ML19332F241

Proposed Revised Tech Specs 3.4.1.4.2,3.5.4,4.9.8.1 & 4.9.8.2 Re RHR Flow Rate & Safety Injection Pump Availability

ML19332F241
Person / Time
Site:	Wolf Creek
Issue date:	11/30/1989
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML19332F185	List: ML19332F184 ML19332F241
References
NUDOCS 8912140123
Download: ML19332F241 (9)

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m ATTACIMENT III 1< 7 3, PROPOSED TECIINICAL SPECIFICATION CHI M ES-l2 i i - t 3

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     . ,7        l-I L At 'tachriient' III to WM 89-0264_                  <
   '( LPage;i: of 8~                                                                                        .

f REFUELING OPERATIONS

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3/4.9.8 RESIOUAL HEAT REl10 VAL AND COOLANT CIRCULATION HIGH WATER LEVEL g LIMITING CONDITION FOR OPERATION i y. 3.9.8.1 At least one residual heat removal (RHR) loop shall be OPERABLE and

in operation.*

1 APPLICABILITY: MODE 6 when the water level above the top of the reactor vessel flange is greater than or equal to'23 feet. t ACTION: With no RHR loop OPERABLE and in operation, suspend all- operations involving an increase in the reactor decay heat load or' a reduction in boron concentra-tion of the Reactor Coolant System and immediately initiate corrective action tg return the required RHR loop to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours.

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SURVEILLANCE REQUIREMENTS 4.9.8.1 At leest one R: R loop sh-li bc verified ir Operation cM circukting rcactcr cocisr.t et e fle.i retc of grcatcr then er cqual to 2000 ;;a at leest l' ence per 12~ hours. At least once per twelve hours, one RHR loop shall be verified in operation and circulating coolant at a flow rate of: a) greater than or equal to 1000gpm, and

                                                                                                                -l b) sufficient to maintain the RCS temperature at less than or equal to 140"F "The RHR loop may be removed f rom operat ion for up to I hour p        -hour period curing the. performance of CORE At 11 RAll0HS in t he vic ini t ; c.     ..a c t v vessel not legs.

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 !~.  . l Page Attachment 2 of 8- 111 to WMl89-0264               ,                                                -

e A 3 REFUELING OPERATIONS

,                      LOW WATER LEVEL
                                                                                                                     -t LIMITING CONDITION FOR OPERATION ll 3.9.8.2                                                                                          ..

and at k. Two independent residual heat removal (RHR) loops shall be OPERABLE, east one RHR loop shall be in operation." APPLICABILITY: MODE 6 when the water level above the top of the reactor vessel flange is less than 23 feet, i ACT. ION: a. With less than the required RHR loops OPERABLE, immediately initiate

• corrective action to return the required RHR loops to OPERABLE status, or to establish greater than or equal to 23 feet of water L above the reactor vessel flange, as soon as possible.

b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. direct access from the containment atmosphere to the outsideClose ( atmosphere within 4 hours. SURVEILLANCE REQUIREMENTS 4.9.8.2 rec ter cochnt St ic=tatone M4eop a ficw rat shel' be scrified-4n-opeeation cnd c4wk: ting cacs par 12 h0ers. cf grcetar than er equal tc 2000 ga st leest At,least once per twelve hours, one RHR loop shall be verified in operation and circulating coolant at a flow rate of : a). greater -than or equal to 1000 gpm, and b) 7 7 7

• sufficient h to maintain the RCS temperature at less than or equal to 140 r -

                  ,,rior to initial criticality, the RHR loop may be removed f rom x.: ation for uo to.1 hour per 2-hour period during the performance of CORE M.TUU!O: 15 in
                   *ne vicinity of the reactor vessel hot legs.

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      " UAttachment IIItto WM 89-0264 4 -Page 3 of_8

{ REACTOR COOLANT SYSTEM (- COLD SHUTDOWN -~ LOOPS NOT FILLED - U LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE # and at least one RHR loop shall be in operation.* APPLICABILITY: MODE 5 with Reactor Coolant loops not filled. ACTION: a. With less than the~above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible, b. With no RHR loop in operation, suspend all operations involving a i reduction in boron concentration of the Rdactor Coolant System and ' immediately initiate corrective action to return the required RHR loop to operation.

                 . SURVEILLANCE REQUIREMENTS
                                                                                                 '(

d 4.4.1.4.2 At least one RHR loop shall be determined to be in operation and d circulating reactor coolant at least once per 12 hours, i

                #0ne RHR loop may be inoperable for up to 2 hours for surveillance testing
                 -provided the other RHR loop is OPERABLE and in operation.
                *The RHR pump may be deenergized for up to 1 hour provided: (1) no operations            1 are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2)-core outlet temperature is maintained at least 10 F              l below saturation temperature w~~

and (3) vessel the reactor flange. vessel water levelj is above the ,

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l' WOLI CREEP UNil 1 3/4 4-6 l .

p, .. s, E . ,19ttpchinent 111 to-WM 89-0264 , f 'l p .- Page;4Lof,8 - f EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 ECCS SUBSYSTEMS - T < 200'F avo _LINITING CONDITION FOR OPERATION 3.5.4 All Safety Infection pumps shall be inoperable. APPLICABILITY: NO{ 0 end M000 0 with the reecter vessel head car i ACTION: 3 ,. i I With a Safety Injection pump OPERABLE, restore all Safety Injection pumps to an inoperable status within 4 hours. SURVEILLANCE REQUIREMENTS 4.5.4 All Safety Injection pumps shall be demonstrated inoperable

• by

(. verifying that the motor circuit breakers are secured in the open position I at least once per 31 days. h ' 9 the top of the Reactor Vessel flange, and

                          -MODE 6 with the Reactor Vessel head on and with the water level above the. top of the Reactor Vessel flange.

