ML19253B789: Difference between revisions

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{{#Wiki_filter:NRC FORM 366                                                                                                                        U. S. NUCLt AH H tGUL Ai UH Y COMMlbbiUN (7 77)        ..
{{#Wiki_filter:NRC FORM 366                                                                                                                        U. S. NUCLt AH H tGUL Ai UH Y COMMlbbiUN (7 77)        ..
                          -
LICENSEE EVENT REPORT                                          LER 79-24/3L CONTROL BLOCK: l                  l      l    l      l    l      l                (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
LICENSEE EVENT REPORT                                          LER 79-24/3L CONTROL BLOCK: l                  l      l    l      l    l      l                (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
I                                      6 lo l1l              VlT V l Y l S l 1 l@l 0 l 0 l - lLICENSE 14    15 0 l 0NUMBER l 0 l 0 l 0 l- l 250 l 026 @l4l1l1l1l1 LICENSE TYPE JO@lS7 C A T 68 l    l@
I                                      6 lo l1l              VlT V l Y l S l 1 l@l 0 l 0 l - lLICENSE 14    15 0 l 0NUMBER l 0 l 0 l 0 l- l 250 l 026 @l4l1l1l1l1 LICENSE TYPE JO@lS7 C A T 68 l    l@
7          8 9          LICENSEE CODE CON'T O    1
7          8 9          LICENSEE CODE CON'T O    1
                       "$$RCE
                       "$$RCE l L l@l        0 ] 5DOCKET l 0 [ 0NUVBER l 0 l 2 l 7 l681 @l        0 l EVENT 9 [ 2DATE l 0 l 7 l 974 l@l1    75 0REPORT l1 l8DATEl 7 l980l@
                              "
l L l@l        0 ] 5DOCKET l 0 [ 0NUVBER l 0 l 2 l 7 l681 @l        0 l EVENT 9 [ 2DATE l 0 l 7 l 974 l@l1    75 0REPORT l1 l8DATEl 7 l980l@
7          8                        60          61                                                  69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o  2 l o  3      l        See attached sheet I
7          8                        60          61                                                  69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o  2 l o  3      l        See attached sheet I
10141 l o  s I                                                                                                                                                                        l
10141 l o  s I                                                                                                                                                                        l O  6        i O    7      l 0  8                                                                                                                                                                          !
                                                                                                                                                            .
O  6        i O    7      l 0  8                                                                                                                                                                          !
l 80 7          8 9 SYSTEY              CAUSE            CAUSE                                                  C OY P.        VALVE CODE                CODE          SUBCODE                COMPONENT CODE                  SUBCODE          SUBCODE O  '3                              lI Bl h (_A_j h [J_j h lI lN S lT lR lU lh l Tl@ l Zl@
l 80 7          8 9 SYSTEY              CAUSE            CAUSE                                                  C OY P.        VALVE CODE                CODE          SUBCODE                COMPONENT CODE                  SUBCODE          SUBCODE O  '3                              lI Bl h (_A_j h [J_j h lI lN S lT lR lU lh l Tl@ l Zl@
9        TJ                                            13                          18          19            20 7          8                                                  II                l2 SEQUENTI AL                    OCCURRENCE          REPORT                    REVISION
9        TJ                                            13                          18          19            20 7          8                                                  II                l2 SEQUENTI AL                    OCCURRENCE          REPORT                    REVISION EVENT YE AR                                  REPORT NO.                          CODE              TYPE                        NO.
_
EVENT YE AR                                  REPORT NO.                          CODE              TYPE                        NO.
LER RO
LER RO
                 @4EP      .
                 @4EP      .
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1  6 8 9 Zlh d@l    10          11 NA 44 l        l 45 NA 80 l
1  6 8 9 Zlh d@l    10          11 NA 44 l        l 45 NA 80 l
PERSONNEL f XPOSURES NUV8ER                TYPF          DE SCRIPTION -
PERSONNEL f XPOSURES NUV8ER                TYPF          DE SCRIPTION -
l1 l 7] ] 0l 0 0l@l Zl@l'                                                              NA
l1 l 7] ] 0l 0 0l@l Zl@l'                                                              NA l
* l
'        " '
P E R SON N d'iNau'n'iE S Nuvu R                DESCRiPnON@
P E R SON N d'iNau'n'iE S Nuvu R                DESCRiPnON@
i  s        l0      0        0l@l12                              NA                                                                                        , , ,
i  s        l0      0        0l@l12                              NA                                                                                        , , ,
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Technical Specification 3.2.G requires this post-accident instrumenta-tion be operable during reactor operation. At no t'me was the torus water inventory out of specification. Since this ituication was re-stored within the limiting 6 hours of Tech. Spec. Table 3.2.6, the plant continued power operation. The potential based on the above con-sequences to the health and safety of the public were minimal.
Technical Specification 3.2.G requires this post-accident instrumenta-tion be operable during reactor operation. At no t'me was the torus water inventory out of specification. Since this ituication was re-stored within the limiting 6 hours of Tech. Spec. Table 3.2.6, the plant continued power operation. The potential based on the above con-sequences to the health and safety of the public were minimal.
CORRECTIVE ACTION TAKEN The fitting was repaired, the reference leg refilled, and the in-struments returned to operation. It has been further reemphasized to all contract personnel of the necessity to proceed with caution during all phases of their work activities.
CORRECTIVE ACTION TAKEN The fitting was repaired, the reference leg refilled, and the in-struments returned to operation. It has been further reemphasized to all contract personnel of the necessity to proceed with caution during all phases of their work activities.
                                                                                    .
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Latest revision as of 00:37, 2 February 2020

