05000271/LER-1979-016-03, /03L-0 on 790717:redundant Containment Isolation Capability Not Available.Caused by Requirement to Disassemble Valve for Maint.Valve Cleaned,Reassembled,Tested & Returned to Svc

From kanterella
(Redirected from ML19256B677)
Jump to navigation Jump to search
/03L-0 on 790717:redundant Containment Isolation Capability Not Available.Caused by Requirement to Disassemble Valve for Maint.Valve Cleaned,Reassembled,Tested & Returned to Svc
ML19256B677
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/16/1979
From: Conway W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19256B676 List:
References
LER-79-016-03L, LER-79-16-3L, NUDOCS 7908210417
Download: ML19256B677 (2)


LER-1979-016, /03L-0 on 790717:redundant Containment Isolation Capability Not Available.Caused by Requirement to Disassemble Valve for Maint.Valve Cleaned,Reassembled,Tested & Returned to Svc
Event date:
Report date:
2711979016R03 - NRC Website

text

asc r oa r.i 26 u. >..uu t t-n n e u u tm u n, uu... H m va (7/7)

LICENSEE EVENT REPORT LER 79-16/3L CONTROL BLOCK:

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 1 l1 l1]@l l

]@

@l 0 l 0 -l0 0

0 0 l0 0 l0 @l4 lv lT V lY lS 1

0 1

1 H 9 LICE NSEE CCOE 14 15 LICENSE NUYt3E H 25 2t>

UCE NSE TYPE.i )

51 LAt 58 CON *T 8 l1 6 7 l9 @

l@l0

']"' l L l@l 0 l 5 l 0 l 0 l 0 l 2 7 l1 @l0 l7 l1 l7 l7 9

o 1

REPCRT D AT E MJ 4

60 ta l UQCKE ; NUYBEH t2 w

EV ENT O AT E 14 EVENT JESChir TION AND PROB ABLE CONSEQUENCES h a D_J l I

l o

3 l

See attached sheet o

4 l

1 o

s l 1

o a

1 i

O 7

l

),

O 8

I SY ST E V

CAUSE

C AUSE COYP VA'VE COC-COCE SU9 CODE CO'.4PoriEN T CODE SU8 CODE SUSCCOE i S l o l@ [E J@ In l@

Vl Al Ll Vl El Xl@

F l@ lD l@

o o

1 8

9 to it _

12 13 18 19 29 SE QUEN TI AL OCCUR Wf r.CF HEFOHT RE\\ IS3ON

_ EVENT YE AH H E POR T NO.

CODE TYPE NC t r :. q

@.i.if; I 7l 9 l-l l0 11 6l l-l l0l3 lL l

[_j g

_ 21 23 T4 iti 21 23 29 JU 31 PCNE N T ACTION FUTUnr EF8ECT SHU T UG A.

ATT ACHYEN T NPR D <1 PRIVE CC"P.

_' 'F A C TU R E H TAKEN aC T ION CN PL ANT YETHOD HOURS e.

SL8VI TT E D FORMdUB SUPPLIE H b

)z 13 4

3 36 3e 40 14 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l

i o

1 i

See attached sheet I

l I

i 1

l i

3 ti 4

1 I

7 8 9 80 YE THOD OF F ACILITV 3g STATUS

. PO?. E R OTHER ST ATUS OiSCOVERY DISCOVE RY DESCR1P T!ON 3.

l > l 5 l l E l@ l0 l 9 l 7 l@l l A l@l Operator Observation J

NA A TiVITY CO 4 TENT RELE ASED OF RE LE ASE AYOUN T OF ACTIVITY LOC ATION Or RE L E ASE NA l

l NA l

U.h] I z I @ LzJ@l 7

d s

10 1;

44 45 80 PE H S's, N E L f k PC'#UR E S NUYR E R TYPE DESC4;PTION n7 101010j@lz @l NA l

7 8 9 11 12 13

- /

/

8J nESCn,TiONO g

}

PF PSONNE L INJUHIES Nim e n li l I l 010101@l NA 7

8 9 11 12 80 t OSS OF CR D AV AGE ',O F AtiLI Tv O" 290823o3 9f/ 7

[.

l

- PE m E ScR,P T,0 Izl@l NA a

1 8 9 10 g6

,muF"=bP1,e,@

827 090 l2lol Nlhl NA l

ll lllll llll l; 1

8 9 10 68 69 80 ;

Way NAVE OF PREPARER PHONE:

VTVYS1 05000271 LER 79-16/3L EVENT DESCRIPTION AND PROBABLE CONSEQUENCES The movement of radioactive equipment near the spent fuel pool radia-tion monitors by Maintenance personnel caused a Group 3 containment isola-tion during normal power operations.

This condition was corrected and the Group 3 isolation valves reset.

Valve V-16-20-22B located in the dry-well to torus pressurization system would not reopen.

SEGT was started in accordance with plant procedures to maintain drywell to torus AP as required by Tech. Spec. 3.7.A.9.

The valve was later disassembled for maintenance leaving only one closed isolation valve availabic between drywell and V-16-20-22B.

As a consequence, redundant contait. ment isola-tion cannbility as required by Tech. Spec. 3.7.D.1 was not available.

The valve was repaired cnd returned to service within three hours.

In accord-ance with Tech. Spec. Section 3.7.D.2, there was at least one valve oper-able and ir. the CLOSLD position as req < ired to isolate this line from the containment; therefore, there were no consequences to the health and safety of the public. There have been no similar occurrences reported to the Commission.

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The cause of this occurrence was the requirement to disassemble V-16-20-223 for maintenance leaving only one operable valve available for containment isolation. Valve 16-20-22B is an Atkomatic, Catalog No.

31840VPlMOD, solenoid operated, one inch, globe isolation valve.

This valve has a magnetic type indicator in a well below the valve body which is actuated by a valve stem extension.

The well had accumulated suffi-cient dirt to prevent the stem extension from traveling its full range.

The valve was cleaned, reassembled, tested and returned to service.

B27 09I