ML19305C061: Difference between revisions
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{{#Wiki_filter:NRC FORM 364 U. S. NUCLEAO R E!ULATCY COMMISSION | {{#Wiki_filter:NRC FORM 364 U. S. NUCLEAO R E!ULATCY COMMISSION | ||
. . LICENSEE EVENT REPORT CONTROL eLOCx: l l l l l l l (PLEAsE PRINT OR TYPE ALL REQUIRED INFCCMATION) | . . LICENSEE EVENT REPORT CONTROL eLOCx: l l l l l l l (PLEAsE PRINT OR TYPE ALL REQUIRED INFCCMATION) | ||
FTil IC I O I r IS lv l1 Ig o lo l- Io lo Io Io lo I- JO lo Igl 4I 11 25 26 1l 2t oggi57 CAT uCENSE TYPE Jo l | FTil IC I O I r IS lv l1 Ig o lo l- Io lo Io Io lo I- JO lo Igl 4I 11 25 26 1l 2t oggi57 CAT uCENSE TYPE Jo l | ||
68 lg 7 8 9 UCENSEE CODE 14 15 uCENSE NLMBER J | 68 lg 7 8 9 UCENSEE CODE 14 15 uCENSE NLMBER J | ||
CON'T | CON'T lol11 $$y","CE l L @l 0 l 510 l 0 l 0 l 2 l 6 l 7 @l 0 l 211 l 8 l 8 l74o l@l0 75 lRE,3 ORT l1 CATE l 9 l 81080 l@ - | ||
lol11 $$y","CE l L @l 0 l 510 l 0 l 0 l 2 l 6 l 7 @l 0 l 211 l 8 l 8 l74o l@l0 75 lRE,3 ORT l1 CATE l 9 l 81080 l@ - | |||
i 8 60 St DOCKET NUMagR 68 69 EVENT DATE EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h lTITI l On February 18, 1980, with the reactor critical at less than 2Z power, it was l ITTTII determined that a vent stack snubber, VSS-117, was inoperable and a degraded mode of I lo l4I I Fo rt S t. Vrain Technical Specification LCO 4.3.10 existed. This is reportable per I ITTTI l Fort St. Vrain Technical Specification AC 7.5.2(b)3. The reactor was taken sub- l ! | i 8 60 St DOCKET NUMagR 68 69 EVENT DATE EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h lTITI l On February 18, 1980, with the reactor critical at less than 2Z power, it was l ITTTII determined that a vent stack snubber, VSS-117, was inoperable and a degraded mode of I lo l4I I Fo rt S t. Vrain Technical Specification LCO 4.3.10 existed. This is reportable per I ITTTI l Fort St. Vrain Technical Specification AC 7.5.2(b)3. The reactor was taken sub- l ! | ||
iTTii1 I critical and remained suberitical till the snubber was replaced. No accompanying oc-l lo til I currence. No affect on public health or safety. A similar occurrence was RO 79-64. l I | iTTii1 I critical and remained suberitical till the snubber was replaced. No accompanying oc-l lo til I currence. No affect on public health or safety. A similar occurrence was RO 79-64. l I | ||
10181 1 so 7 es CE oE SU C E COMPONENT CODE 508 DE SU E lTI n I A l A lh [A_jh l C lh l Sl Ul Pl 0l Rl Tlh Wh [_Z_j h 13 18 19 20 7 8 9 10 11 12 SEQUENTIAL OCCURRENCE REPORT REVISION | 10181 1 so 7 es CE oE SU C E COMPONENT CODE 508 DE SU E lTI n I A l A lh [A_jh l C lh l Sl Ul Pl 0l Rl Tlh Wh [_Z_j h 13 18 19 20 7 8 9 10 11 12 SEQUENTIAL OCCURRENCE REPORT REVISION gggjag EVENTYEAR REPCRT No. CCCE TYPE No. | ||
