ML18005A797

Proposed Tech Specs Re Refueling Operations Water Level

ML18005A797
Person / Time
Site:	Harris
Issue date:	02/22/1989
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18005A795	List: ML18005A793 ML18005A797
References
NUDOCS 8902280499
Download: ML18005A797 (3)

Text

ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT REFUELING OPERATIONS - LOW WATER LEVEL TECHNICAL SPECIFICATION PAGES 89'0~804'P9'90222 PDR ADOCK 05000400 P PDC

W REFUELING OP" RATIONS LOW WA)ER L )))EL LIMITING CONDITiON FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OP RABLE, and at least one RHR loop shall be in operation."

APPLICABILITY: MODE 6, with irradiated fuel in the vessel when the water level above the top of the reactor vessel flange is less than 23 feet.

ACTION:

a0 With less than the required RHR loops OPERABL, immediately ini ia'te corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reac or 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 o return the required RHR loop to operation. Close all containment penetra ions providing.

direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4

4.9.8.2,I At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hour~ uhe~evei We ~agan l~vg is at'or above'~ R<+<+i J .

g jh&f& ~

o~e R H < i~op gpss l I ~c Pea)Cad ia iope~akiow 9 9 F Z 2, P+ )ewsT" cod /8~ 8 84 /e.~s,W once @cia

~"e" e e~ We cui)~m (eve.l is kelo~) i Ae gectc+m v'essej 4'/~uge,

."The operating RHR loop may be removed ,rom operat',on for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 2-hour period during the performance of CORE ALTERATIONS and core loading verifica.ion in the vicinity of the reac or vessel hot legs.

SHEARON HARRIS - UNIT 1 3/4 9-10

RE;UELING OPERATIONS SAS=S 3/4. 9. 6 R"FUELING MACHINE The OPERABILITY requirement0 for the refueling machine ensure that: (1) refuel-ing machine will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficien load capaci y .o lif a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protec ed from excessive lif ions.

ing force in the event .hey are inadvertently engaged during lif.ing opera 3/4.9.7 CRANE TRAVEL " FUEI HANDLING BUILDING The res ric ion on movement of loads in excess of he nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped: (' the.

activity release will be limited to that con ained in a single fuel assembly, and (2) any possible dis ortion of fuel in the s orage 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 leas one residual heat removal (RHR) loop be in opera-ion ensures that: (1) sufficient cooling capaci y is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolan circulation is mainwined througn the core to minimize the effect of a boron dilution inciden and prevent boron s ratifica ion.

The requirement to have two RHR loops OPERABLE when there is less han 23 feet of water above the reactor vessel flange ensures that a singlw failure of he opera ing RHR loop will not result in a complete loss of residual heat removal capability Mith the reactor vessel head removed and at least 23 feet of water aoove t e reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event o, a failure of he operating RHR loop, ade-qua e time is provided to initiate emergency procedures to cool the core.

3/4. 9. 9 CONTAINMENT VENTILATION ISOLATION SYS7=1 The OPERABILITY of this sys em ensures that the can ainment purge makeup and exhaus- penetrations will be automatically isolated upon detec.ion of high .

radiation levels wi hin the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the con ainment atmosphere to the environment.

@he 4c4 o4 ~ 5p8'c4ieJ m'~.'muM pfn<J Qi~, ~~+<

g H p pc.~s w4 +"use ~d'ei t'ai'e.ls w Qeco~gi~s+4+ Sod~~ S,k~+i4i'ca+lou is ~o+ a co~~u A~

SHEARON HARRIS - UNIT 1 B 3/4 9-2