ML19294C028: Difference between revisions

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=Text=
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U. S. NUCLEAR REGULATORY COMMISSION
~NRC FORM 366 (7 77)
LICENSEE EVENT REPORT                                          LER 80-8/3L (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI CONTROL BLOCK: l I
l    l    ]    ]    ]
lh 6
0        8 lvlTIylYls11                      @15l0              lo    - l 0 LICENSE lo 1010            l- 10 lo 10      h l@l LICENSE 26 4l il ilT'rilPEll@l 40 l
St L A T 56 l@
14                                      NUMBER i              8 9                LICENSEE CODE C ON'T
                                "                                                                                                                                              l0 l@
7 G          '
8 S$RCE l L @l 0 l 5 l 0 l 0 l 0 l 217 60            61            DOCKET NUM8 ER                  bd    69    l EVENT 1 @l  OATE 0 l 2 l 0 l 3 l 8 l 0 @l080I3 lo l 3 l 8 le      75      REPORT D ATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h                                                                                                                        I o        2 l l
0        3                      See attached sheet I
o          4        l 1
O          s I l
o        6 I I
o          7        l 1
o          e 1                                                                                                                                                                        80 COMP.          VA LV E SYSTEM            CAUSE          CAUSE                                                                    SUSCODE SU8 CODE                  COMPONENT CCDE                  SUSCODE CODE              CODE O          9 8
l 2 l Z lh Wh l B lh bl 'Il Pl 0l Rl Tl@ ] D l@ l Z @
9          10        11              12                r3                          18          19            20 REVISION 7
SE QU E N TI AL                    OCCURRENCE            REPORT CODE              'Y E                        N O.
REPORT NO.
LE A RO .. EVENT YEAR                                                                                                                        l 0l h $j                  l 81 0l              l-j            l 0l 0l 8l                l/l          [ O! 3l                lLl Jo
[---J Jt            32 Nu                                                  24              26      27            28      29
_ 21          22        23 FOR      8. SUPpLI E            MAN FACTURER ON PLANT              T                        HOURS          S8 IT AKEN ACT ON G l2 l5 7l@
W@W@ W@ [JJ@ l 0101010 l W@ l Yl@
JJ            34                  35              2                3d                    40  41                42 l43A l@        44            47 CAUSE DESCRIPTION AND COHRECTIVE ACTIONS I
i        o l 1
L' L'J l                          see attached sheet 1
I i i 2 I L._ .
I 1        3 i
i 4!l                                                                                                                                                                              80 7                8 9 DIS O RY                            DISCOVERY DESCRIPTION STANS                % POWE R                    OTHER STATUS l
lBl@lMaintenanceInspection W                          Glh !OIOl0lhl                                    NA A 7tviTY          CO TENT                                                                                                LOCATION OF RELEASE RELEASED OF RELE ASE                          AMOUNT OF ACT. <f fY NA                                                        l 1        6                                      l                NA                            l                                                                                  30 44          45 7              s 9                    to          tr PERSONNEL FxPOSURES NUY8ER              TYPE        DESCRIPTION l
7      l0 l0 l0 lhl 2lhl                      ''
NA
                                                                                                                                                                                              '
      '              ' '        ,E sSON ~ d'i~;u'J, ES NUMBER              DESCRIPTION l
8 10 lo 0l@l 7              8 9                      11      12 NA                                                                                                80 LOSS OF OR DAM AGE TO F ACitiTY TYPE        D E SCRIPTION l
1        9 d
W hl
                              'J          10 NA NRC USE ONLY 7
PUB LICI TY                                                                            8 0 0 3 0 60 C,56                                                          ,
ISSUED        oESCRiPTiON @                                                                                                      1    iiiiiiiiiiIi!!
L2_laj LtJ81                                                            s^                                                                            68 69                            80 ;
7              8 9                to PHONE:
802-257-7711                          2, NAME OF PREPAHER                    V    E-    IO'W TI
 
.
VTVYS1 0500G271 LER 80-8/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES As a result of a visual inspection of Vermont Yankee's safety class shock suppressors during the February 1980 shutdown, RR-2 was found with no visible fluid level in its sight glass. The snubber was removed and functionally tested in the as-found condition. The snubber did not lock up within the required tolerances and was declared a visual inspection failure. The snubber was repaired and returned to service prior to re-actor startup as required by Tech. Spec. Section 3.6.I.4. Based on the above, and the lack of any seismic event which would require the snubber to be functional, there were no adverse consequences of this occurrence to the health and safety of the public. There have been no previous failures of this s. ibber reported to the Commission.
CAUSE DESCRIPTION AND CORRECTIVE ACTION Functional testing on the VY test machine was not able to reveal the cause of the leakage. However, upon disassembly no obvious seal degrada-tion was observed though some evidence of snubber fluid Icakage appeared in the rod seal area during the visual inspection. Snubber RR-2 was com-pletely rebuilt and was functionally tested prior to reinstallation. As a result of the fai' lure of snubber RR-2 to pass the visual examination, the next required inspection interval is 12 months +257.. RR-2 is a 3 1/4" Crinnel Figure 201 Shock Suppressor.}}

Revision as of 01:40, 15 November 2019

LER 80-008/03L-0:on 800203,during Feb 1980 Shutdown,Shock Suppressor RR-2 Found W/No Visible Fluid Level in Sight Glass & Declared Visible Insp Failure.Cause of Leakage Unknown.Snubber Rebuilt & Tested Prior to Reinstallation
ML19294C028
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 03/03/1980
From: Conway W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19294C025 List:
References
LER-80-008-03L, LER-80-8-3L, NUDOCS 8003060556
Download: ML19294C028 (2)


Text

.

