ML19210D062: Difference between revisions

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(7-77) o LICENSEE EVENT REPORT CONTROL BLOCo                     l      l    l        l      lh                (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil8 9I Nl Yl Jl A Fl lj@bl 0                         1#    15
(7-77) o LICENSEE EVENT REPORT CONTROL BLOCo lllllh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil I Nl Yl Jl A Fl lj@bl 0- l 0 -l 0 O ! O l - l O ! 0 l 0 @l 4 l 1 l 1 l 1 l I l@l ll@7 8 9 LICENSEE CODE 1#15 LICENSE NUVBER 25 26 LICENSE TYPE JO 57 CM 58 CON'T s$n$Ll@ 015 l 0 O! 01 3 3131@l I l 0 2lSI719 @l111III6171 9@
                                                                                - l 0 -l 0     O ! O l - l O ! 0 l 250 @l26 4 l LICENSE LICENSE NUVBER 1 l 1 lTYPE    1 l JO I l@l57        l CM 58 l@
" o i 7 8 60 61 DO2KET NUV8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h OI2 l SEE ATTACHMENT lo 3 i O 4 1 1 O s llll 0 l6 ll0 7l0 Hll7 8 9 80 SYSTEM CAUSE CAUSE C O'.? P.VALVE CODE CODE SU8 CODE COYPONENT CODE SU8 CODE SUBCODEl Al Bl@E @ l Fl@ lV l A L lV lE lX @ lX@ lHlh o 9 7 8 9 10 11 12 13 18 in 20 SEQUENTIAL OCCURRENCE REFORT REVISION , EVENT YE AR REPORT NO CODE TYPE NO.*O lLER ROl7l9ll-ll0l9l4ll/l 013 lLll-l[0_j Ep,0_ 21 22 23 24 26 27 28 , . 29 30 31 32 TAKE A T ON O PLANT ETH HOURS S 8 IT D FCFP [UB.SUPP LI E MAN FACTURER U@[_2_j@W@Zl@l0l0 0l0llY l@lYlh IAl@lC 2l8I5l@
7                         LICENSEE CODE CON'T
33 34 35 36 3/40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O I SEE ATTACHMENT l 1 1lli I ?l l l.1 3 1 11 141 1-7 8 9 80'ST S% POWER OTHE R STATUS OISCOV RY DISCOVERY DESCRIPTION Uh 1 0l0lh NAllBl@l SURVElLLANCE TEST j i 5 ACTIVITY CONTENT RELEASED OF RE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE li 161 [z_J @ l z l@
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NAlNAl7 8 9 10 11 44 45 80 PERSONNEL E MPOSURES NUYBER DESCRIPTION TYPE @l[0 10 01 @ l l NA i 7'" *''"" PERSONNEL,N;uWitS DESCRIPTION @
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Nuv8ERl0 0l 0l@[NAli 8 7 8 9 11 12 80 LC S OF CH DAMAGE TO FACILITY f pC TYPE DESCRIPTION i NA-}}d @ll1 9 7 8'3 10 80 PUB L ICI T Y NRC USE ONLY ISSUED @ DESCRIPTION ll l I l I l l l l I l l *4
s$n$         60 Ll@61015 l 0DO2KET            O!NUV8ER 01 3 3131@l     68  69 IEVENT l 0 DATE 2lSI719 @l111III6171 74       75         REPORT DATE 9@
*[!1_jlNA 2 O i 7 8 9 10 68 69 80 &NAME OF PREPARER W. Verne ChiIds (31 342-1840{'PHCNE: 7 9112 00 i h
80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h OI2 l               SEE ATTACHMENT                                                                                                                                                         l o    3 i O     4     1                                                                                                                                                                             1 O     s l                                                                                                                                                                                  l l
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9          10          11 E @ l Fl@ lV l A L lV lE lX @ lX@ lHlh 12           13                           18           in                 20 SEQUENTIAL               ,      OCCURRENCE             REFORT                         REVISION
* EVENT YE AR                               REPORT NO                           CODE                 TYPE                               NO.
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41 lYlh 42 IAl@ lC 2l8I5l@
43             44                   47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i   O       I         SEE ATTACHMENT                                                                                                                                                     l 1   1      l li I ?l l                                                                                                                                                                                       l
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7         8 9                                                                                                                                                                             80 ST       S             % POWER                       OTHE R STATUS             OISCOV RY                             DISCOVERY DESCRIPTION i    5 Uh                 1 0l0lh                     NA                      l    lBl@l                 SURVElLLANCE TEST                                                   j ACTIVITY       CONTENT RELEASED OF RE LE ASE                         AMOUNT OF ACTIVITY                                                     LOCATION OF RELEASE NA                                    l                      NA                                                                          l li 1618 9[z_J @ l10z l@
7                                            11                                         44         45                                                                                   80 PERSONNEL E MPOSURES NUYBER                               DESCRIPTION i 7
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i    8 8 9 l0 0l 0l@[                           NA                                                                                                                                      l 7                                 11       12                                                                                                                                               80 LC S OF CH DAMAGE TO FACILITY                                                                                                                       pC TYPE       DESCRIPTION                                                                                                           i       f
                                                                                                                                                                        }}
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80 l
PUB L ICI T Y NRC USE ONLY
* 2 O          [!1_j ISSUED       l        @     DESCRIPTION NA                                                                                                        l        l l I l I l l l l I l l *4 i   7           8 9             10                                                                                                                   68 69                                     80 &
NAME OF PREPARER                       W. Verne ChiIds                                             PHCNE:            (31       342-1840                           {'
.
.
e.-POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LCR 79-094/03L-0 Page 1 of 1 During normal operations while conducting Operations Surveillance Test F-ST-76J14, titled " Smoke and Heat Detector Functional Tests -
7 9112 00 i h
North Cable Room," the master valve associated with the ten ton Cardox system did not open fully. The testing was being conducted to satisfy the requirements of Technical Specifications, Appendix A, Paragraphs 4.12.C.1 and 4.12.E.
 
