ML19209D123: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:.NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)LICENSEE EVENT REPORT CONTROL BLOCK: l llllllh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 0 Ol@l4 1 l 1 l1 l 1 l@l
{{#Wiki_filter:.
@W l I l P l B l H l 2 l@l 0 l 0 l - 10 l 0 l 0 0l0 o 1-7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE T YPE J0 57 CA T 58 CON'T 9 2 l 9l7 l 9 @ll] 0 l1l0 7l9l@
NRC FORM 366                                                                                                                             U. S. NUCLEAR REGULATORY COMMISSION (7-77)
l L @0 l 5 10 l 0 l 0 l 3 l 0 l 1 l@l 0 REPO o i g 7 3 60 61 DOCK ET NUMB ER 68 63 EVENT DATE 14'S REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o 2lAt 0520 hours, 9-29-79, with the unit off line and accroximately 20 per I o a icent ste. y flow, the"B" main steam isolation valve (2-CV-2017) failed
LICENSEE EVENT REPORT CONTROL BLOCK: l 1
;4 to close.Past experience indicates that the reverse tvoe check valve
l    l    l    l    l lh 6
!lwould have closed in high steam flow conditions.
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) o    1 W l LICENSEE IlPlB              l H l 214 l@l15 0 l 0 l - 10 l LICENSE      0 l 0 NUMBER0l0        -
Therefore, the valve I O 5 Eould have performed its safety function had it been required to do so. 1 o 6 0 71 lThis event is reportable per T.
0 Ol@l4            1 l 1 l1 l 1 l@l57 CA T 58 @
S.15.6.9.2.A.9 and was similar to LER ll79-001/01T-0.
7           8 9                             CODE                                                                               25   26     LICENSE T YPE J0 CON'T 7
I O s SY S T E M CAUSE CAUSE COMP.VALVE CCCE CODE SLBCODE COMPONENT CODE SUBCODE SU8 CODE O 9lC D l@ l El@ l B l@
o    i 3
V l A l Ll V l E l X l@ l C l@ (_D_] h 7 8 9 10 11 12 13 18 19 20 ,_SEQUEN TI AL OCCURRENCE RE":T REVISION LER Ap EVENTYEAR REPORT NO.
REPO g      l60L @ 0 l 5 10DOCK 61 l 0 l 0 l 3 l 0 l 1 68l@l630 ET NUMB ER 9    2 l 9l7 l 9 @ll] 0 l1l0 7l9l@
CODE TYPE NO.@ ,R E P,g l217l9-ll0 0l 7ll/ll 011lTll-l0l,_22 23 24 26 27 28 29 JJ 31 32 TAKEN AC ON ON PL NT'ET HOURS SB lFOR 8.SL PP LI E MAN FAC URER l E l@l F l@
EVENT DATE         14     'S         REPORT DATE       80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o   2        lAt 0520 hours, 9-29-79, with the unit off line and accroximately 20 per I o   a icent ste. y flow, the "B" main steam isolation valve (2-CV-2017) failed
Zl@(_Z_j@01 0 l 0 0l(_Y_j @lYl@lNl@lA l5 8 5 l@33 34 35 36 37 40 44 42 43 44 47 CAUSE DESCRIPTION AND COPRECTIVE ACTIONS lThe packing was loosened and the Atwood-Morrill reverse swina check i o valve closed with steam flow at 0533 hours, 9-29-79.
    ;   4             to close.                     Past experience indicates that the reverse tvoe check valve                                                                         !
I i illi>i l t , I I i 4 1 3 3 80 ST S% POWER OTHER STA TUS DISCO RY DISCOVERY DESCRIPTION l Gl@ l 0 2 0l@lN/All A l@l Operator observation li 5'd'"*A TIVITY CO TENT AELEASED OF RELE ASE AVOUNT OF AC alVITY LOC ATION OF RELE ASE l Z l @ l Z l@
O  5        lwould have closed in high steam flow conditions.                                                                         Therefore, the valve                       I o  6        Eould have performed its safety function had it been required to do so. 1 0 71 lThis event is reportable per T. S. 15.6.9.2.A.9 and was similar to LER                                                                                                         l O  s        l79-001/01T-0.                                                                                                                                                         I SY S T E M         CAUSE             CAUSE                                                   COMP.             VALVE CCCE               CODE         SLBCODE                 COMPONENT CODE                   SUBCODE           SU8 CODE O   9                                  lC D l@ l El@ l B l@                                       V l A l Ll V l E l 18X l@ l19 C l@ (_D_]                         h 7             8                           9           10         11               12             13                                                         20
N/All N/Al1 6 7 8 3 10 11 44 45 80 PERSONNEL EXPO 5LRES
                                        ,_                                            SEQUEN TI AL                       OCCURRENCE         RE"   :T                   REVISION LER Ap         EVENTYEAR                                   REPORT NO.                             CODE             TYPE                         NO.
, N L *.'8 E R TYPE D E SC RIPTI C N l0 l 0 l 01@lZ l@l N/A li>'* 'PER SON N A'l. ;u'4 ES
                  @ ,R,E P,g l217l9       22
"*DESCR:PTION@
                                                                      -l              l0 0l 7l 24 l/l            l 011              lTl              l-l          0l
.NueeER 10101 Ol@l N/A I i- .a J 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILtTV
_                          23                             26       27             28     29         JJ                 31       32 TAKEN AC ON                       ON PL NT           'ET                       HOURS             SB l          FOR      8.     SL PP LI E         MAN FAC URER l33E l@l34F l@                         Zl@           (_Z_j@
-TYPE DESCRIPTION lZl@lN/Ali 9 7 4 ?10 80'"* '''#Sc R , P T,0~ @
37 01 0 l 0       0l       (_Y_j @       lYl@ lNl@                       lA l5       8 547 l@
;7910190 427
35               36                                     40     44             42                 43           44 CAUSE DESCRIPTION AND COPRECTIVE ACTIONS i  o        lThe packing was loosened and the Atwood-Morrill reverse swina check i   i          valve closed with steam flow at 0533 hours, 9-29-79.                                                                                                                 I i     >
'"""S'"'" ,shscEhlN/A lllllllllll l l l :2
l                                                                                                                                                                      l t   ,       i                                                                                                                                                                      l i  4        I                                                                                                                                                                       I 1           3 3                                                                                                                                                                     80 ST       S             % POWER                         OTHER STA TUS               DISCO     RY                         DISCOVERY DESCRIPTION i  5 l Gl@ l 0                   2 0l@lN/A                                    l    l A l@l Operator observation                                                   l
: o 7 8 3 to 63 69 80 E NAYE OF PREPARER C.W.Fay 414/277-2811 puoyg.  
  '           d                                         '       "
..ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-007/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 At 0120 hours on September 29, 1979, with Unit 2 off line for secondary side plant maintenance, four condenser steam dump valves were opened (approximately 20% steam flow) during the closing operation of the main steam isolation valves.The"B" main steam valve (2-CV-2017) failed to leave the full open position upon the receipt of a close signal.The"A" main steam isolation (2-CV-2018) valve closed fully.
* A TIVITY         CO TENT AELEASED OF RELE ASE                             AVOUNT OF AC alVITY                                                     LOC ATION OF RELE ASE 1  6 8  3 l Z l @ l10Z l@ 11 N/A                                                          l          l N/A                                                                      l 7                                                                                             44           45                                                                       80 PERSONNEL EXPO 5LRES                                                                                                                 ,
The"B" valve partially closed with some mechanical assistance.
N L *.'8 E R             TYPE         D E SC RIPTI C N
The valve was then reopened and with both mechanical assistance and steam flow, it swung to a position one inch short of the fully closed position.
  '
The valve was again reopened and the gland stuffing ? x packing was loosened.Steam flow was initiated, the close signal given and the valve fully closed at 0533 hours, September 29, 1979.
i    >
After a recent similar event (see Licensee Event Report No. 79-001/0lT-0), the plant staff concluded that the main steam isolation valves would have functioned in the unlikely event of a steam line break and the resulting high steam flow since the valve discs hang at three degrees into the steam flow and have closed on several instances in the 8 6 past at 4 X 10 lbs./hr. (6.6 X 10 lbs./hr. corresponds to 100% power) steam flow even without receiving a close signal.Therefore, it is concluded that the valve would have performed its safety function had it been required to do so.Recognizing the repetitiveness of this type of valve failure to fully close at zero or low flow condition without mechanical assistance or the slacking off of the gland packing, plant staff involvement in investigation of solutions to this problem will continue.
              * '
.1173 354}}
l0 l 0 l 01@lZ l@l" N/A                                                                                                                                               l PER SON N A'l. ;u'4 ES                                                                                                                                         *
                                            .
NueeER                  DESCR:PTION@
i- .a            10101 Ol@l N/A                                                                                                                                                       I J           8 9                   11         12                                                                                                                                   80 LOSS OF OR DAMAGE TO FACILtTV                                                                                                                 -
TYPE           DESCRIPTION 7
i    9 4 ?
lZl@lN/A      10 l
80
                                    '
                        '"* '''#Sc R , P T,0~ @                                           ;7910190 427                                                               "" "S'   "'"
7
:    o 8 3
                  ,shscEhlN/A to l
63 69 llllllllll l l l :2     80 E NAYE OF PREPARER                             C. W.         Fay                                       puoyg.        414/277-2811
 
