05000324/LER-1981-081-03, /03L-0:on 810804,following Reactor Scram W/Group I Isolation,Safety Relief Valve F013B Opened to Control Reactor Pressure Resulting in Average Torus Temp Exceeding 120 F.Cause Not Stated.Temp Reduced

/03L-0:on 810804,following Reactor Scram W/Group I Isolation,Safety Relief Valve F013B Opened to Control Reactor Pressure Resulting in Average Torus Temp Exceeding 120 F.Cause Not Stated.Temp Reduced

ML20010E819
Person / Time
Site:	Brunswick
Issue date:	08/25/1981
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010E816	List: 05000324/LER-1981-081, Forwards LER 81-081/03L-0 05000324/LER-1981-081-03, /03L-0:on 810804,following Reactor Scram W/Group I Isolation,Safety Relief Valve F013B Opened to Control Reactor Pressure Resulting in Average Torus Temp Exceeding 120 F.Cause Not Stated.Temp Reduced
References
LER-81-081-03L, LER-81-81-3L, NUDOCS 8109080289
Download: ML20010E819 (2)

LER-1981-081, /03L-0:on 810804,following Reactor Scram W/Group I Isolation,Safety Relief Valve F013B Opened to Control Reactor Pressure Resulting in Average Torus Temp Exceeding 120 F.Cause Not Stated.Temp Reduced

Event date:
Report date:
3241981081R03 - NRC Website

text

.. SC FORM.366 U. S. NUCLE AR REGULATORY COMMISSION W77),..

f LICENSEE EVENT REPORT CONTROL BLOCK: l l

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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lO12l lFollowing a reactor scram with a Group I isolation, automatic initiation of HPCI and l

l 0 l a l l RCIC, and a stuck open. safety-relief valve F013B (reported in T ER 2-81-76), the l

g l average torus temperature exceeded 1200F.

During this event, the maximum torus l

1o Isl l temperature was 122.1 F.

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l l o 171 1 This event did not affect the health and safety of the public.

l Technical Specifications 3.6.2.1, 6.9.1.9b l

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2 l due to a problem with its service water which is being reported in LER 2-81-73 l

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M. J. Pastva, Jr.

P40NE:

NAME OF PREPARER

s LER 2-81-81 ATTACHMENT Facility: BSEP Unit No. 2 Date: August 4, 1981 At 2009 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.644245e-4 months <br />, approximately twenty minutes following a reactor scram with a Group I isolation, safety relief valve F013B was opened at 1040/l to control teactor pressure. At 900#, an attempt was made to shut the F013B, however, the valve would not close. At 2014 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.66327e-4 months <br />, the B loop of RHR was placed in torus cooling at a temperature of 95 F and the safety relief valve still discharging.

At 2016 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.67088e-4 months <br />, IIPCI and RCIC were started to control vessel level which admitted litional steam to the torus. At 2020, the safety relief valve reset itself

,.id closed at 325#.

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