Continuous fire watch personnel, equipped with portable fire extinguishing equipment were posted for the areas served by the ten ton unit until repair and testing could be completed. The event did not represent a significant hazard to the public health and safety.
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Disassembly and inspection of the valve revealed that the valve packing had hardened due to age and restricted the valve travel.
                                -
Follow-ing replacement of the packing, proper operation of the valve was verified by successful completion of F-ST-76J14 and the system was returned to service approximately two-hours after discovery of the problem.
.
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LCR 79-094/03L-0                               Page 1 of 1 During normal operations while conducting Operations Surveillance Test F-ST-76J14, titled " Smoke and Heat Detector Functional Tests -
North Cable Room," the master valve associated with the ten ton Cardox system did not open fully. The testing was being conducted to satisfy the requirements of Technical Specifications, Appendix A, Paragraphs 4.12.C.1 and 4.12.E. Continuous fire watch personnel, equipped with portable fire extinguishing equipment were posted for the areas served by the ten ton unit until repair and testing could be completed. The event did not represent a significant hazard to the public health and safety.
Disassembly and inspection of the valve revealed that the valve packing had hardened due to age and restricted the valve travel. Follow-ing replacement of the packing, proper operation of the valve was verified by successful completion of F-ST-76J14 and the system was returned to service approximately two-hours after discovery of the problem.
                                              .
                                                      $
    .
                                                                  /
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Revision as of 12:42, 19 October 2019

LER 79-094/03L-0:on 791025,while Conducting Operations Surveillance Test F-ST-76J14,master Valve on 10-ton Cardox Sys Did Not Fully Open.Caused by Hardening of Valve Packing. Repacking of Valve Corrected Problem
ML19210D062
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 11/16/1979
From: W. Verne Childs
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19210D057 List:
References
LER-79-094-03L, LER-79-94-3L, NUDOCS 7911200487
Download: ML19210D062 (2)


