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,              9          LICENSEE CODE                to    15                    LICENSE NUv6ER CON'T                                                                                                                '
,              9          LICENSEE CODE                to    15                    LICENSE NUv6ER CON'T                                                                                                                '
,  0I',                S RCE      W h l0 15 10 60            61 l0lol2l1 196a}@l59 1121119 Do;K ET NUVBER                          EVENT DATE l 719 l@l 01 1l 1181 B I O 14      75      REPORT DATE          80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O    ?      lOn Decevibe r 19, 1979, the equipment operator assigned to conduct an                                                                                      l 0    3      l operability test on the reactor building to suppression chamber vacuum                                                                                    l 0 la        l breakers found valve V-26-17 blocked from opening more than approximate-                                                                                    l 0    s      f ly! 50'4 by sCaf folding placed by contractor personnel .                                          This event is                                          j 0 is      l considered to be operation in a degraded mode as allowed by the Technic-                                                                                    l Oj7        lal Specifications, para. 3.5.A.4.b.                                                                                                                          1 l
,  0I',                S RCE      W h l0 15 10 60            61 l0lol2l1 196a}@l59 1121119 Do;K ET NUVBER                          EVENT DATE l 719 l@l 01 1l 1181 B I O 14      75      REPORT DATE          80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O    ?      lOn Decevibe r 19, 1979, the equipment operator assigned to conduct an                                                                                      l 0    3      l operability test on the reactor building to suppression chamber vacuum                                                                                    l 0 la        l breakers found valve V-26-17 blocked from opening more than approximate-                                                                                    l 0    s      f ly! 50'4 by sCaf folding placed by contractor personnel .                                          This event is                                          j 0 is      l considered to be operation in a degraded mode as allowed by the Technic-                                                                                    l Oj7        lal Specifications, para. 3.5.A.4.b.                                                                                                                          1 l
Oi6        l 7          8 9                                                                                                                    COMP.          VALVE S YSTE f?            CAUSE          CAUSS CCDE                            SUSCCDE                COM80NENT CODE                SUBCCDE          SUSCCDE CCDE ol9                                l Sl D @ l A @ l F l@ l Vl A l L lV lE lX j@ l C l@ l20Cl@                      16          19 7          6                        9          to          11            12              13 OCCURRENCE          REFORT                    REVISION
Oi6        l 7          8 9                                                                                                                    COMP.          VALVE S YSTE f?            CAUSE          CAUSS CCDE                            SUSCCDE                COM80NENT CODE                SUBCCDE          SUSCCDE CCDE ol9                                l Sl D @ l A @ l F l@ l Vl A l L lV lE lX j@ l C l@ l20Cl@                      16          19 7          6                        9          to          11            12              13 OCCURRENCE          REFORT                    REVISION SE QUE NTI AL EVENT YE A R                            REPORT NO.                          CODE              TYPE                        N o.
                                    ._
SE QUE NTI AL EVENT YE A R                            REPORT NO.                          CODE              TYPE                        N o.
LE R>RO O17 ,Rt"SE    RT l7 l9 l                l-l            l 0 l4 l4 l            l/]          l0l3l                lL            l-l          l0 l ut-24            26      27          28      29          30            31          32
LE R>RO O17 ,Rt"SE    RT l7 l9 l                l-l            l 0 l4 l4 l            l/]          l0l3l                lL            l-l          l0 l ut-24            26      27          28      29          30            31          32
_ 21            22          23 SHUTDOWN                              ATTACHVENT          NPRD-4        PRIME COMP.            COMPONENT ACTION FUTURE                      EFFECT FORM bub.        SUPPLIE R          MANUFACTURER TAKEN ACTION                    ON PLANT            METHOD                  HOURS 22      SUB MITTED l33 HlQ!34 H lh                  lbZl@
_ 21            22          23 SHUTDOWN                              ATTACHVENT          NPRD-4        PRIME COMP.            COMPONENT ACTION FUTURE                      EFFECT FORM bub.        SUPPLIE R          MANUFACTURER TAKEN ACTION                    ON PLANT            METHOD                  HOURS 22      SUB MITTED l33 HlQ!34 H lh                  lbZl@
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1    6 8 9 Z l h l 2 lhl 10            11                                          44        45                                                                      8 PERSONNEL EXPOSURES NuveER                              DESCRIPTION -
1    6 8 9 Z l h l 2 lhl 10            11                                          44        45                                                                      8 PERSONNEL EXPOSURES NuveER                              DESCRIPTION -
1    7      l 0 l 0 l 0 lhlTYPEZ lhl                                                          NA        _
1    7      l 0 l 0 l 0 lhlTYPEZ lhl                                                          NA        _
'          ' '
PE RSONN E L INJU IES NUMBER                DESCRIPTION 1    s 8 9 l0l0l0l@l                  12 NA 3
PE RSONN E L INJU IES NUMBER                DESCRIPTION 1    s 8 9 l0l0l0l@l                  12 NA 3
7                                11 LOSS OF oR DAMAGE To F ACILITY Q
7                                11 LOSS OF oR DAMAGE To F ACILITY Q
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1 9 8 9 l Z lhl10                                                                                                                                                          g
1 9 8 9 l Z lhl10                                                                                                                                                          g
                                                                                                                                                             = = ma itSUEr        DE CRiPTION Weekly ne..s release 8 0 0124 o Y33                                        l    lllII1llljj!
                                                                                                                                                             = = ma itSUEr        DE CRiPTION Weekly ne..s release 8 0 0124 o Y33                                        l    lllII1llljj!
y l Y lhj                                                                                                                                      68 69                              g 7          t 9                to
y l Y lhj                                                                                                                                      68 69                              g 7          t 9                to PHONE:    201- W 8 2 NAVE OF PREPARER
* PHONE:    201- W 8 2 NAVE OF PREPARER


