ML18219B572: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:g~/~g/~REGULATORY INFORMATION DISTRIBUTION SYSTEM<RIDS)DISTRIBUTION FOR INCOMING'MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 07/11/78 NRC lN 5 Ml PWR DATE RCVD: 07/14/78 DOCTYPE: LETTER NOTARIZED: | {{#Wiki_filter:g ~/~g/~ | ||
NO COPIES RECEIVED | REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS) | ||
DISTRIBUTION FOR INCOMING 'MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 07/11/78 NRC lN 5 Ml PWR DATE RCVD: 07/14/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED | |||
==SUBJECT:== | ==SUBJECT:== | ||
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034) | LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034) ON 05/15/78 CONCERNING DURING SURVEILLANCE TESTS ON 05/15/78 8. 06/20/78) THE HYDROGEN SKIMMER RECIRCULATION FANS (2HV-CEQi 8( 2-HV-CEQ2) FAILED TO START WITHIN TECH SPEC REQUIREMENT 4. 6. 5. 6. A... W/ATT LER 7Q -Q9"f ] '7B" ~V+ > | ||
ON 05/15/78 CONCERNING DURING SURVEILLANCE TESTS ON 05/15/78 8.06/20/78)THE HYDROGEN SKIMMER RECIRCULATION FANS (2HV-CEQi 8(2-HV-CEQ2) | + 7 | ||
FAILED TO START WITHIN TECH SPEC REQUIREMENT 4.6.5.6.A...W/ATT LER 7Q-Q9"f]'7B"~V+>+7>~k'LANT NAME: COOK | >~k'LANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL: | ||
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS+4>+>>~+>>>>+>>>+> | ++++~>+++++++4+4l+> DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +4>+>>~+>>>>+>>>+> | ||
NOTES: 1.SEND 3 COPIES OF ALL MATERIAL TO lhE ED REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)FOR ACTION: | NOTES: | ||
ENCL K SEYFRIT/IE++W/ENCL LPDR'8 ST.JOSEPH'I+4 | : 1. SEND 3 COPIES OF ALL MATERIAL TO lhE ED REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002) | ||
LTR 45 ENCL 45 , SIZE: 1P+1P+3P',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%% | FOR ACTION: BR CHIE W ¹2 BC+4W/4 ENCL INTERNAL: R G FILE+4W/E NRC PDR++W/ENCL I 5 E~~ ENCL, MIPC~~W/3 ENCL I 8( C SYSTEMS BR+%W/ENCL EMERGENCY PLAN BR++W/ENCL NOVAK/CHECK~+W/ENCL EEB++W/ENCL AD FOR ENG~~~~W/ ENCL PLANT SYSTEMS BR<<W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL AD FOR SYS 8( PROJ+4W/ENCL REACTOR SAFETY BR<+W/ENCL ENGINEERING BR++W/ENCL VOLLMER/BUNCH++M/ENCL KREGER/J. COLLINS<~W/ENCL POWER SYS BRwmW/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'8 ST. JOSEPH' I +4 WfENCL | ||
'ERA>+W/ENCL NSIC~~W/ENCL ACRS CAT B++W/16,ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7819500 4 | |||
, | |||
SIZE: 1P+1P+3P | |||
',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%% THE END | |||
I A | |||
h 4 4 4 N | |||
I 'I 11 tt | |||
'b i1 | |||
erloen | |||
+ CI~ ~ | |||
y>ccI IND/ANA & NICHIGAN PD %EH COMP N Y C7 DONALD C. COOK NUCLEAR PLANT C+ | |||
r'a P.O. Box 458, Bridgman, Michigan 49106 t C.> "! | |||
CrC r v C'ql | |||
%CD July 11, 1978 >~a rC-C CD CA CO C/)CD D Pl C".. X Mr. J.G. Keppler, Regional Director C/l CD Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316 | |||
~ | |||
==Dear Mr. Keppler:== | |||
~ | Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted: | ||
~ | RO 78-034/03L-1 RO 78-044/03L-0 RO 78-045/03L-0 RO 78-046/03L-0 Sincerely, D.V. Shaller Plant Manager | ||