LER 79-024/03L-0:on 790920,abrupt Change Noted in Indicated Torus Water Level on Control Room Indicators.Hpci Suction Valves Shifted Lineup from Condensate Tank to Torus.Caused by Dislodged Fitting on Torus Level Transmitters
ML19253B789
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 10/18/1979
From: Conway W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19253B775 List:
References
LER-79-024-03L, LER-79-24-3L, NUDOCS 7910220243
Download: ML19253B789 (2)


Text

NRC FORM 366 U. S. NUCLt AH H tGUL Ai UH Y COMMlbbiUN (7 77) ..

LICENSEE EVENT REPORT LER 79-24/3L CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6 lo l1l VlT V l Y l S l 1 l@l 0 l 0 l - lLICENSE 14 15 0 l 0NUMBER l 0 l 0 l 0 l- l 250 l 026 @l4l1l1l1l1 LICENSE TYPE JO@lS7 C A T 68 l l@

7 8 9 LICENSEE CODE CON'T O 1

"$$RCE l L l@l 0 ] 5DOCKET l 0 [ 0NUVBER l 0 l 2 l 7 l681 @l 0 l EVENT 9 [ 2DATE l 0 l 7 l 974 l@l1 75 0REPORT l1 l8DATEl 7 l980l@

7 8 60 61 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l o 3 l See attached sheet I

10141 l o s I l O 6 i O 7 l 0 8  !

l 80 7 8 9 SYSTEY CAUSE CAUSE C OY P. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE O '3 lI Bl h (_A_j h [J_j h lI lN S lT lR lU lh l Tl@ l Zl@

9 TJ 13 18 19 20 7 8 II l2 SEQUENTI AL OCCURRENCE REPORT REVISION EVENT YE AR REPORT NO. CODE TYPE NO.

LER RO

@4EP .

R l7 l9 l l-l l0 l2 l4 l l/l l 0l 3 lLl 9 0]

w 21 22 23 24 26 27 28 29 30 31 32 TAKE C CN ON PL T V T HOURS 22 S BNIT D FOR i bub. S PPLIE MAN FACTURER Zl@ 0 l0 l0 l0 l YlQ l Y]Q l N]g R 2 l9 l0 lg 33Bl@34Hl@ lZ 3d

@ 36 3/ 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i O l l See attached sheet I

[ilil i  :> l I a I i l i 4 1 7 8 9 80 STA 5  % POWER OTHER STATUS ISC RY DISCOVEHY DESCRIPTION Operator Observation i 5 l Zlh l0 l 8 l 8 l@l NA l l A l@l l ACTIVITY CONTENT RELEASED U RELE ASE AMOUNT OF ACTlvlTY LOCATION OF RELEASE 7

1 6 8 9 Zlh d@l 10 11 NA 44 l l 45 NA 80 l

PERSONNEL f XPOSURES NUV8ER TYPF DE SCRIPTION -

l1 l 7] ] 0l 0 0l@l Zl@l' NA l

P E R SON N d'iNau'n'iE S Nuvu R DESCRiPnON@

i s l0 0 0l@l12 NA , , ,

7 H 9 11 h 80 LOSS OF OR DAM AGE TO F ACILITY .

TYPE DESCRIPTION F Fl J @l 7 H 9 10 NA 80 l

NRC USE ONW ISSU D ESCRIP TION NA 79102202 &3 ll lll ll2 12 I o l LUE81 68 69 ll 50 5 7 8 9 10

. . OnWay PHONE:

8 2-257-7711 {

NAME OF PREPARER

. a. .

VTVYS1 05000271 LER 79-24/3L EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During steady state operation, Control Room personnel observed an abrupt change in indicated torus water level on Control Room Indicators LI-16-19-46A/B. Channel A increased from 1.15' to 4.54' while Channel B increased from 1.15' to 6.13'. Additionally, the HPCI suction valves shifted line-up from the condensate storage tank to the torus.

Upon investigation, it was revealed that contractor personnel, while erecting staging, dislodged a fitting on the torus level trans-mitters thereby draining the leg and causing the erroneous readings.

Technical Specification 3.2.G requires this post-accident instrumenta-tion be operable during reactor operation. At no t'me was the torus water inventory out of specification. Since this ituication was re-stored within the limiting 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of Tech. Spec. Table 3.2.6, the plant continued power operation. The potential based on the above con-sequences to the health and safety of the public were minimal.

CORRECTIVE ACTION TAKEN The fitting was repaired, the reference leg refilled, and the in-struments returned to operation. It has been further reemphasized to all contract personnel of the necessity to proceed with caution during all phases of their work activities.

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