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{{#Wiki_filter:NRC FOR,M 366                                                                                                                      U. S. NUCLE AR REGULATORY COMMISSION
{{#Wiki_filter:NRC FOR,M 366                                                                                                                      U. S. NUCLE AR REGULATORY COMMISSION
'
   *VI '                                                                          LICENSEE EVENT REPORT                                          LER 78-35/3L                              -
   *VI '                                                                          LICENSEE EVENT REPORT                                          LER 78-35/3L                              -
            ,
CONTROL BLOCK:                      l      l    l    l    lQ                (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o    1 8 9 lVlTlVIYlSl1l@l0l0l- 0l0l0 LICENSEE CODE              14      15 0 l 0 l- l 0 l 0 l@l LICENSE NUMBER                    25      26 l 0 0TYPE 4 l 1LICENSE          l 0Jol@l5 7 CA T 68l@
CONTROL BLOCK:                      l      l    l    l    lQ                (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o    1 8 9 lVlTlVIYlSl1l@l0l0l- 0l0l0 LICENSEE CODE              14      15 0 l 0 l- l 0 l 0 l@l LICENSE NUMBER                    25      26 l 0 0TYPE 4 l 1LICENSE          l 0Jol@l5 7 CA T 68l@
CON'T
CON'T 0  1 5$R      j L}@l0 5l0l0l0l2 7 l168@l691 l 211                                              l017 l 874l@l0 EVENT DATE                        75 l1REPORT l0 l DATE 8 l 7 l980l@
                        " "'
0  1 5$R      j L}@l0 5l0l0l0l2 7 l168@l691 l 211                                              l017 l 874l@l0 EVENT DATE                        75 l1REPORT l0 l DATE 8 l 7 l980l@
7            3                  60          61                DOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 1
7            3                  60          61                DOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 1
o  2 o  3      l        See attached sheet                                                                                                                                      l I
o  2 o  3      l        See attached sheet                                                                                                                                      l I
Line 49: Line 45:
                                     *.POWER                        OTHER STATUS                DISCO RY                              DISCOVERY DESCRIPTION STA 5 i
                                     *.POWER                        OTHER STATUS                DISCO RY                              DISCOVERY DESCRIPTION STA 5 i
sl W @lll0lOl@                                            NA                        l    W @l Operatcr Investigation                                                      l ACTIVITY CONTENT AMOUNT OF ACTIVITY                                                      LOCATION OF RELEASE RELEASED OF RELE ASE l
sl W @lll0lOl@                                            NA                        l    W @l Operatcr Investigation                                                      l ACTIVITY CONTENT AMOUNT OF ACTIVITY                                                      LOCATION OF RELEASE RELEASED OF RELE ASE l
    #
i  c W @ ygl                                    NA                              l        l        NA PERSONNEL FXPOS ES NUYBER              TYPE        DESCRIPTION l
i  c
1  7 l0l0l0l@lZl@l                                                    NA PEPSONNELINJU IES NUVBER              DESCRIPTION NA                                                                                                            l li l s 8l 9l 0 l 0 l 0 l@l12 1                            11 80 LOSS OF OR OAMAGE TO FACILITY TYPE    DESCRIPTION NA                                                                                                            l l 1 l 9 l l Z l@l10                                                                                                                                                            80 7          8 9 2 o          lNl l @DESCR;PTION ISSUED                                  NA                                                                                      l    lllllll]lllll}
              * '
W @ ygl                                    NA                              l        l        NA PERSONNEL FXPOS ES NUYBER              TYPE        DESCRIPTION l
    '
1  7
              "
* l0l0l0l@lZl@l                                                    NA PEPSONNELINJU IES NUVBER              DESCRIPTION NA                                                                                                            l li l s 8l 9l 0 l 0 l 0 l@l12 1                            11 80 LOSS OF OR OAMAGE TO FACILITY TYPE    DESCRIPTION NA                                                                                                            l l 1 l 9 l l Z l@l10                                                                                                                                                            80 7          8 9
* 2 o          lNl l @DESCR;PTION ISSUED                                  NA                                                                                      l    lllllll]lllll}
68 69                            80 5 9        0 Q g8                                        ,
68 69                            80 5 9        0 Q g8                                        ,
802-257-7711 NM OF PREPARER W. F. COnway                                          . , _        pgggg;                                              {
802-257-7711 NM OF PREPARER W. F. COnway                                          . , _        pgggg;                                              {


,-
VTVYS1
VTVYS1
* 05000271
* 05000271 LER78-35/3L EVENT DESCRIPrION AND PROBABLE CONSEQUENCES During normt1 plant operations, it was observed that the indicated torus water level was increasing at a f aster than normal rate. While in-vestigations into'.the abnormal level increase were in progress, approxi-mately 3,000 cubic feet of water was transferred to Radwaste. This was s
                                                                                  '
LER78-35/3L EVENT DESCRIPrION AND PROBABLE CONSEQUENCES During normt1 plant operations, it was observed that the indicated torus water level was increasing at a f aster than normal rate. While in-vestigations into'.the abnormal level increase were in progress, approxi-mately 3,000 cubic feet of water was transferred to Radwaste. This was s
done to prevent exiteeding the Order for Modification specified maximum torus volume of 70,000 cubic feet. The investigation subsequently re-vealed that the corison reference leg to the torus level transmitters, LT-16-19-38A/B was n'at full. This canned the level indicators to show a higher than actual 1evel. Upon refilling the reference leg, the actual 1
done to prevent exiteeding the Order for Modification specified maximum torus volume of 70,000 cubic feet. The investigation subsequently re-vealed that the corison reference leg to the torus level transmitters, LT-16-19-38A/B was n'at full. This canned the level indicators to show a higher than actual 1evel. Upon refilling the reference leg, the actual 1
level indicated a vol4.ine of only 65,200 cubic feet. Technical Specifi-cation Section 3.7.A.1,.e requires a minimum volume of 68,000 cubic feet.
level indicated a vol4.ine of only 65,200 cubic feet. Technical Specifi-cation Section 3.7.A.1,.e requires a minimum volume of 68,000 cubic feet.

