Two nuclear service closed cycle cooling wate pumps must be operable.

b. .Two nuclea service river wate pumps must be operacle.

c. Two cecay heat closee cycle cooling water pumps must be operacle.

d. Two de:ay heat river water pumps must be operable.

e. Two reacter building emergency cooling rive wat'er pumps must be operable.

3.3.1.5 Engineered Safeguards Valves and Interlocks Associated .itn' ene Systems in specifications 3.3.1.1, 3.3.1.2, 3.3.1.3, 3.3.1.4 are

. operat ie . Specification 3.0.1 applies . l 3.3.2 Maintenance shall be allowed during power operatian on any component (s) in the makeup and purif ication, cecay heat, R3 emergency -

cooling water, RB spray, CFT pressure instrumentation, CFT level instrumentation, SWST level instrumentation, or cooling wate systems which will not remove more than one train of esca system from service.

Components shall not be removed from servi,ce so that the af f ectec system train is Inoperable for more tnan 72 consecutive hours. If the system is not restored to meet the requirements of Specifications 3.3.1 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be placed in a cold shutdown

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condition within twelve hours. .

A:nndment No. 3), 80 3-22

s 3.4 DECAY HEAT REMOVAL' -!: TUR3INE' CYCLE.

Applicability

.nq? Applies to the operating status of equipment thac functio'is to remove decay heat, utilizing the secondary side of the Steam Generators.

Objective Ta define the conditions 2ecessary to asse're immediate availability of the "

• Imergency Teedvater (IT4) Systa= and Main Stea= Safety Valves.

Soecification M 4.1 Vith the Acactor Coolan: Syste= temperature greater than 250*T, three independent IT' pu=ps and associated flow paths

• sna11 be OPII.,JC.I .

with:

an OPIRA3LI

a. Two ITJ pu=ps, each capable of being powered fro: i amergency bus, and one IFb' pu=p capable of being powered fro =.an l OPuiXI s esa= supply syste=. Specification 3.0.1 applies.

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b. With one pu=p oi flow path

• inoperable, restore the inoperable pu=p l or flow path to OPIRA31I status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD -

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SEL'*D0kT vithin the nex: 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With mo're than one ITk' pt p or flow path

• inoperable, restore the inoperable pt.~._ps or flow paths

• to OPERA 3LE sta:us or be suberitical vi:hin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, in at least E07 e

SELTD0kT vithin the nex: 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SEi.'IDok7 within the s

/ fc11ovins 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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c. Toc of six turbine bypass valves are OPERA 3LI.

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d. The condensa:e storage tanks (CST) shall be OPIE 13LI vich With a mini =t:=

a CST of 150,000 gallons of condensate available in each CST.

inoperable, restore the CST to operability within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in a: leas: EDT SELwok3 vithin the nex: 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and COLD SEUID0kT With more than one CSI inoperable, within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

restore the inoperable CST to ,0PERA3LE status or be suberitical within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, in a: leas:

ECT Shcwok5 within the nex 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,  ;

Specification ,

and in COLD SELTDokT vi:hin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. '

j 3.0.1 applies.  !

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For 'the purpose of this require =ent, an OPIRA3LI flow p'ath shan mean '

an unohstructed path fro = the water source to the pu=p and frc= the pu=p to a steam generator  !

NA) ,

Amendment No. #.78 3-25 i

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r 3 5~ INSTRUC"TATION SYS*D'.S .

351 OPnATIoxAL sATITY InsnUKmTATIon

( Anelicability

- Applies to u=it instrumentation and control syste=s.

Objective ,

To delineate the conditions of the unit instru=entatio'n and safety circuits

. necessary to assure reactor; safety.

Suecifications 3 5 1.1 The reactor shall not be in a startup mode or in a critical state

' A' and '3' are met.

unless the re3.u 0.1

. Specification ire =ents, of Table 3 5-1. Col, -

applies. .l 3 5 1.2 For on-line testing or in the event of a p'retection instrument or channel failure, a key operated channel bypass svitch associated with each reactor protection channel vin be used to lock the reactor trip module in the untripped state as indicated by a light. only one channel shall be locked in this u= tripped state at any one time. Unit operation at rated power shall be per=itted to continue with Table, 3 5-1, colu=n "A". only one channel bypass key shan be kept in the control room.

3 5.1.3 In the event the number of protection channels operable Yans belov c

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f the IMt given under Table 3 5-1, Colu=n "A", operation shall be li=ited as specified in Colu=n "C". Specification 3.0.1 applies. l

! 3 5 1.k The key operated shutdom bypass svitch associated with each reactor

' protection channel shan not be used during reactor " pover operation (except for required maintenance or testing) .

3515 .During startup when the intermediate range instru=ents come on seale, the overlap betveen the intermediate range and the source range

, instru=entation shan not be less than one decade.

1 3 5 1.6 In the event that one of the trip devi:es in either of the sources supplying power t.o t.he control rod drive mechanis=s fails in the -

untripped state, the power supplied to the roi drive mechanisms through the f ailed trip device shall be manually re=oved within 30 The re=aining trip device minutes. The condition vin be corrected.

shall be tested within eight hours. If the condit. ion is not corrected i

and the remaining trip devices are not, tested within the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> -

period, the reactor shan be placed in the het shutdovn condition.

within an additional k hours.

! 3ases g Every reasonable effort vill be made to maintain au safety instr.=nentation in operation. A startup is not per=it,ted unless three pover range neutron instru-7,),

nent channels and t.vo channels each of the fonoving are operable: four Amendment No. 62 3-27 2-11-31

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for any reason, reactor operation is permissible for the succeeding seven days provided that during such seven days the operable diesel generator is tested immediately and daily, In the event two diesel generators are inoperable, the unit shall be placed in hot shutdown for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If one diesel is not operable within an additional 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period tne plant shall ce placed in cold shutdown within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter.

With one diesel generator inoperaole, in addition to the aoove, verify that: All required systems, subsystems, trains, components and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are also OPERA 8LE oI follow specifications 3.0.1.

d.- If one Unit Auxiliary Transformer is inoperable and a 4160 volt tie from mit 2 transformer cannot be placed in service and a diesel generator becomes inoperable, the unit will be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If one of the above sources of power is not made operable within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the unit shall be placed in cold shutdown within an aoditional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter. .

e. If Unit 1 is separcted from the system while carrying its own auxiliaries, or if only one 230 kv line is in service, continued reactor operation is permissible provided one emergency diesel generator shall be started and run continuously until two transmission lines are restored.

f. The engineered safeguards electrical cus, switchgear, load shedding, and automatic diesel start systems shall be operable except as provided in Specification 3.7.2c above and as required for testing.

g. One station battery may be removed from service for not more than eight hours BASES The Unit Electrical Power System is designed to provide a reliable source of power for balance of plant auxiliaries and a continuously availaole power supply for the engineered safeguards equipment. The availability of the various components of the Wit Electric Power System dictates the permissiale mode of station operation Operating Logs document equipment operability in accordance with existing l - adninistrative procedures.

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