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                        *An inoperable purnp may be energized ior testinq or ior fil1in: crumulator, provid"d the disch,irge at Llui pump h.U. he"o isolated from t h.-         by a i l o ,.

,olation valve with power removed f r om tin- v.t i ve ope ra ti: .i 6 :.inu a !

1,olat, son valve *otored in t f u c lusori po , i t io i b'Ol I CPIl K Util i l 1/ /; *, y

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 . -     .NtachmentIIItoWM 89-0264                    ,        -

Page 5 of 8 ' EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

                         ----T     imitation for a maximum of one centrifugal charging pump to b                                                      -

and the Survei. nt to verify all chargin ety Injec-tion pumps except the require ' o be inoperable in MODES 4 and 5 and in MODE 6 with tha -__. vessel inwvi

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ssurance that a mass a'ddit m.; y.e~TrEstent can be relieved by the opera HR suction relief valve. INSERT A , The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITf is maintained. Surveillance Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, , (2) rirovide the proper flow split between injection points in accordance with l the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable I level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. The Surveillance Requirements for leakage testing of ECCS check valves ensures that a failure of one valve will not cause an intersystem LOCA. The Surveillance Requiren.ents to vent the ECCS pump casings ,

   ,a                and , accessible, i.e.i can be reached without personnel hazard or high radiation f                 dose, discharge piping ensures against inoperable pumps caused by gas binding                                                          (

e or water hammer in ECCS piping. 1 . 3/4.5.S REFUELING WATER STORAGE TANK The OP$RABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits. on RWST minimum volume and boron concentration ensure that: (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes assuming all the control rods are out of the core. These assumptions l are consistent with the LOCA analyses. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment af ter a LOCA. This pH band minimizes the evolution of iodine and minimizes the ef fect of chloride and caustic stress corrosion on mechanica l systems and components. W>ll CRf:K UN!! l B 1/4 5 ? , w.t E

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       ... Attachment III to WM 89-0264 Mr,. Page 6 Of 8                                                                                                   ;

l J 1 INSERT A l-l The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirements to verify all charging pumps except the  ! ! required OPERABLE charging pump to be inoperable in MODES 4 and 5 and in i MODE 6 with the reactor vessel head on, provides assurance that a mess addition pressure transient can be relieved by the operation of a single PORV or,RHR suction relief valve. In addition, the requirement to verify all Safety Injection pumps to be inoperable in MODE 4 in MODE 5 with the water level above the top of the reactor vessel flange, and in MODE 6 with the reactor vessel head on and with water level above the top of the reactor vessel flange, provides assurance that the mass addition can be relieved by a single PORV or RHR suction relief valve. With the water level not above the top of the reactor vessel flange and with' the vessel head on, Safety Injection pumps may be available to mitigate the ' affects of a loss of decay heat removal during a reduced RCS intentory condition. 1 l l L

MAttachment Ill to WM 89-0264 , .-* e Rage 7 of 8 '

      ,                       REFUELING OPERATIONS BASES

,- (, 3 /4. 9. 6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine and auxiliary hoist ensure that: (1) manipulator cranes will be used for uovement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. ' 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool areas ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in a r, ingle fuel assembly, and (2) any possible distortion of fuel in the storage racks will.not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses. 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that: (1) sufficient cooling capacity is available to remove I decay heat and maintain the water in the reactor vessel below 140'F as required during the FJ. FUELING MODE, and (2) sufficient coolant circulation is maintained through the core,ta minimize the.cL( of a boron dilution incident and prevent boron stratification.- INSERT B The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of RHR capability. With the reactor vessel head removed and at least 23 feet of water above the J reactor vessel flange, a large heat sink is available for core cooling. Thus, L in the event of a f ailure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

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3/4. 9. 9 CONTAINMENT VENTILAT10N' SYSTEM The OPERABILITY of this system ensures that the containment Durge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABilllY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment. Klf CRl!T - UNII 1 0 3/4 9-2 f 1 J, ,p ,,,s.. _...s.. > =- ' = ' ' " ' ' " ' ' ' ' '

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         .AttachmentIIItoWM 89-0264        ,    ,

_ Page C-7 8 - n. f usar n , i,- The minimum of 1000 gpm allows flow rates which provide additional margin f against vortexing at the RER pump suction while in a reduced RCS inventory condition. i m.. -_}}