/bab CC: J.E. Dolan R.W. Jur gensen R.F. Kroeger R. Kilburn | |||
,R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq. | |||
R. Walsh, Esq. | |||
G. Charnoff, Esq. | |||
PNSRC J.F. Stietzel JUP ].g 1978 R.S. Keith Dir., IE (30 copies) | |||
~ | Dir., MIPC (3 copies) | ||
~ | |||
~ | "0 W | ||
L( | |||
V u | |||
( NRC FOR0/I 366 | |||
~ | ) | ||
(7') "UPDAT~EPORT - PREVIOUS REPORT DATE LICENSE E EV EN T R E PORT 6/ I CONTROL BLOCK: | |||
~ | 1 ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) | ||
~oi 7 8 9 M I D I.ICENSEE CODE C C 2 14 2 | |||
15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Q 3 26 4 1 1 LICENSE TYPE 1 1 30 Q4~QE 57 CAT 58 CON'T | |||
~O REPoRT | |||
~LQ6 P 5 P P P 3 1 6 Q7 0 5 1 5 7 8 QB 0 / I I / 8 Q 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 DURING SURVEILLANCE TESTS ON 5-15-78 END 6-20-78, THE HYDROGEN SKIMMER RECIRCULATION | |||
~O3 FANS (2HV-CEQl and 2-HV-CEQ2) FAILED TO START WITHIN THE TIME LIMIT SPECIFIED BY T.S. | |||
SURVEILLANCE REQUIREMENT 4.6.5.6.a. IN BOTH CASES THE AGASTAT TIMERS WERE RESET TO | |||
~O6 WITHIN SPECIFICATIONS. PREVIOUS OCCURRENCES OF A SIMILAR NATURE INCLUDE: RO-050-315/75 | |||
~O6 -'.15. | |||
~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE. | |||
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE | |||
~SC Q>> ~Q\2 ~Z Q13 R 2 L A Y S Q14 ~NQ1s ~Z Q16 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LER]RO REPQRT ACTION FUTURE EVfNT YEAR | |||
~S8 21 22 EFFECT Q | |||
23 SHUTDOWN | |||
~03 24 REPORT N Q. | |||
4 26 Q~ | |||
27 | |||
~03 28 ATTACHMENT CODE 29 NPRDP TYPE QL 30 g | |||
PRIME COMP. | |||
31 NO. | |||
Ql 32 COMPONENT. | |||
TAKEN ACTION | |||
~2Q15 ~Z 33 34 Qls ON PLANT " | |||
~Z 35 Q20 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD | |||
~Z 36 Q21 37 0 | |||
HOURS Q22 0 0 0 40 | |||
~ | |||
SUBMITTED 41 Q23 FORM SUB. | |||
LJLIQ24 42 SUPPLIER | |||
~A 43 Q25 44 MANUFACTURER A 1 0 9 47 Q26 o NA 3 | |||
~14 7 8 9 80, FACILITY STATUS 91 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 EIH 7 8.9 E Q26 ~~Q29 10 12 13 44 MQ31 45 46 80 | |||
~16 ACTIVITY | |||
~Z Q33 CONTENT RELEASED OF RELEASE Z Q34 AMOUNT OF ACTIVITY NA | |||
~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 | |||
~00 0 Z NA 7 | |||
7 8 9 11 Q37 PERSONNEL INJURIES 12 QEs 13 " | |||
Iyqh 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 PUBLICITY NRC USE ONLY o | |||
7 8 9 10 68 69 80 o 0 | |||
NAME OF PREPARER PH NE, 61 6 465 5901 | |||
L' l | |||
NRC FORM 366 S. NUCLEAR REGULATORY,COMMISSION (7'7PJ LICENSEE EVENT REPORT CONTROL BLOCK: | |||
I 6 Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) | |||
~01 7 8 9 N I D C LICENSEE CODE C 2 14 Q2'0 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQE 25 26 4 1 1 LICENSE TYPE 1 1QR~QE 30 57 CAT 58 | |||
'1 CON'T | |||
~01 ~LQB 0 5 0 0 0 3 1 6 Q70 6 1 8 7 8QBO 7 1 I 7 8 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION PRESSURI'ZER LEVEL CHANNEL III NL - 53 1 | |||
MODEL 8764) WAS DECLARED INOPERABLE DUE TO EXCESSIVELY HIGHER INDICATION THAN THE | |||
~O4 OTHER TWO CHANNELS. THE APPLICABLE ACTION RE UIREMENTS OF T.S. TABLE 3.3-1 ITEM ll | |||