  .
    .
ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-007/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 At 0120 hours on September 29, 1979, with Unit 2 off line for secondary side plant maintenance, four condenser steam dump valves were opened (approximately 20% steam flow) during the closing operation of the main steam isolation valves. The "B" main steam valve (2-CV-2017) failed to leave the full open position upon the receipt of a close signal. The "A" main steam isolation (2-CV-2018) valve closed fully.
The "B" valve partially closed with some mechanical assistance. The valve was then reopened and with both mechanical assistance and steam flow, it swung to a position one inch short of the fully closed position. The valve was again reopened and the gland stuffing ? x packing was loosened. Steam flow was initiated, the close signal given and the valve fully closed at 0533 hours, September 29, 1979.
After a recent similar event (see Licensee Event Report No. 79-001/0lT-0), the plant staff concluded that the main steam isolation valves would have functioned in the unlikely event of a steam line break and the resulting high steam flow since the valve discs hang at three degrees into the steam flow and have closed on several instances in the past at 4 X 10 8 lbs./hr. (6.6 X 10 6 lbs./hr. corresponds to 100% power) steam flow even without receiving a close signal. Therefore, it is concluded that the valve would have performed its safety function had it been required to do so.
Recognizing the repetitiveness of this type of valve failure to fully close at zero or low flow condition without mechanical assistance or the slacking off of the gland packing, plant staff involvement in investigation of solutions to this problem will continue.
.
1173 354}}

