ML19322E374: Difference between revisions
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{{#Wiki_filter:NRC FORM 366 8. 6 L&Mhtysd Las@@LL46Vsuv m (7 77) ' | {{#Wiki_filter:NRC FORM 366 8. 6 L&Mhtysd Las@@LL46Vsuv m (7 77) ' | ||
LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l0 l1l8 l9 Ml Al Pl P! Sl 1l@l 14 015 l 0 l -l 0 l 0LICENSEl 0 l NUMBER 0 l 0 l - l 0 l 0 l@l 25 426 l 1 LICENSE l 1 l 1TYPE l l 1 Jul@l 57 CAT bd l@ | LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l0 l1l8 l9 Ml Al Pl P! Sl 1l@l 14 015 l 0 l -l 0 l 0LICENSEl 0 l NUMBER 0 l 0 l - l 0 l 0 l@l 25 426 l 1 LICENSE l 1 l 1TYPE l l 1 Jul@l 57 CAT bd l@ | ||
7 LICENSEE CODE f CON'T | 7 LICENSEE CODE f CON'T lolil 7 8 3ouRMlLl@l 0l5]01-]0l2]9l3l@l01310l8l8lOl@l0]3121Ol8l0l@ | ||
lolil 7 8 3ouRMlLl@l 0l5]01-]0l2]9l3l@l01310l8l8lOl@l0]3121Ol8l0l@ | |||
60 61 DOCK ET NUMBER 68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 121 l On March 8, 1980 during the 0001-0800 hour shift. irradiated fuel was moved within l l the fuel pool. Prior to moving this fuel, routine evaluation of the availability l | 60 61 DOCK ET NUMBER 68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 121 l On March 8, 1980 during the 0001-0800 hour shift. irradiated fuel was moved within l l the fuel pool. Prior to moving this fuel, routine evaluation of the availability l | ||
.I o 131 1 l of required equipment was satisfactorily completed. Review of this decision de- I | .I o 131 1 l of required equipment was satisfactorily completed. Review of this decision de- I | ||
,l o 14 I l termined that due to a procedural inadequacy, this decision was inaccurate. Plans y | ,l o 14 I l termined that due to a procedural inadequacy, this decision was inaccurate. Plans y | ||
]o l6 l l I l | ]o l6 l l I l | ||
10171 I l O l8 l l ] | 10171 I l O l8 l l ] | ||
SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8 CODE COMFvNENT CODE SUSCODE SUSCODE loisi I Z I Z I@ l D l@ l Z l@ lZ lZ lZ lZ l Zl Zl@ ]@ [Zj @ 18 19 20 7 8 9 10 11 12 13 SEQUE NTI AL OCCURRENCE REPORT REVISION | SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8 CODE COMFvNENT CODE SUSCODE SUSCODE loisi I Z I Z I@ l D l@ l Z l@ lZ lZ lZ lZ l Zl Zl@ ]@ [Zj @ 18 19 20 7 8 9 10 11 12 13 SEQUE NTI AL OCCURRENCE REPORT REVISION EVENT YE AR REPORT NO. CODE TYPE NO. | ||
EVENT YE AR REPORT NO. CODE TYPE NO. | |||
LER RO | LER RO | ||
@ sgg I 81 0l a | @ sgg I 81 0l a | ||
Line 45: | Line 39: | ||
l i l 71 1010101@l Z l@l N.A. | l i l 71 1010101@l Z l@l N.A. | ||
80 | 80 | ||
,ERSONNEL mau'R,,, | ,ERSONNEL mau'R,,, | ||
2 i3 NUMBER DESCRIPTION . | 2 i3 NUMBER DESCRIPTION . | ||
N.A. | N.A. | ||
I1 i a 8 9 l0l0l0l@l 11 12 80 l | I1 i a 8 9 l0l0l0l@l 11 12 80 l | ||
' ^" ' | ' ^" ' | ||
W.5E USC #1 JN '''' " " @ C 0 " 3 2 7 0.3 7-- 7 N.A. | W.5E USC #1 JN '''' " " @ C 0 " 3 2 7 0.3 7-- 7 N.A. | ||
Line 59: | Line 51: | ||
N A*.* E OF PRE 3 AR E 4 PHONE. 3 | N A*.* E OF PRE 3 AR E 4 PHONE. 3 | ||
~ | ~ | ||
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION | BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 i | ||
Attachment to LER Sd-008/01T , | Attachment to LER Sd-008/01T , | ||
On March 8,1980 fuel was moved within the fuel pool without prior satisfaction of Technical Specification requirements. | On March 8,1980 fuel was moved within the fuel pool without prior satisfaction of Technical Specification requirements. | ||
A review of the plant's status revealed that: | A review of the plant's status revealed that: | ||
1 | 1 | ||
: 1. Secondary containment was not established and, | : 1. Secondary containment was not established and, | ||
: 2. The automatic ' function of the diesel generators was impaired. - | : 2. The automatic ' function of the diesel generators was impaired. - | ||
