05000324/LER-1980-111-03, /03L-0:on 801210,12 & 18,reactor Coolant Activity Exceeded Tech Specs.Caused by Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element

/03L-0:on 801210,12 & 18,reactor Coolant Activity Exceeded Tech Specs.Caused by Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element

ML19351F609
Person / Time
Site:	Brunswick
Issue date:	01/07/1981
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19351F604	List: 05000324/LER-1980-111, Forwards LER 80-111/03L-0 05000324/LER-1980-111-03, /03L-0:on 801210,12 & 18,reactor Coolant Activity Exceeded Tech Specs.Caused by Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element
References
LER-80-111-03L, LER-80-111-3L, NUDOCS 8101130568
Download: ML19351F609 (3)

LER-1980-111, /03L-0:on 801210,12 & 18,reactor Coolant Activity Exceeded Tech Specs.Caused by Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element

Event date:
Report date:
3241980111R03 - NRC Website

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lTITI l on Deca-har o - loco Un i e % - 1 was shutdeun for acheduled maineansnra a ITTTI I approximately 2 weeks of high power operation. During plant shutdown on December 10.l lO 4; l 1980 and again during 2 subsequent reactor startups on December 12 and 18. the l

reactor coolant activity exceeded the technical specifications limit of 0.2 uCi/gm i

lO;5l l 131 O s l1 dose equivalent for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with the highest recorded activities at 0.2276.

I l 0.3280 and 0.2020 uCi/gm respectively.

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M.J. PASTVA. JR.

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NAME OF PREPARER

LER ATTACHMENT - RO #2-80-111 Facility: BSEP Unit No. 2 Event Date: 12-10-80 A si:nilar event involving coolant activity was reported in LER 2-80-82.

To help eliminate future similar occurrences, the Unit No. 2 fuel bundles will be sipped during the next refueling outage and the leaking bundles. removed from the core.

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OFF-GAS ANALYSIS Prior to this incident, the following Unit No. 2 Steam Jet Air Ejector (SJAE) off-gas level was measured:

Date Reactor Power, %

off-Gas uCi/see at SJAE 12-5-80 99.4 2.65257 E4 Following this incident, the following Unit No. 2 Steam Jet Air Ejector

• 3 (SJAE) off-gas level was measured:

Date Reactor Power, %

Off-Cas uCi/see at SJAE 3

1-6-81 82.4 3.547 E e

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