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3 VrhJtxzA Er.ncruzc Ann Pownn CvJrA:n RicuMonn.V norn A nanot September 29, 1976 Mr. Norman C. Moseley, Director Serial No. 264 Office of Inspection and Enforcement PO&f/ALH:jlf i
U. S. Nuclear Regulatory Conxnission Region II - Suite 818 Docket No. 50-281 230 Peachtree Street, Northwest License No. DPR-37 Atlanta, Georgia 30303
Dear Mr. Moseley:
Pursuant to Surry Power Station Technical Specification 6.6.2, the i
Virginia Electric and Power Company hereby subnits a copy of Licensee Event Report No. A0-S2-76-05.
I The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Committee.
Very truly yours,
[
C. M. Stallings Vice President-Power Supply
~
and Production Operations Enclosure cc:
Mr. Robert L Reid, Chief (40 copies)
Operating Reactors Branch 4 i
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SCHLISS82-534 PDR I
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l (PLEAM PRINT ALL RECulHED INFCRMATIO 1
6 L Cf NSIE E CE NSE EYINI NAME ECENSE NUV8E A TVPE TYPE Iv h I sl els 12 l 10101-10101010101-10_l 01 141111111 Ol 1011 1 Oi 7 89 14 15 25 26 30 31 32
" ' f NN coCxt? NuMBEA EvtNT oArt nEront oATE C ATE Gony vp
- 01 CONT l P l O !
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[1_, j l0 l 5 l 0 l-l 0 l 2l 8l 1l l 0 l-9 l 1 I s l 7 l 6 l ln I ol? l7 l7lA_f 7 8 57 58 59 GO 61 68 69 74 75 00:
EVENT DESCRIPTION BE ! During normal operation the pre'ssurizer level fell below the 457. level set point. This}
80-7 89 h lresulted in a decrease in pressurizer pressure and a decrease in the volume control 80 7 89 EE l tank level. These events indicated a leak rate in excess of 10 nom from an unidenti-l 80 7' 89l f f nei source. A reactor trio was manually initiated oer Emergenev Procedurn E4 (Time-l 80 7-89 HG l 1345). A manual safety iniection followed the manual tric per Emereenev Proce<*ure (Cond 80 7 89 Pswt M
i R
YOLATON CE CODE COMPONENT CODE
.O lNlal Lv_I lxlxlxlxlxlx1 LnJ lwl1l2l0l ly_]
7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION O
l Steam Generator "A" of Unit 2 was isolated via Phase I isolation and a leak rate in b
80 7 89 O
l excess of 10gpm was confirmed (9/15/76) (Time:
1400).Operationcpersonnelproceeded'l 80
- 7 89
@ l to bring the reactor to a cold shutdown condition. The ~ tube leak was visually (Con't) l A us'
% POWER OTHER STATUS DSCOVERY DrSCOVERY DESCRIPTON 5:W l1l 0l 0l l N/A l
[A_l l Operational Event._
l 1
7 8 9
10 12 13 44 45 46 80, ELIASEl l
1N/A l:
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LOCATOk CF AELEEE.
AMOUNT OF ACTMTV A LE S o
3
[_Zj
[Z_j N/A 7 8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCAsPTON 1
l0l0l0l (Z_j l N/A l
SM 7 89 11 12 13 PERSONNEL INJURIES NUMDER DESCRIPTON ll l0l0l0l l
N/A
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7 89 11 12 B@
OFFSITE CONSEOUENCES l
8 l N/A BM 7 89 LOSS OR DAMAGE TO FAC1tlTY T Y PE DE SC AfPTON l
D2 (L_j l N/A B@
7 89 10 z
PUBUCITY
/
Ml N/A l
8@
7 89 ADDITIONAL FACTORS
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@ lSince the reactor was brought to a cold shutdown condition af ter the _ d t,cctiort of the l 7
y B@
7 89 I i @ l leak and the major portion of the gaseous activity from the af f'elcitor was (continuedi 89 l7 89
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't ENENT DESCRIPTION (con' t) s 1
- 4. This event is reportabic per Technical Specification 3.1.C.4. (AO-S2-76-05).
i CAUSE DESCRIPTION (con't) confirmed in steam generator "A", Row 1 and CoIumn 7, (Sept. 17, 1976,' Time: 1711).
Corrective measures have been started to evaluate the cause of the tube failure 4
and to plug the leaking tube.in steam generator "A".
I t
ADDI_TIONAL FACTORS (con't) l s
vented to containment, the health and safety of the general public were not affected.
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