ML20070J896

RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated

ML20070J896
Person / Time
Site:	Surry, 05000000
Issue date:	09/29/1976
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20070J834	List: L-75-304, Responds to NRC Re Deviation Noted in IE Insp Repts 50-250/75-07 & 50-251/75-07.Corrective Actions:Fire Stops Installed in Cable Trays in Unit 4 Control Rod Drive Room & Entrance to Auxiliary Bldg Above Main Corridor Doors L-75-354, Responds to NRC Re Violation Noted in IE Insp Repts 50-250/75-08 & 50-251/75-08.Corrective Actions: Superseded Procedures for Surveillance Testing Removed & Latest Revision Placed in Control Room on 750526 L-75-595, Responds to NRC Re Violation Noted in IE Insp Repts 50-250/75-16 & 50-251/75-16.Corrective Actions:Overdue Inservice Insp Rept Transmitted to NRC on 751120 & Procedure Written to Describe Scheduling & Preparation of Repts ML20070J858 ML20070J868 ML20070J880 ML20070J896 ML20070J983 ML20070J985 ML20070K041 NG-75-2264, Responds to NRC Re Violations Noted in IE Insp Rept 50-261/75-14.Corrective Actions:Quarterly Calibr of Survey Instruments Will Be Performed Per Health Physics Procedure HP-11 by 760131 & Procedure HP-1 Will Be Revised
References
FOIA-82-534 264, RO-76-05, RO-76-5, TAC-12237, NUDOCS 8212290085
Download: ML20070J896 (15)

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. . 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

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and Production Operations Enclosure cc: Mr. Robert L Reid, Chief (40 copies)

Operating Reactors Branch 4 i

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8212290085 821130 PDR FOIA j SCHLISS82-534 PDR I -

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e' , , CONTROL DLOCK l l l l l l l (PLEAM PRINT ALL RECulHED INFCRMATIO 1 6 L Cf NSIE E CE NSE EYINI ECENSE NUV8E A TVPE TYPE NAME Oi Iv h I sl els 1214l 10101-10101010101-10_l 01 141111111 Ol 1011 1 7 89 15 25 26 30 31 32 C ATE Gony " vp' f NN coCxt? NuMBEA EvtNT oArt nEront oATE

01 CONT l P l O ! {J_l [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 674l ln 75 I ol? l7 l7lA_f 00:

7 8 57 58 59 GO 61 68 69 EVENT DESCRIPTION BE ! During normal operation the pre'ssurizer level fell below the 457. level set point. This}

7 89 80-h lresulted in a decrease in pressurizer pressure and a decrease in the volume control  !

7 89 80 l

EE l tank level. These events indicated a leak rate in excess of 10 nom from an unidenti-7' 89 80 l f f nei source. A reactor trio was manually initiated oer Emergenev Procedurn E4 (Time- l 7- 89 80 HG l 1345). A manual safety iniection followed the manual tric per Emereenev Proce<*ure (Cond 7 89 Pswt

- 80 M i R YOLATON CE CODE COMPONENT CODE '

.O lNlal Lv_I 12lxlxlxlxlxlx1 LnJ lwl1l2l0l47 ly_]

48

, 7 89 10 11 17 43 44 .

CAUSE DESCRIPTION ,

O l Steam Generator "A" of Unit 2 was isolated via Phase I isolation and a leak rate in 80 b

7 89 O l excess of 10gpm was confirmed (9/15/76) (Time: 1400).Operationcpersonnelproceeded'l

7 89 . 80

@ l to bring the reactor to a cold shutdown condition. The ~ tube leak was visually (Con't) l DSCOVERY DrSCOVERY DESCRIPTON 5: A us'  % POWER OTHER STATUS l Operational Event._

1 7 8 9 W 10 l1l 0l 0l 12 13 l N/A l 44

[A_l 45 46 80, l

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A LE S o AMOUNT OF ACTMTV LOCATOk CF AELEEE.

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[Z_j N/A l 44 1N/A 45 80 l:

7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCAsPTON 1 l0l0l0l (Z_j l N/A l 7 89 11 12 13 SM PERSONNEL INJURIES NUMDER DESCRIPTON ll l0l0l0l11 12l N/A

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OFFSITE CONSEOUENCES '

l 8 l N/A 7 89 ,

BM LOSS OR DAMAGE TO FAC1tlTY T Y PE DE SC AfPTON '

D2 (L_j l l N/A _

B@

7 89 10 z PUBUCITY /

l Ml N/A _

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7 89 ADDITIONAL FACTORS ~

@ lSince the reactor was brought to a cold shutdown condition af ter the _ dy t,cctiort of theB@l 7 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) b h .

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1. 4. This event is reportabic per Technical Specification 3.1.C.4. (AO-S2-76-05).

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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".

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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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