ML19095A641

LER 1976-003-00 for Surry Unit 1 Excessive Leakage of Borated Water from Ruptured Diaphragm in Valve 1-CH-85

ML19095A641
Person / Time
Site:	Surry
Issue date:	04/15/1976
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/IE, NRC/RGN-II
References
LER 1976-003-00
Download: ML19095A641 (3)

Text

.,

t, e e RIOHMOND, VIRGINIA 23261 Mr. Norman c. Moseley, Director Office of Inspection and Enforcement

u. s. Nuclear Regulatory Cormnission Region II - Suite 818 230 Peachtree Street, Northwest Atlanta, Georgia 30303

Dear Mr. Moseley:

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Cormnittee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Cormnittee.

lings t-Power Supply Production Operations Enclosures 40 copies USRE-S1-76-03 cc: Mr. Robert W. Reid, Chief Operating Reactors Branch 4 401.6

USRE-Sl-76-03 LICENSEE EVENT REPORT CONTROL BLOCK: I ,. *, I I I (PLEAI PRINT ALL REQUIRED INFORMATION].

,* 1* . 6 LICENSEE LICENSE EVENT NAME . LICENSE NUMBER TYPE TYPE

@Ellv!Alsl 7 8 9 Pis 111 14 10101-10101010101-10101 15 . 25 14 11 111110 I 26 30 lo31 ! 332I REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

@ill_cON'T P 7 8 r I O. I lJJ 57 58 59 Lb.J 60 Io I 5

~

I o I~ I oI 21 a! o I. I o I 3 I 2 I 6 I 1 !6

~ ~ n I IOl4lll4l7l6l 75 80 EVENT DESCRIPTION lo!2l !During normal operation a ruptured diaphragm in valve 1-CH-85 (Boric Acid Tank 11 A11 Sup-I 7 89 , 80 lol3l loly from Filter) caused excessive leakage of borated water. In order to repair the I 7 8 9 . 80

• lol41 !valve, reci rcul at ion between the Boron I nj ecti on Tank and Bari c Acid Tank II A11 was I 7 8 9 80 10151 !secured for approximate 1 y 12 minutes, during which time a 150 M.ole/hr rampdown was con- l 7 8 9 . 1 80 jo!st !ducted. This is contrar'{ to Technical Specification 3.2.C.6 and reportable per (cont'd) I 7 8 9 . . . PRIME . 80 SYSTEM CAUSE COMPONENT COMPONENT SUPPLIER MANUFACTURER*

w COOE CODE COMPONENT CODE

[§0 7 8 IP IC I 9 . 10 11 I V I A I LIV I E I X.17I 12 w 43

!G 44 I 21 5 j 5L 47 CAUSE DESCRIPTION lo!0! lA Grinnel Company 2 inch diaphragm* valve failed due to normal wear. In order to repair I 7 8 9 80 1°1981 9lthe 7

valve, reci rcuJ ation between.

the Bari c Acid Tank and Boron In.iecti on Tank had to

. 80 I

IT@ jbe secured. A power ramp down* was commenced; the va Tve was repaired and p1aced ( cont I d~

7 89 00 FACILITY METHOD OF STATUS  %*POWER* OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION' Em8 7

LEJ 9

11 10 10 Io 12I 13I NA 44 I ~

45 I

46 NA 80 I

FORM OF ACTNITY CONTENT rn RELEASED AMOUNT OF ACTIVITY LOCATION OF RELEASE NA .

7 8 llJ 9

. OF tEziSE 10 11 I I 44 45 NA 80 PERSONNEL EXPOSURES IIrn NUMBER 10 IO IO I LlJ __N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

TYPE

• DESCRIPTION 7 89 11 12 13 80 PERSONNEL INJURIES EE) !o lo !al NUMBER DESCRIPTION

~NA_________________________________________________~

7 8 9* 11 12 80 OFFSITE CONSEQUENCES

.!ill) NA 7 8 9 80

°Loss OR DAMAGE TO FACILITY TYPE DESCRIPTION 7E1fil8 9L1.J 10____________________________________

NA __,80 PUBLICITY

[illj*__ NA__________________________________________________________

7 8 9 80 ADDITIONAL FACTORS*

Elfil*89~--------------------------------------------------------~80 7

E 7 89l f i l . ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ 00 NAME:: E. M. Sweeney, Jr. PHONE: {804) 357-3184 GPO 881,667

r

• EVENT DESCRIPTION e

{CONTINUED)

Technical Specifications 6.6.28(2). The valve was repaired and the unit was re-*

turned to full power ( USRE-Sl-76-03).

CAUSE DESCRIPTION (CONTINUED) back in service befora the reactor.was in a shutdown condition. Due to the short time interval, no significant stratification of boric acid concentration should have occurred. Additionally, the Boron Injection Tank remained at full capacity.

Since the Safety Injection System retained full capabilities, the health and safety of the* general public was not affected.