ML19320B323

LER 80-030/03L-0:on 800604,while Performing Leakage Test, Discovered That Loop 2 Steam Generator Penetration Leakage Exceeded Allowable Limit.Cause Unknown.Temporary Relief from Allowable Limit Received from NRC

ML19320B323
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/02/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19320B321	List: ML19320B320 ML19320B323
References
LER-80-030-03L, LER-80-30-3L, NUDOCS 8007100176
Download: ML19320B323 (1)

Text

NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION ml7 77) ,

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CATE l EVENT DESCRIPTION AND PROB ABLE CONSEOUENCES  ;

I o 12 ( l On June 4, 1980, during normal power operation while nerforming SR 5. 2.16a-m, Loop 2 l .

I o 13 l [ steam generator penetration leakage apoeared to be greater than the 400 pounds oer davl I o i 4 I l limit o f LCO 4.2.9. Further testing revealed the leakage was less then 400 counds cer!

I o 15 l t day and appeared to be internal to the steam eenerator not through the seals. No l 1o is l I similar reportable occurrences. There was no affect on public health or safetv. Re- 1 I o 17 l Lportable per AC 7.5.2(b) 2. I l

l o is t i 80 a 7 3 9 SYSTEU CAUSE CAUSE COVP. VA LV E CCCE C00E SUSCCOE CCM*CNENT CODE StsC00E SLeCOCE 10191 7 8 i aI al@ lx l@ 12 l@ l al Tl El Xl Cl Hlh l Fl@ l Zl@

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,i j o l l Cause of the interspace leakaze is not known at this time. Temocrarv relief from the l lijijiLCO limit of 400 pounds per day was recuested and received from the NRC. The eroblem I i, ,7, l will be investigated and repairs made as recuired durinz the next refueline shutdown. l ,

j, j3l l Results will be submitted in a future supplemental recert7 l 11 141 l I l 80 i 7 6 3 S $  % POWER OTwER STATUS IS RY D'SCOVERY CESCRI87?ON l1 { s l l E l@ l 0l 6l 7l@lnN/A l l Bl@l Regular Scheduled Surveillance l

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