Revision as of 14:28, 19 October 2019

LER 79-007/01T-0:on 790929,main Steam Line B Isolation Valve Failed to Close During 20% Steam Flow,W/Unit Off Line.Caused Not Stated.Packing Was Loosened & Atwood Morrill Reverse Swing Check Valve Closed
ML19209D123
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 10/10/1979
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19209D113 List:
References
LER-79-007-01T-01, LER-79-7-1T-1, NUDOCS 7910190429
Download: ML19209D123 (2)


Text

.

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) o 1 W l LICENSEE IlPlB l H l 214 l@l15 0 l 0 l - 10 l LICENSE 0 l 0 NUMBER0l0 -

0 Ol@l4 1 l 1 l1 l 1 l@l57 CA T 58 @

7 8 9 CODE 25 26 LICENSE T YPE J0 CON'T 7

o i 3

REPO g l60L @ 0 l 5 10DOCK 61 l 0 l 0 l 3 l 0 l 1 68l@l630 ET NUMB ER 9 2 l 9l7 l 9 @ll] 0 l1l0 7l9l@

EVENT DATE 14 'S REPORT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h o 2 lAt 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />, 9-29-79, with the unit off line and accroximately 20 per I o a icent ste. y flow, the "B" main steam isolation valve (2-CV-2017) failed

4 to close. Past experience indicates that the reverse tvoe check valve  !