@ ,a,Eg L--J lo Io I6 I l-l I oI 3i L_t_] l--J lo I l21 81 22 01 23 24 26 27 28 29 30 31 32 K N A P T MET HOURS 58 81 7 FoR 8. SUP L MA UFA RER lH l@W@ | |||
gggjag EVENTYEAR REPCRT No. CCCE TYPE No. | |||
@ ,a,Eg L--J lo Io I6 I l-l I oI 3i L_t_] l--J lo I l21 81 22 01 23 24 26 27 28 29 30 31 32 | |||
K N A P T MET HOURS 58 81 7 FoR 8. SUP L MA UFA RER lH l@W@ | |||
33 34 l35Z l@ l36Z l@ l0l0l0l0l 37 40 | 33 34 l35Z l@ l36Z l@ l0l0l0l0l 37 40 | ||
[Y_j@ | [Y_j@ | ||
Line 41: | Line 34: | ||
, l taken critical with operations personnel unaware that VSS-117 had been removed. I gl Personnel involved were reprimanded and the igortance of following approved pro- l gl cedures re-emphasized. No other corrective action anticipated or required. I 7 e e s0 A 4 POWER OTHER STAT 1.is 01 MY Disco 4ERY DESCRI TION i 5 (_C,_j @ lo 10 11 l @ lN/A l W@l Plant Personnel Observation l 1 | , l taken critical with operations personnel unaware that VSS-117 had been removed. I gl Personnel involved were reprimanded and the igortance of following approved pro- l gl cedures re-emphasized. No other corrective action anticipated or required. I 7 e e s0 A 4 POWER OTHER STAT 1.is 01 MY Disco 4ERY DESCRI TION i 5 (_C,_j @ lo 10 11 l @ lN/A l W@l Plant Personnel Observation l 1 | ||
. g y,, g ,,,, u n 44 . . .o REtmEo o, REtmE tocatioN o, REtmE @ | . g y,, g ,,,, u n 44 . . .o REtmEo o, REtmE tocatioN o, REtmE @ | ||
E i s 4 ouuTo ,cTiviTv @ l I 8/A I | E i s 4 ouuTo ,cTiviTv @ l I 8/A I Lz_l | ||
Lz_l | |||
@ Iz l@l 8/^ " * " | @ Iz l@l 8/^ " * " | ||
,moNNE Ex,os&',Es l N ER l i Q r l l 0 ] 0 l 0 ZlhlTv,E@leEscMirnoN @ | ,moNNE Ex,os&',Es l N ER l i Q r l l 0 ] 0 l 0 ZlhlTv,E@leEscMirnoN @ | ||
l N/A l l ' m. o NEi. % UJiEs N ER oE,cR,,T,.@ | |||
l N/A l | |||
l ' m. o NEi. % UJiEs N ER oE,cR,,T,.@ | |||
i i l 1010 l o l@l N/A " | i i l 1010 l o l@l N/A " | ||
'' esso,omol',"cE"o ,AciuTv W | |||
'' esso,omol',"cE"o ,AciuTv | Tm U_LJ8 9LzJ@l10s/A 7 | ||
=EscR '" | =EscR '" | ||
O0 34 50 I | O0 34 50 I | ||
,,J'''itscR,,T,oN @ ~acuseca'v . | ,,J'''itscR,,T,oN @ ~acuseca'v . | ||
u.W | u.W lx O N/A - i I!iltiliti!'ll (awe c, ,RE,,RER MV8 ,~cN E: Em$'ns-2253 ~!}} | ||
lx O N/A - i I!iltiliti!'ll (awe c, ,RE,,RER MV8 ,~cN E: Em$'ns-2253 ~!}} |
Latest revision as of 13:50, 1 February 2020
ML19305C061 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 03/19/1980 |
From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
Shared Package | |
ML19305C059 | List: |
References | |
LER-80-006-03L, LER-80-6-3L, NUDOCS 8003250537 | |