  .
Jersey Central Power & Light Company
* Jersey Central Power & Light Company
                                 )
                                 )
                                    ,
'            ,          f                                                  Mad. son Avenue at Punch Bowl Road l                      L  -
'            ,          f                                                  Mad. son Avenue at Punch Bowl Road l                      L  -
Mornstown. New Jerse/ 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-44/3L Report Date
Mornstown. New Jerse/ 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-44/3L Report Date January 18, 1980 Occurrence Date December 19, 1979 Identification of Occurrence Reactor building to suppression chamber vacuum breaker valve V-26-17 was found to be prevented f rom fully opening more than approximately 50% by scaffolding.
                                                                                                                .
January 18, 1980 Occurrence Date December 19, 1979 Identification of Occurrence Reactor building to suppression chamber vacuum breaker valve V-26-17 was found to be prevented f rom fully opening more than approximately 50% by scaffolding.
This event is considered to be operation in a degraded mode as allowed by the Technical Specifications, paragraph 3.5. A.4.b, and to be a reportable occurrence as defined in paragraph 6.9.2.b. (2).
This event is considered to be operation in a degraded mode as allowed by the Technical Specifications, paragraph 3.5. A.4.b, and to be a reportable occurrence as defined in paragraph 6.9.2.b. (2).
Conditions Prior to Occurrence The plant was operating at steady state power.
Conditions Prior to Occurrence The plant was operating at steady state power.
Line 57: Line 49:
1794 15i C'>  _. V PO /,    ,s ' : Co~;;r    U-  J eGeners Pub! c Utit:es S/ stem
1794 15i C'>  _. V PO /,    ,s ' : Co~;;r    U-  J eGeners Pub! c Utit:es S/ stem