~OS AND T.S. TABLE 3.3-3 ITEN 18d MERE FULFILLED. PREVIOUS OCCURRENCES OF A SIMILAR | |||
~os NATURE INCLUDE: RO 05 316-78-6 050 315-78-10 77-41 76-41 40 75-76. | |||
~OB 80 7 8 9 3 SYSTEM CAUSE CAUSE COMP. VALVE. | |||
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8 | |||
~IA 9 10 Q11 ~X 11 Q72 ~2 12 Q73 13 I N S T R U 18 PR ~T 19 Q78 ~2 20 Q18 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LERIRO REPQRT ACTION FUTURE EVENT YEAR | |||
~78 21 22 EFFECT | |||
+ | |||
23 SHUTDOWN | |||
~04 24 REPORT NO. | |||
4 26 QZ 27 | |||
~03 28 ATTACHMENT CODE 29 NPRDR TYPE QL 30 | |||
~ | |||
PRIME COMP. | |||
Q 31 32 NO. | |||
[JO COMPONENT TAKEN ACTION ON PLANT ~ | |||
METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER | |||
~BQ78 ~2 Q78 ~2 QEP ~2 Q27 0 0 0 0 ~N Q23 ~YQ24 ~L QEE B 0 0 0 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 8 INVESTIGATION REVEALED THAT A LEAK HAD DEVELOPED AT A PLUGGED TEE FITTING IN THE REFERENCE LEG. THE LEAK WAS REPAIRED AND THE REFERENCE LEG WAS REFIL E . | |||
P AFFECTED CHANNEL WAS RETURNED TO OPERATION WITH INDICATION WITHIN 3'5 OF THE OTHER TWO CHANNELS. | |||
9 80 | |||
~ | |||
7 8 FACILITY 3P METHOD OF | |||
, STATUS BG POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 | |||
' | |||
8 F Q28 ~04 0 Q28 NA ~AQ37 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT 6 | |||
RELEASED OF RELEASE Z | |||
AMOUN1'F ACTIVITY NA NA LOCATION OF RELEASE Q | |||
~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 | |||
~00 0QZ Q38 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~43 TYPE DESCRIPTION Z Q42 NA 7 8 9 10 80 O N PUBLICITY ISSUED Q44 DESCRIPTION ~ NA NRC USE ONLY O | |||
7 8 9 10 68 69 80 ER Jack Rischling 616-465-5901 0 | |||
C 4 | |||
b | |||
'" | |||
NRC FORM 366 (7.77) | |||
LICENSEE EVENT REPORT U. S. NUCLEAR REGULATORY COMMISSION CONTROL BLOCK: Ol (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION) | |||
I 6 | |||
~p M I D C C 2 14 QO IS 0 0 0 0 0'0 LICENSE NUMBER 0 0 0 OQ3 25 26 4 1 1 LICENSE TYPE 1 1Q ~Qs 30 57 CAT 7 8 9 LICENSEE CODE CON'T | |||
~01 ~LQ6 0 5 0 0 0 3 1 6 Q70 6 1 2 7 8 Qs 0 7 I I 7 8 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlp DURING NORMAL OPERATION, FOLLOWING AN ADDITION OF BORIC ACID TO THE BORATED WATER | |||
~o3 SYSTEMIS. "THE BORON INJECTION TANK BORON CONCENTRATION WAS FOUND TO BE 19,780 PPM. | |||
~o4 THIS WAS BELOW THE 20,000 PPM LIMIT OF T. S. 3.5.4.1. THE ASSOCIATED BORIC ACID | |||
~os STORAGE TANK SOLUTION WAS FOUND TO CONTAIN 18,705 PPM BORON, WHICH IS BELOW THE LIMIT | |||
~o6 SPECIFIED BY T.S. 3.1.2.8. THE ACTION REQUIREMENTS OF BOTH T.S. WERE FULFILLED. | |||
~os 80 7 8 9 | |||
'3 SYSTEM CAUSE CAUSE COMP. VALVE. | |||
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE | |||
~oe ~SF Q11 A Q12 ~X Q13 Z Z Z Z Z Z Q14 ~Z Q13 ~Z 20 Q13 7 8 9 10 12 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LERIRO REPoRT ACTION FUTURE EVENT YEAR | |||
~78 21 | |||
~ | |||
22 EFFECT | |||
~ | |||
23 SHUTDOWN | |||
~0~ | |||
24 REPORT NO. | |||
8 26 | |||
~~ | |||
27 ATTACHMENT | |||
~03 28 CODE 29 NPRDQ TYPE | |||
~L 30 PRIME COMP. | |||