Text

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(7-77) o LICENSEE EVENT REPORT CONTROL BLOCo l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lil8 9I Nl Yl Jl A Fl lj@bl 0 1# 15

- l 0 -l 0 O ! O l - l O ! 0 l 250 @l26 4 l LICENSE LICENSE NUVBER 1 l 1 lTYPE 1 l JO I l@l57 l CM 58 l@

7 LICENSEE CODE CON'T

"

7 o i 8

s$n$ 60 Ll@61015 l 0DO2KET O!NUV8ER 01 3 3131@l 68 69 IEVENT l 0 DATE 2lSI719 @l111III6171 74 75 REPORT DATE 9@

80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h OI2 l SEE ATTACHMENT l o 3 i O 4 1 1 O s l l l

l 0 l6 l l 0 7 l 0 H l l 7 8 9 80 SYSTEM CAUSE CAUSE C O'.? P. VALVE CODE CODE SU8 CODE COYPONENT CODE SU8 CODE SUBCODE 7

o 9 8

l Al Bl@

9 10 11 E @ l Fl@ lV l A L lV lE lX @ lX@ lHlh 12 13 18 in 20 SEQUENTIAL , OCCURRENCE REFORT REVISION

  • EVENT YE AR REPORT NO CODE TYPE NO.

O lLER ROEp,0 l7l9l l-l l0l9l4l l/ l 013 l Ll l-l [0_j

_ 21 22 23 24 26 27 28 , . 29 30 31 32 TAKE A T ON O PLANT ETH HOURS S 8 IT D FCFP [UB. SUPP LI E MAN FACTURER U@[_2_j@

33 34 W@

35 36 Zl@ l0l0 3/

0l0l 40 lY l@

41 lYlh 42 IAl@ lC 2l8I5l@

43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O I SEE ATTACHMENT l 1 1 l li I ?l l l

.

1 3 1

-

11 141 1

'

7 8 9 80 ST S  % POWER OTHE R STATUS OISCOV RY DISCOVERY DESCRIPTION i 5 Uh 1 0l0lh NA l lBl@l SURVElLLANCE TEST j ACTIVITY CONTENT RELEASED OF RE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l NA l li 1618 9[z_J @ l10z l@

7 11 44 45 80 PERSONNEL E MPOSURES NUYBER DESCRIPTION i 7

[0 10 01 @ lTYPE l @l NA

' " *

PERSONNEL,N;uWitS

" "

Nuv8ER DESCRIPTION @

i 8 8 9 l0 0l 0l@[ NA l 7 11 12 80 LC S OF CH DAMAGE TO FACILITY pC TYPE DESCRIPTION i f 7 1 9 8 d @l

                   '3           10 NA
                                                                                                                                                           -

80 l PUB L ICI T Y NRC USE ONLY

  • 2 O [!1_j ISSUED l @ DESCRIPTION NA l l l I l I l l l l I l l *4 i 7 8 9 10 68 69 80 &

NAME OF PREPARER W. Verne ChiIds PHCNE: (31 342-1840 {' . 7 9112 00 i h

e

                                -

. POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET N0. 50-333 ATTACHMENT TO LCR 79-094/03L-0 Page 1 of 1 During normal operations while conducting Operations Surveillance Test F-ST-76J14, titled " Smoke and Heat Detector Functional Tests - North Cable Room," the master valve associated with the ten ton Cardox system did not open fully. The testing was being conducted to satisfy the requirements of Technical Specifications, Appendix A, Paragraphs 4.12.C.1 and 4.12.E. Continuous fire watch personnel, equipped with portable fire extinguishing equipment were posted for the areas served by the ten ton unit until repair and testing could be completed. The event did not represent a significant hazard to the public health and safety. Disassembly and inspection of the valve revealed that the valve packing had hardened due to age and restricted the valve travel. Follow-ing replacement of the packing, proper operation of the valve was verified by successful completion of F-ST-76J14 and the system was returned to service approximately two-hours after discovery of the problem.

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