  .
.
Reportable Occurrence                                                      Page 2 Report No. 50-219/79-44/3L Analysis of Occurrence The vacuum relief system from the reactor building to the pressure suppression chamber consists of two 100% vacuum relief breaker subsystems (2 parallel sets of 2 valves in series). The purpose of the vacuum relief valves is to equalize pressure so that containment external design pressure limits are not exceeded.
Reportable Occurrence                                                      Page 2 Report No. 50-219/79-44/3L Analysis of Occurrence The vacuum relief system from the reactor building to the pressure suppression chamber consists of two 100% vacuum relief breaker subsystems (2 parallel sets of 2 valves in series). The purpose of the vacuum relief valves is to equalize pressure so that containment external design pressure limits are not exceeded.
Operation of either subsystem will maintain the suppression chamber external pressure less than its design pressure of 1 psi.
Operation of either subsystem will maintain the suppression chamber external pressure less than its design pressure of 1 psi.
The safety significance of this event is considered minimal because the valve would have opened approximately 50% and because the redundant subsystem is designed to perform the necessary venting function unassisted.
The safety significance of this event is considered minimal because the valve would have opened approximately 50% and because the redundant subsystem is designed to perform the necessary venting function unassisted.
                                                                                    "
Corrective Action The blockage was immediately cleared and proper valve operation was verified.
Corrective Action The blockage was immediately cleared and proper valve operation was verified.
Operations and contractor personnel were informed of the incident and reminded of the need to ensure that equipment is not damaged or prevented from performing its intended function.
Operations and contractor personnel were informed of the incident and reminded of the need to ensure that equipment is not damaged or prevented from performing its intended function.

Latest revision as of 14:50, 1 February 2020

LER 79-044/03L-0:on 791219,valve V-26-17 Was Blocked from Opening More than 50%.Caused by Placement of Scaffolding by Contractor Personnel.Blockage Cleared & Proper Valve Operation Verified
ML19291C440
Person / Time
Site: Oyster Creek
Issue date: 01/18/1980
From: Ross D
JERSEY CENTRAL POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19291C437 List:
References
LER-79-044-03L, LER-79-44-3L, NUDOCS 8001240433
Download: ML19291C440 (3)


Text

CONT ROL BLOCK: l i l \ l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

. i e 0IvI IN IJ lo I cl ni i l@lolo1-lolo1oloIol-lolol@l4Iilililil@l 26 26 tlCENSE TYPE 30 l

6) CAT sa l@

, 9 LICENSEE CODE to 15 LICENSE NUv6ER CON'T '

, 0I', S RCE W h l0 15 10 60 61 l0lol2l1 196a}@l59 1121119 Do;K ET NUVBER EVENT DATE l 719 l@l 01 1l 1181 B I O 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O  ? lOn Decevibe r 19, 1979, the equipment operator assigned to conduct an l 0 3 l operability test on the reactor building to suppression chamber vacuum l 0 la l breakers found valve V-26-17 blocked from opening more than approximate- l 0 s f ly! 50'4 by sCaf folding placed by contractor personnel . This event is j 0 is l considered to be operation in a degraded mode as allowed by the Technic- l Oj7 lal Specifications, para. 3.5.A.4.b. 1 l

Oi6 l 7 8 9 COMP. VALVE S YSTE f? CAUSE CAUSS CCDE SUSCCDE COM80NENT CODE SUBCCDE SUSCCDE CCDE ol9 l Sl D @ l A @ l F l@ l Vl A l L lV lE lX j@ l C l@ l20Cl@ 16 19 7 6 9 to 11 12 13 OCCURRENCE REFORT REVISION SE QUE NTI AL EVENT YE A R REPORT NO. CODE TYPE N o.