U. S. NUCLEAR REGULATORY COMMISSION

~NRC FORM 366 (7 77)

LICENSEE EVENT REPORT LER 80-8/3L (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI CONTROL BLOCK: l I

l l ] ] ]

lh 6

0 8 lvlTIylYls11 @15l0 lo - l 0 LICENSE lo 1010 l- 10 lo 10 h l@l LICENSE 26 4l il ilT'rilPEll@l 40 l

St L A T 56 l@

14 NUMBER i 8 9 LICENSEE CODE C ON'T

" l0 l@

7 G '

8 S$RCE l L @l 0 l 5 l 0 l 0 l 0 l 217 60 61 DOCKET NUM8 ER bd 69 l EVENT 1 @l OATE 0 l 2 l 0 l 3 l 8 l 0 @l080I3 lo l 3 l 8 le 75 REPORT D ATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o 2 l l

0 3 See attached sheet I

o 4 l 1

O s I l

o 6 I I

o 7 l 1

o e 1 80 COMP. VA LV E SYSTEM CAUSE CAUSE SUSCODE SU8 CODE COMPONENT CCDE SUSCODE CODE CODE O 9 8

l 2 l Z lh Wh l B lh bl 'Il Pl 0l Rl Tl@ ] D l@ l Z @

9 10 11 12 r3 18 19 20 REVISION 7

SE QU E N TI AL OCCURRENCE REPORT CODE 'Y E N O.

REPORT NO.

LE A RO .. EVENT YEAR l 0l h $j l 81 0l l-j l 0l 0l 8l l/l [ O! 3l lLl Jo

[---J Jt 32 Nu 24 26 27 28 29

_ 21 22 23 FOR 8. SUPpLI E MAN FACTURER ON PLANT T HOURS S8 IT AKEN ACT ON G l2 l5 7l@

W@W@ W@ [JJ@ l 0101010 l W@ l Yl@

JJ 34 35 2 3d 40 41 42 l43A l@ 44 47 CAUSE DESCRIPTION AND COHRECTIVE ACTIONS I

i o l 1

L' L'J l see attached sheet 1

I i i 2 I L._ .

I 1 3 i

i 4!l 80 7 8 9 DIS O RY DISCOVERY DESCRIPTION STANS  % POWE R OTHER STATUS l

lBl@lMaintenanceInspection W Glh !OIOl0lhl NA A 7tviTY CO TENT LOCATION OF RELEASE RELEASED OF RELE ASE AMOUNT OF ACT. <f fY NA l 1 6 l NA l 30 44 45 7 s 9 to tr PERSONNEL FxPOSURES NUY8ER TYPE DESCRIPTION l

7 l0 l0 l0 lhl 2lhl

NA

'

' ' ' ,E sSON ~ d'i~;u'J, ES NUMBER DESCRIPTION l

8 10 lo 0l@l 7 8 9 11 12 NA 80 LOSS OF OR DAM AGE TO F ACitiTY TYPE D E SCRIPTION l

1 9 d

W hl

'J 10 NA NRC USE ONLY 7

PUB LICI TY 8 0 0 3 0 60 C,56 ,

ISSUED oESCRiPTiON @ 1 iiiiiiiiiiIi!!

L2_laj LtJ81 s^ 68 69 80 ;

7 8 9 to PHONE:

802-257-7711 2, NAME OF PREPAHER V E- IO'W TI

.

VTVYS1 0500G271 LER 80-8/3L EVENT DESCRIPTION AND PROBABLE CONSEOUENCES As a result of a visual inspection of Vermont Yankee's safety class shock suppressors during the February 1980 shutdown, RR-2 was found with no visible fluid level in its sight glass. The snubber was removed and functionally tested in the as-found condition. The snubber did not lock up within the required tolerances and was declared a visual inspection failure. The snubber was repaired and returned to service prior to re-actor startup as required by Tech. Spec. Section 3.6.I.4. Based on the above, and the lack of any seismic event which would require the snubber to be functional, there were no adverse consequences of this occurrence to the health and safety of the public. There have been no previous failures of this s. ibber reported to the Commission.

CAUSE DESCRIPTION AND CORRECTIVE ACTION Functional testing on the VY test machine was not able to reveal the cause of the leakage. However, upon disassembly no obvious seal degrada-tion was observed though some evidence of snubber fluid Icakage appeared in the rod seal area during the visual inspection. Snubber RR-2 was com-pletely rebuilt and was functionally tested prior to reinstallation. As a result of the fai' lure of snubber RR-2 to pass the visual examination, the next required inspection interval is 12 months +257.. RR-2 is a 3 1/4" Crinnel Figure 201 Shock Suppressor.