ML18082B347: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:.. 17-771 | {{#Wiki_filter:.. | ||
17-771 CONTROL BLOCK: | |||
[il:I] IN I J Is I G*I sl l 101 o I o I. o I o I | [il:I] IN I J Is I G*I sl l 101 o I o I. | ||
@ * . /During a record.review in preparation for a reactor startup, it was determined that ' [[]]] !the required inservice inspection surveillance of valves per Technical Specification . I | I 1 | ||
Similar []]!] 1occurrences include 76-03, 78-21, 78-81, 80-10 and 80-33. . J um 7 8 9 SYSTEM CAUSE CAUSE COMP. V.C.LVE CODE | * I. | ||
/::;':;\ ATTACHMENT NPRD-4 PRIME COMP. | LICENSEE EVENT REPORT 10 6 | ||
The surveillance was completed and an on-the-spot rrm !Change issued to Operating Ins'!:rUction* | e (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION! | ||
I-3.3, Hot Standby to Minimum Load, to add this OJiJ jsurveillance to the mode change checklist. | ~I o I o I oIO I o I - I o I o IG)l4 I i I l I i I l l©I I I@ | ||
lilil 7 8 9 FACILITY | 7 8 9 LICENSEE cone 14 15 . LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T | ||
[ITJJ 7 8 | |||
~~~~~; UJ©I ol s I oIo I oI 2 I I 2 GI o I 1 9 I i I o I 0 I o 1@11 I o 11 I o I a I o 10 60 68 6169 DOCKET NUMBER EVENT DATE 74 75 REPORT CATE BO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES @ * . | |||
/During a record.review in preparation for a reactor startup, it was determined that | |||
' | |||
[[]]] !the required inservice inspection surveillance of valves per Technical Specification .I | |||
~ !4.0.S had not been completed, as required at the previous reactor shutdown. | |||
. Similar | |||
Loss OF OR OAMAGE TO FACILITY '43' | []]!] 1occurrences include 76-03, 78-21, 78-81, 80-10 and 80-33. .J um 7 8 9 80 SYSTEM CAUSE CAUSE COMP. V.C.LVE rim 7 B 9 CODE 1z 1z 1@ 1£.J@ w@ 1v IA IL 1v IE 1x 10 CODE 11 SUSCODE 12 13 COMPONENT CODE 18 1e SUBCOOE Ll.J@ | ||
19 SUBCOOE w | |||
(.:\ NRC USE ONLY | 20 SEQUENTIAL OCCURRENCE REPORT REVISION t::;\ LE R RO *cVENT YEAR REP.ORT NO. CODE TYPE NC. | ||
*"-.:.JRePoRr NUMBEFI I0lol 21 22 I*! | |||
23 lolsl2! | |||
24 26 I/I 27 lo 13 I 28 29 W | |||
30 1-1 31 . | |||
LQJ 32 ACTION FUTURE EFFECT SHUTDOWlll /::;':;\ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKE'.; ACTION ON PLANT METHOO HOURS ~ SUBMITTED FORM ::.uB. SUPPLIER MANUFACTURER E...J@W@ W@ W I o Io I 0.1 o I L!J@ L!J@ ~@) I z 19 19 19 I@ | |||
33 34 35 36 37 40 41 42 43 .. 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @ | |||
*o::Ir]* !The surveillance is scheduled on a calendar basis and does not accommodate the II:DJ jcontingency of a reactor shutdown. The surveillance was completed and an on-the-spot rrm !Change issued to Operating Ins'!:rUction* I-3.3, Hot Standby to Minimum Load, to add this OJiJ jsurveillance to the mode change checklist. | |||
lilil 7 8 9 80 FACILITY STATUS '!GPOWER OTHERSTATUS ~ | |||
l3Q\ METHOD OF DISCOVERY DISCOVERY DESCRIPTION | |||
32 ITJII ~ I 0 I 0 I 0 l@l.....___N.._/A_ _ _, l.£.JQD~l ___________R~e~c~o~r~d~Re.;;;..;.v~i~e_w__________. | |||
: 7. B 9 10 12 l'l 44 45 46 80 ACTIVITY CONTENT ~ | |||
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @) | |||
QJI] L!.I L!J@I N/A N/A 7 8 9 10 It BO PERSONNEL EXPOSURES t::;::<., | |||
~TYPE DESCRIPTION ~ | |||
rrrn 1 a 1 o 1 a 10~..________N...:A~---------------------- | |||
NUMBER | |||
, B 9 11 12 13 . BO PERSONNEL INJURIES t:°:\ | |||
NUMBER DESCRIPTION~ | |||
IT:GJ 7 8 I9 0 I 0 I 0 I@ | |||
11 ~ 1 2 | |||
. NA | |||
__.._________....,:::..,:;:____________...______________________________ ~ - - - - - - - - - - - - ~ B O Loss OF OR OAMAGE TO FACILITY TVPE DESCRIPTION ~ | |||
'43' ITI2J ~@)l-...~~~---~N~A:___ _ _~~~--~~~---~~----~ | |||
7 B 9 10 .SO PUBLICITY (.:\ NRC USE ONLY | |||
~ ISSUEOc:;\ OESCRIPTION ~ | |||
~w~ | |||
7 8 9 10. | |||
. NA 68 I I I I I I I I I I I I I~ | |||
&9 80 "* | |||
"' | |||
J. M. Randolph 609-935-0998 ~ | |||
NAMEOFPREPARER----~-~--------------------- PHONE: .;. | |||
(j 010200 !s'I ~ - ---- -~- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ J}} | |||
Revision as of 14:04, 21 October 2019
| ML18082B347 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 10/10/1980 |
| From: | Randolph J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML18082B345 | List: |
| References | |
| LER-80-052-03L, LER-80-52-3L, NUDOCS 8010200592 | |
| Download: ML18082B347 (1) | |
Text
..17-771 CONTROL BLOCK:
[il:I] IN I J Is I G*I sl l 101 o I o I.