~ | |||
31 NO. | |||
32 0 | |||
COMPONENT TAKEN ACTION ON PLANT 4 METHOD HOIJRS Q22 SUBMITTED FORM SUB. SUPPLIEII MANUFACTURER | |||
~NQPE ~ZQER ~ZQER ~ZQ>> 0 0 0 0 ~NQEE ~NQ34 ~ZQEE Z 9 9 9 Qss 33 34 35 36 37 40 41 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 INVESTIGATION REVEALED THAT A CHEMICAL TECHNICIAN HAD THE BORIC ACID EVAPORATOR | |||
' | |||
p BOTTOMS PUMPED TO THE SOUTH BORIC ACID STORAGE TANKS(S-BAST) WITH A LOWER THAN DESIRED BORIC ACID CONCENTRATION. THE S-BAST IS RECIRCULATED THROUGH THE BORON 3 INJECTION TANK, CAUSING ITRJAS LOW BORIC ACI D CONCENTRATION ~ | |||
7,8 9 80 FACILITY | |||
~ | |||
~3P METHOD OF | |||
'7 8 9 | |||
~ | |||
STATUS Q26 10 99POWER | |||
$ ~9~Q2e 12 13 OTHERSTATUS NA 44 DISCOVERY | |||
'BQ31 45 46 ROUTINE SAMPLES DISCOVERY DESCRIPTION 80 EK izJO33 ACTIVITY RELEASED OF RELEASE CONTENT | |||
- | |||
z Q34 AMOUNTQF ACTIVITY ~ NA LOCATION OF RELEASE 036 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 | |||
~lT ~00 0 QET Z Q33 NA 7 8 9 11 12 13 80 PERSONNEI. INJURIES NUMBER DESCRIPTIONO41 | |||
[<i~] ~00 0 Qs NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 z Q42 NA 7 8 9 10 P 80 O | |||
ISSUED L~JQ44 I | |||
PUB L CITY DESCRIPTION ~ NA NRC USE ONLY ES Es 7 8 9 10 68, 69 80 TR 0 | |||
NAME OF PREPARER Jack Rischling PHDNE 6 1 6 465 590 1 L 49 | |||
t NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 4 | |||
LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 | |||
~O 7 8 9 P | |||
LICENSEE CODE P C 302 14 15 P P P P P LICENSE NUMBER P P, P.P 034 25 26 | |||
$ I LICENSE TYPE | |||
$ 3 30 04~03 57 CAT 58 CON'T | |||
~O 7 8 soU'"cE~LQB 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 6Q7 68 69 0 6 1 EVENT DATE 7 7 8QB 74 75 0 7 1 REPORT DATE 1 | |||
80 Q | |||
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATIONS, A WELD LEAK WAS DISCOVERED ON THE | |||
~O3 ESSENTIAL SERVICE WATER OUTLET ON 2AB DIESEL LUBE OIL COOLER | |||
~O4 HEAD. TO ACCOMPLISH REPAIRS, IT WAS NECESSARY TO TAKE 2AB | |||
~OB DIESEL GENERATOR OUT OF SERVICE. ALTHOUGH THE COMPANION DIESEL, | |||
~OB 2CD, WAS OPERABLE DURING 2AB REPAIRS, THE UNIT WAS IN A DEGRADED | |||
~O7 MODE AS DELINEATED IN TECH. SPEC. SECTION 3.8.1.1. | |||
~OS 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAI.VE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE | |||
~EE Q11 5 Q12 ~C Q13 H T E X C H Q14 ~C QEs ~Z QER 7 8 9 10 11 12 1, 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LE RIB REPoRT ACTION FUTURE O | |||
~7" EVENT YEAR 21 22 EFFECT | |||
~ | |||
23 SHUTDOWN | |||
~04 24 REPORT NO. | |||
6 26 | |||
~~ | |||
27 | |||
~03 28 ATI'ACHMENT CODE 29 NPRDP TYPE | |||
~L, 30 | |||
~ | |||
PRIME COMP. | |||
31 | |||
~0 32 NO. | |||
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER | |||
~AQER ~ZQ13 33 34 | |||
~Z020 35 | |||
~Z027 36 37 0 0 0 11 H Q23 ~Y024 ~AQ25 W 3 I 5 QER 40 41 42 - | |||
43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAUSE OF THE CRACK WAS MISALIGNMENT STRESS BETWEEN THE COOLER HEAD AND CONNECTING PIPING. A NEW PIPING SPOOL PIECE WAS FABRI-CATED TO ELIMINATE THE MISALIGNMENT. THE FOUR INCH CRACK IN THE 3 | |||
