ML19241A694

LER 79-013/01T-0 on 790613:main Steam Relief Valve RV3-2-71L Lifted,Causing Torus Water Vol to Exceed Tech Spec Limit by 2.6%.Reactor Manually Scrammed.Valve Replaced & Sent to Wiley Lab to Determine Cause for Failure

ML19241A694
Person / Time
Site:	Peach Bottom
Issue date:	06/27/1979
From:	Cooney H, Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19241A692	List: ML19241A691 ML19241A694
References
LER-79-013-01T, LER-79-13-1T, NUDOCS 7907090298
Download: ML19241A694 (2)

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LVLNT DEbCH PTION A OPRo0A C NSL ENCES oi/ l With Unit 3 operating at 95% power, main ateam relief valve RV3-2-71L i ni i ] lifted caucing torus water volume to reach 130, 675 cu ft., 2. G above j o 4 l Tech Spoc limit of 127,300 cu. ft. Reactor cool-down rate reached 11h0p  ;

ois l in one hour,1h- above Tech Spec limit of 100 0F per hour. The reactor j toj i was tr.nually acr,med before the torus temperature reached 1100 F in j oi, i acco2 dance with procedure and =ax cool-down rate was below the design j a a! i limit, therefore the consequences were minimal, 7 a 9 W

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44 .g f cAUSE DESCalPTioN AND CORRECTIVE ACTIONS h liio;1 The cause of the occurrence was the lifting of relief valve H7-71L. l titc l The relief valve was replaced and sent to Wiley Lab to determine the j] [ reason for lifting. A visual inspection of the d /well and torua  !

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NAME GF PREPAHER s [p3- ,' C h'/ ..) yl. J. Cooney PnONE.

(215) 841-5020 lo J WA