Latest revision as of 17:01, 1 February 2020

LER 78-035/03L-0 on 781210:indicated Torus Water Level Rose Too Fast.Indication Was False Due to Loss of Water in the Reference Leg of the Torus Level Transmitters, LT-16-19-38A/B
ML19289C421
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 01/08/1979
From: Conway W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19289C419 List:
References
LER-78-035-03L, LER-78-35-3L, NUDOCS 7901120159
Download: ML19289C421 (2)


Text

NRC FOR,M 366 U. S. NUCLE AR REGULATORY COMMISSION

  • VI ' LICENSEE EVENT REPORT LER 78-35/3L -

CONTROL BLOCK: l l l l lQ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 o 1 8 9 lVlTlVIYlSl1l@l0l0l- 0l0l0 LICENSEE CODE 14 15 0 l 0 l- l 0 l 0 l@l LICENSE NUMBER 25 26 l 0 0TYPE 4 l 1LICENSE l 0Jol@l5 7 CA T 68l@

CON'T 0 1 5$R j L}@l0 5l0l0l0l2 7 l168@l691 l 211 l017 l 874l@l0 EVENT DATE 75 l1REPORT l0 l DATE 8 l 7 l980l@

7 3 60 61 DOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 1

o 2 o 3 l See attached sheet l I

o 4 l l

loIsll 0 6 l 0 7 l l

0 8 l 80 7 8 9 C DE CODE SU8CO E COMPONENT CODE SU8C DE SU E 7

o 9 8

l Sl Al@ W@ W@ l Il N Sl Tl Rl Ulh l T l@ W @

9 10 11 12 13 18 19 20 SEOUENTI AL C CCU".R E N CE REPORT REVISION REPOR T NO. CODE TYPE N O.

LER RO _ EVENT YEAR

@ REP RT l 7l 8l 21 22 l-l 23 '

l 0l 3 5[26 24

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27 l0!3l 28 29 lL l 30

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32 ON PL NT HOURS S8 IT FOR1 B. SUPPLIE MANUFACTURER TAK ACT ON T l33Elgl34 Zlg l35Zlg [Z l@ l 0l 0 31 0 0l 40

]Q 41 l N g l Al@

42 43 l44Z [ 9 l 9 [ 947l@

36 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I

Ii o l See attached sheet i i i l I

i 2 l

11 131 l I

11 1411 80 7 8 9

  • .POWER OTHER STATUS DISCO RY DISCOVERY DESCRIPTION STA 5 i

sl W @lll0lOl@ NA l W @l Operatcr Investigation l ACTIVITY CONTENT AMOUNT OF ACTIVITY LOCATION OF RELEASE RELEASED OF RELE ASE l

i c W @ ygl NA l l NA PERSONNEL FXPOS ES NUYBER TYPE DESCRIPTION l

1 7 l0l0l0l@lZl@l NA PEPSONNELINJU IES NUVBER DESCRIPTION NA l li l s 8l 9l 0 l 0 l 0 l@l12 1 11 80 LOSS OF OR OAMAGE TO FACILITY TYPE DESCRIPTION NA l l 1 l 9 l l Z l@l10 80 7 8 9 2 o lNl l @DESCR;PTION ISSUED NA l lllllll]lllll}

68 69 80 5 9 0 Q g8 ,

802-257-7711 NM OF PREPARER W. F. COnway . , _ pgggg; {

VTVYS1

  • 05000271 LER78-35/3L EVENT DESCRIPrION AND PROBABLE CONSEQUENCES During normt1 plant operations, it was observed that the indicated torus water level was increasing at a f aster than normal rate. While in-vestigations into'.the abnormal level increase were in progress, approxi-mately 3,000 cubic feet of water was transferred to Radwaste. This was s

done to prevent exiteeding the Order for Modification specified maximum torus volume of 70,000 cubic feet. The investigation subsequently re-vealed that the corison reference leg to the torus level transmitters, LT-16-19-38A/B was n'at full. This canned the level indicators to show a higher than actual 1evel. Upon refilling the reference leg, the actual 1

level indicated a vol4.ine of only 65,200 cubic feet. Technical Specifi-cation Section 3.7.A.1,.e requires a minimum volume of 68,000 cubic feet.

Preparations for an orlierly reactor shutdown were initiated as well as efforts to refill the torus to the required volume. The torus was re-stored to its required irolume approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> af ter the discovery.

Since the volume was requced to within a few percentage points of the required volume and for gnly a short time period, the potential conse-quences to the health and, safety of the pttblic were minimal. There were no previously reported sitsilar occurrences.

CAUSE DESCRIPTION AND CORRE'CTIVE ACTION The cause of this occurkence is attributed to loss of water in the reference leg of the torus level transmitters. This caused an apparent level that was higher than the actual level. The reason the reference leg decreased has not been deiermined. The reference leg,has been moni-tored for the last few weeks to verify that there is no significant change in icvel during normal station operation. This event is consid-ered an isolated incident and no further corrective action is planned.

,