COOLER HEAD COULD NOT BE REPAIRED, THEREFORE, THE COOLER HEAD WAS REPLACED. | |||
4 7 8 9 80 FACILITY STATLIS POWE R OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 0 LLLJQ 55 CZI 7 | |||
6 8 9 B 2B 10 0 6 0 12 2e 13 NA 44 | |||
~A 45 Q31 46 ROUTINE INSPECTION 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ36 LOCATION OF RELEASE Q36 6 ~Z Q33 Z Q34 NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 037 MZ033 HA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7 | |||
s 8 | |||
~00 9 | |||
0 Qo 12 NA 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 o | |||
ISSUED uNQ44 PUBLICITY DESCRIPTION ~ NA NRC USF ONLY 7 | |||
7 8 9 10 68 69 80 o NAMEOF PRFPARER C AEL S. BRO N 616-465-5901, EXT.}} |
Revision as of 19:55, 20 October 2019
ML18219B572 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 07/11/1978 |
From: | Shaller D American Electrtic Power System, Indiana Michigan Power Co |
To: | James Keppler NRC/RGN-III |
References | |
LER 1978-034-03L, LER 1978-044-03L, LER 1978-045-03L, LER 1978-046-03L | |
Download: ML18219B572 (12) | |
Text
g ~/~g/~
REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)
DISTRIBUTION FOR INCOMING 'MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 07/11/78 NRC lN 5 Ml PWR DATE RCVD: 07/14/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-034) ON 05/15/78 CONCERNING DURING SURVEILLANCE TESTS ON 05/15/78 8. 06/20/78) THE HYDROGEN SKIMMER RECIRCULATION FANS (2HV-CEQi 8( 2-HV-CEQ2) FAILED TO START WITHIN TECH SPEC REQUIREMENT 4. 6. 5. 6. A... W/ATT LER 7Q -Q9"f ] '7B" ~V+ >
+ 7
>~k'LANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
++++~>+++++++4+4l+> DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS +4>+>>~+>>>>+>>>+>
NOTES:
- 1. SEND 3 COPIES OF ALL MATERIAL TO lhE ED REEVES-1 CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)
FOR ACTION: BR CHIE W ¹2 BC+4W/4 ENCL INTERNAL: R G FILE+4W/E NRC PDR++W/ENCL I 5 E~~ ENCL, MIPC~~W/3 ENCL I 8( C SYSTEMS BR+%W/ENCL EMERGENCY PLAN BR++W/ENCL NOVAK/CHECK~+W/ENCL EEB++W/ENCL AD FOR ENG~~~~W/ ENCL PLANT SYSTEMS BR<<W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL AD FOR SYS 8( PROJ+4W/ENCL REACTOR SAFETY BR<+W/ENCL ENGINEERING BR++W/ENCL VOLLMER/BUNCH++M/ENCL KREGER/J. COLLINS<~W/ENCL POWER SYS BRwmW/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'8 ST. JOSEPH' I +4 WfENCL
'ERA>+W/ENCL NSIC~~W/ENCL ACRS CAT B++W/16,ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 7819500 4
,
SIZE: 1P+1P+3P
',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%% THE END
I A
h 4 4 4 N
I 'I 11 tt
'b i1
erloen
+ CI~ ~
y>ccI IND/ANA & NICHIGAN PD %EH COMP N Y C7 DONALD C. COOK NUCLEAR PLANT C+
r'a P.O. Box 458, Bridgman, Michigan 49106 t C.> "!
CrC r v C'ql
%CD July 11, 1978 >~a rC-C CD CA CO C/)CD D Pl C".. X Mr. J.G. Keppler, Regional Director C/l CD Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316
Dear Mr. Keppler:
Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:
RO 78-034/03L-1 RO 78-044/03L-0 RO 78-045/03L-0 RO 78-046/03L-0 Sincerely, D.V. Shaller Plant Manager
/bab CC: J.E. Dolan R.W. Jur gensen R.F. Kroeger R. Kilburn
,R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.