Prior to moving fuel, the establishment of Secondary Containment must be ensured by the successful completion of Station Procedure Number 8.7.3.1 entitled | Prior to moving fuel, the establishment of Secondary Containment must be ensured by the successful completion of Station Procedure Number 8.7.3.1 entitled | ||
Line 76: | Line 63: | ||
'in prepa ation for de-fueling of the reactor vessel on January 5,1980 and is scheduled for repetition prior to refueling the vessel. However, this test is , | 'in prepa ation for de-fueling of the reactor vessel on January 5,1980 and is scheduled for repetition prior to refueling the vessel. However, this test is , | ||
also required prior to moving fuel within the confines of the fuel pool. | also required prior to moving fuel within the confines of the fuel pool. | ||
l l | l l | ||
The diesel generators, although functional, were configured so that operator i action would be required to switch the emergency, A5&A6, 4 KV bus loads. This j action was taken as a precaution to prevent the diesels from being switched onto a live, out of phase bus. Electrical work was being performed on the 345KV lines and the shutdown transformer was supplying the station load. This precaution would not prevent an automatic start of the diesel generator but would have prevented the diesel generator from automatically accepting the station load. | The diesel generators, although functional, were configured so that operator i action would be required to switch the emergency, A5&A6, 4 KV bus loads. This j action was taken as a precaution to prevent the diesels from being switched onto a live, out of phase bus. Electrical work was being performed on the 345KV lines and the shutdown transformer was supplying the station load. This precaution would not prevent an automatic start of the diesel generator but would have prevented the diesel generator from automatically accepting the station load. | ||
Corrective Action Immediately upon assessment of the situation, fuel movement was prohibited and the following actions were taken. | Corrective Action Immediately upon assessment of the situation, fuel movement was prohibited and the following actions were taken. | ||
: 1. , Secondary containment leak rate testing was initiat.a This test was sat-isfactorily completed on March 20, 1980. | : 1. , Secondary containment leak rate testing was initiat.a This test was sat-isfactorily completed on March 20, 1980. | ||
Line 85: | Line 70: | ||
: 3. Station electrical loading was returned to normal. The diesel generator satisfactorily testel and declared operable. | : 3. Station electrical loading was returned to normal. The diesel generator satisfactorily testel and declared operable. | ||
: 4. Discussions were held with licensed personnel to apprise them of the situation and preclude its repetition. The operator training plan will in-clude review of this situation. | : 4. Discussions were held with licensed personnel to apprise them of the situation and preclude its repetition. The operator training plan will in-clude review of this situation. | ||
i | i | ||
( | ( | ||
i l | i l | ||
l l | l l | ||
.-}} | .-}} |
Revision as of 03:51, 1 February 2020
ML19322E374 | |
Person / Time | |
---|---|
Site: | Pilgrim |
Issue date: | 03/20/1980 |
From: | Mcloughlin M BOSTON EDISON CO. |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
Shared Package | |
ML19322E373 | List: |
References | |
LER-80-008-01T, LER-80-8-1T, NUDOCS 8003270327 | |
Download: ML19322E374 (2) | |
Text
{{#Wiki_filter:NRC FORM 366 8. 6 L&Mhtysd Las@@LL46Vsuv m (7 77) ' LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l0 l1l8 l9 Ml Al Pl P! Sl 1l@l 14 015 l 0 l -l 0 l 0LICENSEl 0 l NUMBER 0 l 0 l - l 0 l 0 l@l 25 426 l 1 LICENSE l 1 l 1TYPE l l 1 Jul@l 57 CAT bd l@ 7 LICENSEE CODE f CON'T lolil 7 8 3ouRMlLl@l 0l5]01-]0l2]9l3l@l01310l8l8lOl@l0]3121Ol8l0l@ 60 61 DOCK ET NUMBER 68 69 EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 121 l On March 8, 1980 during the 0001-0800 hour shift. irradiated fuel was moved within l l the fuel pool. Prior to moving this fuel, routine evaluation of the availability l .I o 131 1 l of required equipment was satisfactorily completed. Review of this decision de- I ,l o 14 I l termined that due to a procedural inadequacy, this decision was inaccurate. Plans y
]o l6 l l I l
10171 I l O l8 l l ] SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8 CODE COMFvNENT CODE SUSCODE SUSCODE loisi I Z I Z I@ l D l@ l Z l@ lZ lZ lZ lZ l Zl Zl@ ]@ [Zj @ 18 19 20 7 8 9 10 11 12 13 SEQUE NTI AL OCCURRENCE REPORT REVISION EVENT YE AR REPORT NO. CODE TYPE NO. LER RO
@ sgg I 81 0l a
22 l-l 23 10 10 18 I 24 26 l/l 27 10 11 I 28 29 lTl Jo l-l 31 10 l 32 _ 21 AK N AC N ON PL NT METH HOURS SB IT D FOR B. SU PP LI E MAN FACTURER l G l@j34X l@ l3bZ [@ lZ l@ l0 l0 l0 l0 l 31 lYl@ 41 lN l@ l43 Zl@ lZl919l9l@ 33 36 40 42 44 47 CAUSE DESCRIPTION AND CC9RECTIVE ACTIONS h Ii iO I l -__ l Refer to Attachment. , li 121 l I l 11 131 I 1 11 141 l 7 8 9 80
$A S % POWER OTHER STATUS DIS O RY DISCOVERY DESCRIPTION l115 l l H l@ l0 l0 l0 l@l N.A. l y @l Management Review l ACTIVITY CC TENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOC ATION OF RELE ASE N.A. l l N.A. l l1 l68 l9 W @ lZ l@l 7 10 11 44 45 80 PERSONNEL EXPOSURES NUV8ER TYPE DESCRIPTION I
l i l 71 1010101@l Z l@l N.A. 80
,ERSONNEL mau'R,,,
2 i3 NUMBER DESCRIPTION . N.A. I1 i a 8 9 l0l0l0l@l 11 12 80 l
' ^" '
W.5E USC #1 JN ' " " @ C 0 " 3 2 7 0.3 7-- 7 N.A.
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lZl@l 3 to 80 l I N.A. [[]llllllllllf !7 DT5]8 9S3EE@ 1 l 10 DESCRIPTION l 63 69 30 3 M. Thomas McLoughlin 617-746-7900 ? N A*.* E OF PRE 3 AR E 4 PHONE. 3
~
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 i Attachment to LER Sd-008/01T , On March 8,1980 fuel was moved within the fuel pool without prior satisfaction of Technical Specification requirements. A review of the plant's status revealed that: 1
- 1. Secondary containment was not established and,
- 2. The automatic ' function of the diesel generators was impaired. -
Prior to moving fuel, the establishment of Secondary Containment must be ensured by the successful completion of Station Procedure Number 8.7.3.1 entitled
" Secondary Containment Leak Rate Test". This test was satisfactorily performed 'in prepa ation for de-fueling of the reactor vessel on January 5,1980 and is scheduled for repetition prior to refueling the vessel. However, this test is ,
also required prior to moving fuel within the confines of the fuel pool. l l The diesel generators, although functional, were configured so that operator i action would be required to switch the emergency, A5&A6, 4 KV bus loads. This j action was taken as a precaution to prevent the diesels from being switched onto a live, out of phase bus. Electrical work was being performed on the 345KV lines and the shutdown transformer was supplying the station load. This precaution would not prevent an automatic start of the diesel generator but would have prevented the diesel generator from automatically accepting the station load. Corrective Action Immediately upon assessment of the situation, fuel movement was prohibited and the following actions were taken.
- 1. , Secondary containment leak rate testing was initiat.a This test was sat-isfactorily completed on March 20, 1980.
I 2. A revision to Station procedure number 4.3 entitled " Fuel Handlin~g" was initiated to provide detailed instruc'tions for operators for the moving i of fuel within the fuel pool. -
- 3. Station electrical loading was returned to normal. The diesel generator satisfactorily testel and declared operable.
- 4. Discussions were held with licensed personnel to apprise them of the situation and preclude its repetition. The operator training plan will in-clude review of this situation.
i ( i l l l
.-}}