O 5 lwould have closed in high steam flow conditions. Therefore, the valve I o 6 Eould have performed its safety function had it been required to do so. 1 0 71 lThis event is reportable per T. S. 15.6.9.2.A.9 and was similar to LER l O s l79-001/01T-0. I SY S T E M CAUSE CAUSE COMP. VALVE CCCE CODE SLBCODE COMPONENT CODE SUBCODE SU8 CODE O 9 lC D l@ l El@ l B l@ V l A l Ll V l E l 18X l@ l19 C l@ (_D_] h 7 8 9 10 11 12 13 20

,_ SEQUEN TI AL OCCURRENCE RE" :T REVISION LER Ap EVENTYEAR REPORT NO. CODE TYPE NO.

@ ,R,E P,g l217l9 22

-l l0 0l 7l 24 l/l l 011 lTl l-l 0l

_ 23 26 27 28 29 JJ 31 32 TAKEN AC ON ON PL NT 'ET HOURS SB l FOR 8. SL PP LI E MAN FAC URER l33E l@l34F l@ Zl@ (_Z_j@

37 01 0 l 0 0l (_Y_j @ lYl@ lNl@ lA l5 8 547 l@

35 36 40 44 42 43 44 CAUSE DESCRIPTION AND COPRECTIVE ACTIONS i o lThe packing was loosened and the Atwood-Morrill reverse swina check i i valve closed with steam flow at 0533 hours0.00617 days <br />0.148 hours <br />8.812831e-4 weeks <br />2.028065e-4 months <br />, 9-29-79. I i >

l l t , i l i 4 I I 1 3 3 80 ST S  % POWER OTHER STA TUS DISCO RY DISCOVERY DESCRIPTION i 5 l Gl@ l 0 2 0l@lN/A l l A l@l Operator observation l

' d ' "

  • A TIVITY CO TENT AELEASED OF RELE ASE AVOUNT OF AC alVITY LOC ATION OF RELE ASE 1 6 8 3 l Z l @ l10Z l@ 11 N/A l l N/A l 7 44 45 80 PERSONNEL EXPO 5LRES ,

N L *.'8 E R TYPE D E SC RIPTI C N

'

i >

  • '

l0 l 0 l 01@lZ l@l" N/A l PER SON N A'l. ;u'4 ES *

.

NueeER DESCR:PTION@

i- .a 10101 Ol@l N/A I J 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILtTV -

TYPE DESCRIPTION 7

i 9 4 ?

lZl@lN/A 10 l

80

'

'"* #Sc R , P T,0~ @ ;7910190 427 "" "S' "'"

7

o 8 3

,shscEhlN/A to l

63 69 llllllllll l l l :2 80 E NAYE OF PREPARER C. W. Fay puoyg. 414/277-2811

.

.

ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-007/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> on September 29, 1979, with Unit 2 off line for secondary side plant maintenance, four condenser steam dump valves were opened (approximately 20% steam flow) during the closing operation of the main steam isolation valves. The "B" main steam valve (2-CV-2017) failed to leave the full open position upon the receipt of a close signal. The "A" main steam isolation (2-CV-2018) valve closed fully.

The "B" valve partially closed with some mechanical assistance. The valve was then reopened and with both mechanical assistance and steam flow, it swung to a position one inch short of the fully closed position. The valve was again reopened and the gland stuffing ? x packing was loosened. Steam flow was initiated, the close signal given and the valve fully closed at 0533 hours0.00617 days <br />0.148 hours <br />8.812831e-4 weeks <br />2.028065e-4 months <br />, September 29, 1979.

After a recent similar event (see Licensee Event Report No. 79-001/0lT-0), the plant staff concluded that the main steam isolation valves would have functioned in the unlikely event of a steam line break and the resulting high steam flow since the valve discs hang at three degrees into the steam flow and have closed on several instances in the past at 4 X 10 8 lbs./hr. (6.6 X 10 6 lbs./hr. corresponds to 100% power) steam flow even without receiving a close signal. Therefore, it is concluded that the valve would have performed its safety function had it been required to do so.

Recognizing the repetitiveness of this type of valve failure to fully close at zero or low flow condition without mechanical assistance or the slacking off of the gland packing, plant staff involvement in investigation of solutions to this problem will continue.

.

1173 354