Download: ML19305C061 (1) | |
Text
NRC FORM 364 U. S. NUCLEAO R E!ULATCY COMMISSION
. . LICENSEE EVENT REPORT CONTROL eLOCx: l l l l l l l (PLEAsE PRINT OR TYPE ALL REQUIRED INFCCMATION)
FTil IC I O I r IS lv l1 Ig o lo l- Io lo Io Io lo I- JO lo Igl 4I 11 25 26 1l 2t oggi57 CAT uCENSE TYPE Jo l
68 lg 7 8 9 UCENSEE CODE 14 15 uCENSE NLMBER J
CON'T lol11 $$y","CE l L @l 0 l 510 l 0 l 0 l 2 l 6 l 7 @l 0 l 211 l 8 l 8 l74o l@l0 75 lRE,3 ORT l1 CATE l 9 l 81080 l@ -
i 8 60 St DOCKET NUMagR 68 69 EVENT DATE EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h lTITI l On February 18, 1980, with the reactor critical at less than 2Z power, it was l ITTTII determined that a vent stack snubber, VSS-117, was inoperable and a degraded mode of I lo l4I I Fo rt S t. Vrain Technical Specification LCO 4.3.10 existed. This is reportable per I ITTTI l Fort St. Vrain Technical Specification AC 7.5.2(b)3. The reactor was taken sub- l !
iTTii1 I critical and remained suberitical till the snubber was replaced. No accompanying oc-l lo til I currence. No affect on public health or safety. A similar occurrence was RO 79-64. l I
10181 1 so 7 es CE oE SU C E COMPONENT CODE 508 DE SU E lTI n I A l A lh [A_jh l C lh l Sl Ul Pl 0l Rl Tlh Wh [_Z_j h 13 18 19 20 7 8 9 10 11 12 SEQUENTIAL OCCURRENCE REPORT REVISION gggjag EVENTYEAR REPCRT No. CCCE TYPE No.
@ ,a,Eg L--J lo Io I6 I l-l I oI 3i L_t_] l--J lo I l21 81 22 01 23 24 26 27 28 29 30 31 32 K N A P T MET HOURS 58 81 7 FoR 8. SUP L MA UFA RER lH l@W@
33 34 l35Z l@ l36Z l@ l0l0l0l0l 37 40
[Y_j@
41 lN 42 l@ l43A l@ lI l2 l0 l7 l@
44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
gl VSS-117, a vent stack snubber, was removed from service during a maintenance shut- I
['iTO l dcwn without informing the Shif t Supervisor. On February 17, 1980, the reactor was I
, l taken critical with operations personnel unaware that VSS-117 had been removed. I gl Personnel involved were reprimanded and the igortance of following approved pro- l gl cedures re-emphasized. No other corrective action anticipated or required. I 7 e e s0 A 4 POWER OTHER STAT 1.is 01 MY Disco 4ERY DESCRI TION i 5 (_C,_j @ lo 10 11 l @ lN/A l W@l Plant Personnel Observation l 1
. g y,, g ,,,, u n 44 . . .o REtmEo o, REtmE tocatioN o, REtmE @
E i s 4 ouuTo ,cTiviTv @ l I 8/A I Lz_l
@ Iz l@l 8/^ " * "
,moNNE Ex,os&',Es l N ER l i Q r l l 0 ] 0 l 0 ZlhlTv,E@leEscMirnoN @
l N/A l l ' m. o NEi. % UJiEs N ER oE,cR,,T,.@
i i l 1010 l o l@l N/A "
esso,omol',"cE"o ,AciuTv W
Tm U_LJ8 9LzJ@l10s/A 7
=EscR '"
O0 34 50 I
,,JitscR,,T,oN @ ~acuseca'v .
u.W lx O N/A - i I!iltiliti!'ll (awe c, ,RE,,RER MV8 ,~cN E: Em$'ns-2253 ~!