LE R>RO O17 ,Rt"SE RT l7 l9 l l-l l 0 l4 l4 l l/] l0l3l lL l-l l0 l ut-24 26 27 28 29 30 31 32

_ 21 22 23 SHUTDOWN ATTACHVENT NPRD-4 PRIME COMP. COMPONENT ACTION FUTURE EFFECT FORM bub. SUPPLIE R MANUFACTURER TAKEN ACTION ON PLANT METHOD HOURS 22 SUB MITTED l33 HlQ!34 H lh lbZl@

3 l36 Z lh 3 0 l0 lOlnl40 l? Wh Wh Wh 41 42 43 44 Z lZ lZ lZ l 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h 1 O l Proper valve oneninn en c; nrovnntoa hv ccnffnisinn ni m a bv contractor I i 3 [ personnel. The blockage was immediately cleared and proper valve oper- l

, ,7 ;ation was verified. Operation and contractor personnel were informed  ;

ii3 [ of the incident and reminded of the need to insure that equipment is not {

i,4 l damaged nor prevented from performino its intended function. ]

80 7 8 9 STA  % POWER OTH E R STATUS OlS O RY DISCOVERY DESCRIPTION l1 l 5 l l E lh l 0 l 8 l 8 lhl NA l lAlhl Operator observation l ACTIVITY CO TENT RELE ASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE NA l l NA l 7

1 6 8 9 Z l h l 2 lhl 10 11 44 45 8 PERSONNEL EXPOSURES NuveER DESCRIPTION -

1 7 l 0 l 0 l 0 lhlTYPEZ lhl NA _

PE RSONN E L INJU IES NUMBER DESCRIPTION 1 s 8 9 l0l0l0l@l 12 NA 3

7 11 LOSS OF oR DAMAGE To F ACILITY Q

^ 9 1 p TvPE DESCRIPTION D q ~/ ' I lt 1 U NA 7

1 9 8 9 l Z lhl10 g

= = ma itSUEr DE CRiPTION Weekly ne..s release 8 0 0124 o Y33 l lllII1llljj!

y l Y lhj 68 69 g 7 t 9 to PHONE: 201- W 8 2 NAVE OF PREPARER

Jersey Central Power & Light Company

)

' , f Mad. son Avenue at Punch Bowl Road l L -

Mornstown. New Jerse/ 07960 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/79-44/3L Report Date January 18, 1980 Occurrence Date December 19, 1979 Identification of Occurrence Reactor building to suppression chamber vacuum breaker valve V-26-17 was found to be prevented f rom fully opening more than approximately 50% by scaffolding.

This event is considered to be operation in a degraded mode as allowed by the Technical Specifications, paragraph 3.5. A.4.b, and to be a reportable occurrence as defined in paragraph 6.9.2.b. (2).

Conditions Prior to Occurrence The plant was operating at steady state power.

Power: Reactor, 1701 MWt Generator, 585 MWe b gpm Flow: Recirculation 16 x Feedwater6.33x10{0 lbm/hr Stack s: 2.71 x 100 uci/sec Description of Occurrence On December 19, 1979, the equipment operator assigned to conduct an operability test on the reactor building to suppression chamber vacuum breakers found V-26-17 blocked by scaffolding. He immediately cleared the blockage and con-ducted the test. The operability test was completed satisfactorily.

Apparent Cause of Occurrence This cause of the occurrence is attributed to contractor personnel who placed scaffolding in a position to block the valve from fully opening.

1794 15i C'> _. V PO /, ,s ' : Co~;;r U- J eGeners Pub! c Utit:es S/ stem

Reportable Occurrence Page 2 Report No. 50-219/79-44/3L Analysis of Occurrence The vacuum relief system from the reactor building to the pressure suppression chamber consists of two 100% vacuum relief breaker subsystems (2 parallel sets of 2 valves in series). The purpose of the vacuum relief valves is to equalize pressure so that containment external design pressure limits are not exceeded.

Operation of either subsystem will maintain the suppression chamber external pressure less than its design pressure of 1 psi.

The safety significance of this event is considered minimal because the valve would have opened approximately 50% and because the redundant subsystem is designed to perform the necessary venting function unassisted.

Corrective Action The blockage was immediately cleared and proper valve operation was verified.

Operations and contractor personnel were informed of the incident and reminded of the need to ensure that equipment is not damaged or prevented from performing its intended function.

Failure Data Not applicable

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