R. Walsh, Esq.
G. Charnoff, Esq.
PNSRC J.F. Stietzel JUP ].g 1978 R.S. Keith Dir., IE (30 copies)
Dir., MIPC (3 copies)
"0 W
L(
V u
( NRC FOR0/I 366
)
(7') "UPDAT~EPORT - PREVIOUS REPORT DATE LICENSE E EV EN T R E PORT 6/ I CONTROL BLOCK:
1 ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~oi 7 8 9 M I D I.ICENSEE CODE C C 2 14 2
15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Q 3 26 4 1 1 LICENSE TYPE 1 1 30 Q4~QE 57 CAT 58 CON'T
~O REPoRT
~LQ6 P 5 P P P 3 1 6 Q7 0 5 1 5 7 8 QB 0 / I I / 8 Q 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES +10 DURING SURVEILLANCE TESTS ON 5-15-78 END 6-20-78, THE HYDROGEN SKIMMER RECIRCULATION
~O3 FANS (2HV-CEQl and 2-HV-CEQ2) FAILED TO START WITHIN THE TIME LIMIT SPECIFIED BY T.S.
SURVEILLANCE REQUIREMENT 4.6.5.6.a. IN BOTH CASES THE AGASTAT TIMERS WERE RESET TO
~O6 WITHIN SPECIFICATIONS. PREVIOUS OCCURRENCES OF A SIMILAR NATURE INCLUDE: RO-050-315/75
~O6 -'.15.
~OB 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~SC Q>> ~Q\2 ~Z Q13 R 2 L A Y S Q14 ~NQ1s ~Z Q16 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LER]RO REPQRT ACTION FUTURE EVfNT YEAR
~S8 21 22 EFFECT Q
23 SHUTDOWN
~03 24 REPORT N Q.
4 26 Q~
27
~03 28 ATTACHMENT CODE 29 NPRDP TYPE QL 30 g
PRIME COMP.
31 NO.
Ql 32 COMPONENT.
TAKEN ACTION
~2Q15 ~Z 33 34 Qls ON PLANT "
~Z 35 Q20 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 METHOD
~Z 36 Q21 37 0
HOURS Q22 0 0 0 40
~
SUBMITTED 41 Q23 FORM SUB.
LJLIQ24 42 SUPPLIER
~A 43 Q25 44 MANUFACTURER A 1 0 9 47 Q26 o NA 3
~14 7 8 9 80, FACILITY STATUS 91 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 EIH 7 8.9 E Q26 ~~Q29 10 12 13 44 MQ31 45 46 80
~16 ACTIVITY
~Z Q33 CONTENT RELEASED OF RELEASE Z Q34 AMOUNT OF ACTIVITY NA
~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~00 0 Z NA 7
7 8 9 11 Q37 PERSONNEL INJURIES 12 QEs 13 "
Iyqh 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 PUBLICITY NRC USE ONLY o
7 8 9 10 68 69 80 o 0
NAME OF PREPARER PH NE, 61 6 465 5901
L' l
NRC FORM 366 S. NUCLEAR REGULATORY,COMMISSION (7'7PJ LICENSEE EVENT REPORT CONTROL BLOCK:
I 6 Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~01 7 8 9 N I D C LICENSEE CODE C 2 14 Q2'0 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 OQE 25 26 4 1 1 LICENSE TYPE 1 1QR~QE 30 57 CAT 58
'1 CON'T
~01 ~LQB 0 5 0 0 0 3 1 6 Q70 6 1 8 7 8QBO 7 1 I 7 8 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATION PRESSURI'ZER LEVEL CHANNEL III NL - 53 1
MODEL 8764) WAS DECLARED INOPERABLE DUE TO EXCESSIVELY HIGHER INDICATION THAN THE
~O4 OTHER TWO CHANNELS. THE APPLICABLE ACTION RE UIREMENTS OF T.S. TABLE 3.3-1 ITEM ll
~OS AND T.S. TABLE 3.3-3 ITEN 18d MERE FULFILLED. PREVIOUS OCCURRENCES OF A SIMILAR
~os NATURE INCLUDE: RO 05 316-78-6 050 315-78-10 77-41 76-41 40 75-76.