I 1
- I.
LICENSEE EVENT REPORT 10 6
e (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
~I o I o I oIO I o I - I o I o IG)l4 I i I l I i I l l©I I I@
7 8 9 LICENSEE cone 14 15 . LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T
[ITJJ 7 8
~~~~~; UJ©I ol s I oIo I oI 2 I I 2 GI o I 1 9 I i I o I 0 I o 1@11 I o 11 I o I a I o 10 60 68 6169 DOCKET NUMBER EVENT DATE 74 75 REPORT CATE BO EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES @ * .
/During a record.review in preparation for a reactor startup, it was determined that
'
[[]]] !the required inservice inspection surveillance of valves per Technical Specification .I
~ !4.0.S had not been completed, as required at the previous reactor shutdown.
. Similar
[]]!] 1occurrences include 76-03, 78-21, 78-81, 80-10 and 80-33. .J um 7 8 9 80 SYSTEM CAUSE CAUSE COMP. V.C.LVE rim 7 B 9 CODE 1z 1z 1@ 1£.J@ w@ 1v IA IL 1v IE 1x 10 CODE 11 SUSCODE 12 13 COMPONENT CODE 18 1e SUBCOOE Ll.J@
19 SUBCOOE w
20 SEQUENTIAL OCCURRENCE REPORT REVISION t::;\ LE R RO *cVENT YEAR REP.ORT NO. CODE TYPE NC.
- "-.:.JRePoRr NUMBEFI I0lol 21 22 I*!
23 lolsl2!
24 26 I/I 27 lo 13 I 28 29 W
30 1-1 31 .
LQJ 32 ACTION FUTURE EFFECT SHUTDOWlll /::;':;\ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKE'.; ACTION ON PLANT METHOO HOURS ~ SUBMITTED FORM ::.uB. SUPPLIER MANUFACTURER E...J@W@ W@ W I o Io I 0.1 o I L!J@ L!J@ ~@) I z 19 19 19 I@
33 34 35 36 37 40 41 42 43 .. 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @
- o::Ir]* !The surveillance is scheduled on a calendar basis and does not accommodate the II:DJ jcontingency of a reactor shutdown. The surveillance was completed and an on-the-spot rrm !Change issued to Operating Ins'!:rUction* I-3.3, Hot Standby to Minimum Load, to add this OJiJ jsurveillance to the mode change checklist.
lilil 7 8 9 80 FACILITY STATUS '!GPOWER OTHERSTATUS ~
l3Q\ METHOD OF DISCOVERY DISCOVERY DESCRIPTION
32 ITJII ~ I 0 I 0 I 0 l@l.....___N.._/A_ _ _, l.£.JQD~l ___________R~e~c~o~r~d~Re.;;;..;.v~i~e_w__________.
- 7. B 9 10 12 l'l 44 45 46 80 ACTIVITY CONTENT ~
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @)
QJI] L!.I L!J@I N/A N/A 7 8 9 10 It BO PERSONNEL EXPOSURES t::;::<.,
~TYPE DESCRIPTION ~
rrrn 1 a 1 o 1 a 10~..________N...:A~----------------------
NUMBER
, B 9 11 12 13 . BO PERSONNEL INJURIES t:°:\
NUMBER DESCRIPTION~
IT:GJ 7 8 I9 0 I 0 I 0 I@
11 ~ 1 2
. NA
__.._________....,:::..,:;:____________...______________________________ ~ - - - - - - - - - - - - ~ B O Loss OF OR OAMAGE TO FACILITY TVPE DESCRIPTION ~
'43' ITI2J ~@)l-...~~~---~N~A:___ _ _~~~--~~~---~~----~
7 B 9 10 .SO PUBLICITY (.:\ NRC USE ONLY
~ ISSUEOc:;\ OESCRIPTION ~
~w~
7 8 9 10.
. NA 68 I I I I I I I I I I I I I~
&9 80 "*
"'
J. M. Randolph 609-935-0998 ~
NAMEOFPREPARER----~-~--------------------- PHONE: .;.
(j 010200 !s'I ~ - ---- -~- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ J