ML20093E172

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Proposed Tech Spec Changes,Providing Addl Restriction on Plant Operation During Limiting Condition for Operation W/ One Recirculation Loop Out of Svc
ML20093E172
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/12/1984
From:
GEORGIA POWER CO.
To:
Shared Package
ML20093E170 List:
References
TAC-55530, NUDOCS 8407170398
Download: ML20093E172 (4)


Text

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3/4.4 RFACTOR COOLANT SYSTBI 3/4.4.1 REC 1RCUIATION SYSTIM FFC1RCULAT10N LOOPS LIMITING CONDITION FOR OFFFATION 3.4.1.1 1ko reactor coolant recirculation loops shall be in operation with each recirculation pump operating and the pump discharge valves OFFRAPLE.

APPLICABIL11Y: C0hT;IT10NS la and 2*.

ACTION:

a. With one recirculation loop not in operation, initiate action within 15 minutes and continue action to reduce reactor power to or below the limit specified in Figure 3.4.1.1-1 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and restore bcth loops to operation within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or te in at least it0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b. With no recirculation loops in operatien, place the reactor rede shitch in the Shutdown position.

SURVE1LIANCF RFQUIREMFhTS 4.4.1.1 Each pump discharge valve shall be demonstrated 0FFRAELE by cycling each valve through at least one complete cycle of full travel:

a. Each startup** prior to VITWAL POWIR exceeding 25% of RATFD BlIRPAL PCWER, and
b. During each COLD SHlTTLCWN which exceeds de hours,**

I a see special Test Exception 3.10.4.

    • 1f not performed within the previous 31 days.

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    • NI'rACIMNP 2 NIC DOCKER 50-366 OPERATING LICENSE NPF-5 EIWIN I. IINICII NUCIEAR PIANT UNIT 2 RBOUES'r EUR TIDINICAL SPirIFICATION AENDMlWP

'IU SUPIOffr OPEleTION IN ' lith ELIA 10X110N Furalant to 10 CFR 170.22, Georgia Power Conpany han evaluated the attached proposed amerriment to Operatirvj Licenno NPP-5, and han determined thats

a. The propoccd amendment does not regtire evaluation of a new Safety Analysis Ieport and rewrite of the facility licenses
b. The proposed ameruiment does not regiire evaluation of several ceraplex inatos, involvo ACici review, or re<pire an environmental inpact statanent; *
c. 'Ito proposed amorriment does not involvo a conplex innio or more than one environmental or cafety inato;
d. The proposed amerviment doco involvo a nirvjle cafety istuo, namely that plant operatiuru be restricted at or below the limit shown in

'Ibchnical Specification Firpro 3.4.1.1-1 within 2 hairs af ter the loan of operability of either reciro21ation loop.

e. Tin proposed amerviment in thorofore a claco III amerriment.

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. .* j ATrA09ENr 3 NRC D00TP 50-366 OPERATING LICENSE NPP-5 ELWIN I. HA'IGI NUCIEAR PIAITF UNIT 2  !

REQUEST POR TIGNICAL SPECIFICATION M9:ND>fNr

'IO SUFIORP OPERATION IN '!HE ELIA I@XIION '

'the following is a listing of the gecific 'Itchnical Specification t revision regaested ty this sutnittal and the basis for consideration of the change as not involving a significant hazard as described in 10 CFR 50.92:  ;

Replace "... operation may contirues..." with "... initiate action within 15 mirutes and contirue action to redice reactor power to or below the limit gecified in Figure 3.4.1.1-1 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> arsl..." in ACTION 3.4.1.1.a, and add Figure 3.4.1.1-1 as a new page (3/4 4-la) . j BASIS: i

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' Itis chame unld restrict plant operation to the region at or below the limit shown in Technical Specification Figure 3.4.1.1-1, within 2 tairs after either recirculation loop is declared inoperable. That limit corresponds to a load line leading to 80% reactor power at rated core flow. 'this constitutes an additional restriction not presently in tlw

'Iwchnical Specifications; therefore, this proposed change is consistent with Item (ii) of the "Exanples of Amerviments that are Considered Not i Likely to Involve Significant Hazards Considerations" listed on pge l 14,870 of the April 6,1983, isale of the Federal IMgister.  ;

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