~OB 80 7 8 9 3 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8
~IA 9 10 Q11 ~X 11 Q72 ~2 12 Q73 13 I N S T R U 18 PR ~T 19 Q78 ~2 20 Q18 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LERIRO REPQRT ACTION FUTURE EVENT YEAR
~78 21 22 EFFECT
+
23 SHUTDOWN
~04 24 REPORT NO.
4 26 QZ 27
~03 28 ATTACHMENT CODE 29 NPRDR TYPE QL 30
~
PRIME COMP.
Q 31 32 NO.
[JO COMPONENT TAKEN ACTION ON PLANT ~
METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~BQ78 ~2 Q78 ~2 QEP ~2 Q27 0 0 0 0 ~N Q23 ~YQ24 ~L QEE B 0 0 0 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 8 INVESTIGATION REVEALED THAT A LEAK HAD DEVELOPED AT A PLUGGED TEE FITTING IN THE REFERENCE LEG. THE LEAK WAS REPAIRED AND THE REFERENCE LEG WAS REFIL E .
P AFFECTED CHANNEL WAS RETURNED TO OPERATION WITH INDICATION WITHIN 3'5 OF THE OTHER TWO CHANNELS.
9 80
~
7 8 FACILITY 3P METHOD OF
, STATUS BG POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32
'
8 F Q28 ~04 0 Q28 NA ~AQ37 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT 6
RELEASED OF RELEASE Z
AMOUN1'F ACTIVITY NA NA LOCATION OF RELEASE Q
~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~00 0QZ Q38 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY ~43 TYPE DESCRIPTION Z Q42 NA 7 8 9 10 80 O N PUBLICITY ISSUED Q44 DESCRIPTION ~ NA NRC USE ONLY O
7 8 9 10 68 69 80 ER Jack Rischling 616-465-5901 0
C 4
b
'"
NRC FORM 366 (7.77)
LICENSEE EVENT REPORT U. S. NUCLEAR REGULATORY COMMISSION CONTROL BLOCK: Ol (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)
I 6
~p M I D C C 2 14 QO IS 0 0 0 0 0'0 LICENSE NUMBER 0 0 0 OQ3 25 26 4 1 1 LICENSE TYPE 1 1Q ~Qs 30 57 CAT 7 8 9 LICENSEE CODE CON'T
~01 ~LQ6 0 5 0 0 0 3 1 6 Q70 6 1 2 7 8 Qs 0 7 I I 7 8 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlp DURING NORMAL OPERATION, FOLLOWING AN ADDITION OF BORIC ACID TO THE BORATED WATER
~o3 SYSTEMIS. "THE BORON INJECTION TANK BORON CONCENTRATION WAS FOUND TO BE 19,780 PPM.
~o4 THIS WAS BELOW THE 20,000 PPM LIMIT OF T. S. 3.5.4.1. THE ASSOCIATED BORIC ACID
~os STORAGE TANK SOLUTION WAS FOUND TO CONTAIN 18,705 PPM BORON, WHICH IS BELOW THE LIMIT
~o6 SPECIFIED BY T.S. 3.1.2.8. THE ACTION REQUIREMENTS OF BOTH T.S. WERE FULFILLED.
~os 80 7 8 9
'3 SYSTEM CAUSE CAUSE COMP. VALVE.
CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~oe ~SF Q11 A Q12 ~X Q13 Z Z Z Z Z Z Q14 ~Z Q13 ~Z 20 Q13 7 8 9 10 12 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION Q11 LERIRO REPoRT ACTION FUTURE EVENT YEAR
~78 21
~
22 EFFECT
~
23 SHUTDOWN
~0~
24 REPORT NO.
8 26
~~
27 ATTACHMENT
~03 28 CODE 29 NPRDQ TYPE
~L 30 PRIME COMP.
