ML18219B572: Difference between revisions

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: 1. SEND 3 COPIES OF ALL MATERIAL TO          lhE ED REEVES-1    CY ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002)
: 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  &#xb9;2  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
FOR ACTION:        BR CHIE      W  &#xb9;2  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
                         '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
,
SIZE: 1P+1P+3P
',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%%          THE END
',%%%0f%%%%%%%%%%%%4 SH8%%%%%%%%%%%%%%%%          THE END


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                                                                                         ~
                                                                                         ~
7        8 FACILITY                                                                  3P      METHOD OF
7        8 FACILITY                                                                  3P      METHOD OF
             , STATUS              BG POWER                          OTHER STATUS                DISCOVERY                                DISCOVERY DESCRIPTION          Q32
             , 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
                                                                                            '
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
RELEASED OF RELEASE Z
AMOUN1'F ACTIVITY NA                                                NA LOCATION OF RELEASE          Q
AMOUN1'F ACTIVITY NA                                                NA LOCATION OF RELEASE          Q
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b
b


        '"
NRC FORM 366 (7.77)
NRC FORM 366 (7.77)
LICENSEE EVENT REPORT U. S. NUCLEAR REGULATORY COMMISSION CONTROL BLOCK:                                                      Ol                (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)
LICENSEE EVENT REPORT U. S. NUCLEAR REGULATORY COMMISSION CONTROL BLOCK:                                                      Ol                (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)
Line 175: Line 170:
32 0
32 0
COMPONENT TAKEN ACTION                      ON PLANT      4      METHOD                    HOIJRS Q22        SUBMITTED          FORM SUB.          SUPPLIEII            MANUFACTURER
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
                   ~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 ~
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
7,8              9                                                                                                                                                                            80 FACILITY
                                                                                           ~
                                                                                           ~
Line 185: Line 179:
STATUS Q26 10 99POWER
STATUS Q26 10 99POWER
                                   $ ~9~Q2e        12        13 OTHERSTATUS NA 44 DISCOVERY
                                   $ ~9~Q2e        12        13 OTHERSTATUS NA 44 DISCOVERY
                                                                                                 'BQ31 45          46 ROUTINE SAMPLES DISCOVERY DESCRIPTION 80 EK izJO33 ACTIVITY RELEASED OF RELEASE CONTENT
                                                                                                 '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
                                -
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
~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
[<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

Latest revision as of 20:22, 2 February 2020

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0)
ML18219B572
Person / Time
Site: Cook  American Electric Power icon.png
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.