~
31 NO.
32 0
COMPONENT TAKEN ACTION ON PLANT 4 METHOD HOIJRS Q22 SUBMITTED FORM SUB. SUPPLIEII MANUFACTURER
~NQPE ~ZQER ~ZQER ~ZQ>> 0 0 0 0 ~NQEE ~NQ34 ~ZQEE Z 9 9 9 Qss 33 34 35 36 37 40 41 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 INVESTIGATION REVEALED THAT A CHEMICAL TECHNICIAN HAD THE BORIC ACID EVAPORATOR
'
p BOTTOMS PUMPED TO THE SOUTH BORIC ACID STORAGE TANKS(S-BAST) WITH A LOWER THAN DESIRED BORIC ACID CONCENTRATION. THE S-BAST IS RECIRCULATED THROUGH THE BORON 3 INJECTION TANK, CAUSING ITRJAS LOW BORIC ACI D CONCENTRATION ~
7,8 9 80 FACILITY
~
~3P METHOD OF
'7 8 9
~
STATUS Q26 10 99POWER
$ ~9~Q2e 12 13 OTHERSTATUS NA 44 DISCOVERY
'BQ31 45 46 ROUTINE SAMPLES DISCOVERY DESCRIPTION 80 EK izJO33 ACTIVITY RELEASED OF RELEASE CONTENT
-
z Q34 AMOUNTQF ACTIVITY ~ NA LOCATION OF RELEASE 036 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39
~lT ~00 0 QET Z Q33 NA 7 8 9 11 12 13 80 PERSONNEI. INJURIES NUMBER DESCRIPTIONO41
[<i~] ~00 0 Qs NA 80 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 z Q42 NA 7 8 9 10 P 80 O
ISSUED L~JQ44 I
PUB L CITY DESCRIPTION ~ NA NRC USE ONLY ES Es 7 8 9 10 68, 69 80 TR 0
NAME OF PREPARER Jack Rischling PHDNE 6 1 6 465 590 1 L 49
t NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION 4
LICENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
~O 7 8 9 P
LICENSEE CODE P C 302 14 15 P P P P P LICENSE NUMBER P P, P.P 034 25 26
$ I LICENSE TYPE
$ 3 30 04~03 57 CAT 58 CON'T
~O 7 8 soU'"cE~LQB 60 61 0 5 0 0 0 DOCKET NUMBER 3 1 6Q7 68 69 0 6 1 EVENT DATE 7 7 8QB 74 75 0 7 1 REPORT DATE 1
80 Q
EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING NORMAL OPERATIONS, A WELD LEAK WAS DISCOVERED ON THE
~O3 ESSENTIAL SERVICE WATER OUTLET ON 2AB DIESEL LUBE OIL COOLER
~O4 HEAD. TO ACCOMPLISH REPAIRS, IT WAS NECESSARY TO TAKE 2AB
~OB DIESEL GENERATOR OUT OF SERVICE. ALTHOUGH THE COMPANION DIESEL,
~OB 2CD, WAS OPERABLE DURING 2AB REPAIRS, THE UNIT WAS IN A DEGRADED
~O7 MODE AS DELINEATED IN TECH. SPEC. SECTION 3.8.1.1.
~OS 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAI.VE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~EE Q11 5 Q12 ~C Q13 H T E X C H Q14 ~C QEs ~Z QER 7 8 9 10 11 12 1, 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LE RIB REPoRT ACTION FUTURE O
~7" EVENT YEAR 21 22 EFFECT
~
23 SHUTDOWN
~04 24 REPORT NO.
6 26
~~
27
~03 28 ATI'ACHMENT CODE 29 NPRDP TYPE
~L, 30
~
PRIME COMP.
31
~0 32 NO.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~AQER ~ZQ13 33 34
~Z020 35
~Z027 36 37 0 0 0 11 H Q23 ~Y024 ~AQ25 W 3 I 5 QER 40 41 42 -
43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAUSE OF THE CRACK WAS MISALIGNMENT STRESS BETWEEN THE COOLER HEAD AND CONNECTING PIPING. A NEW PIPING SPOOL PIECE WAS FABRI-CATED TO ELIMINATE THE MISALIGNMENT. THE FOUR INCH CRACK IN THE 3
COOLER HEAD COULD NOT BE REPAIRED, THEREFORE, THE COOLER HEAD WAS REPLACED.
4 7 8 9 80 FACILITY STATLIS POWE R OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 0 LLLJQ 55 CZI 7
6 8 9 B 2B 10 0 6 0 12 2e 13 NA 44
~A 45 Q31 46 ROUTINE INSPECTION 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ36 LOCATION OF RELEASE Q36 6 ~Z Q33 Z Q34 NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 037 MZ033 HA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7
s 8
~00 9
0 Qo 12 NA 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q4. NA 7 8 9 10 80 o
ISSUED uNQ44 PUBLICITY DESCRIPTION ~ NA NRC USF ONLY 7
7 8 9 10 68 69 80 o NAMEOF PRFPARER C AEL S. BRO N 616-465-5901, EXT.