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{{#Wiki_filter:NRC FORM 195 V.S.NUCLEAR RFOVLATORV COMMISSION I2 70)o NR DISTRIBUTION FDR PART 50 DOCI(ET MATERIAL DO TgtgVI 0 E FI FILE NVMOER INCIDENT REPORT To: J.G.Keppl er FRDM: Indiana 8 Michigan Power Co.Bridgman, Michigan R.lJ.Jurgensen DATE OF DOCUMENT 6-2-76 DATE RECEIVED 6-10-76 SLETTER 0ORIGINAI QCOPV'NOTOR I Z E D EI V N C LASS I F I E D PROP INPUT FORM NUMBER OF COPIES RECEIVED 30 DESCRIPTldN Ltr.trans the followihg........
{{#Wiki_filter:NRC FORM 195                                                   V.S. NUCLEAR RFOVLATORV COMMISSION DO    TgtgVI 0 E FI I2 70)                 o FILE NVMOER NR DISTRIBUTION FDR PART 50 DOCI(ET MATERIAL                                       INCIDENT REPORT To:     J.G. Keppl er                                 FRDM: Indiana 8 Michigan Power Co.       DATE OF DOCUMENT Bridgman, Michigan                       6-2-76 R.lJ. Jurgensen                     DATE RECEIVED 6-10-76 SLETTER                     NOTOR I Z E D             PROP                  INPUT FORM          NUMBER OF COPIES RECEIVED 0ORIGINAI              EI V N C LASS I F I E D
PLANT NA1IE.Cook b 1 ENCLOSURE Licensee Event Report (%.0.II 76-23)on 5-2-76 Concerning Various Valves (Isloation) failed to meet acceptable leak rate Specifications......
            '
-Licensee Event Report (R.O.k'6-24)on-5-6-76 Concer'ning"Lower.
QCOPV                                                                                                    30 DESCRIPTldN                                                             ENCLOSURE Licensee Event Report (%.0. II 76-23) on 5-2-76 Ltr. trans the followihg........                                        Concerning Various Valves (Isloation) failed to meet acceptable leak rate Specifications......
Inlet.Door'-R*opening'Torque being in excess of Tech.Sepc.......
                                                                      - Licensee Event Report (R.O. k'6-24) on 6-76 Concer'ning"Lower. Inlet. Door'-R* opening 'Torque being in excess of Tech. Sepc.......
(30 Carbon Sisgned Cys.REceived)ACKNOWLEDGED DO NOT REMOVZ NOTE: IF PERSONNEL EXPOSURE IS INVOLVED..
(30 Carbon Sisgned Cys. REceived)
SEND DIRECTLY TO KREGER/J, COLLINS--SAFETY BRANCH CHIEF: W 3 CYS FOR ACTION LIC~-ASST: W/CYS ACRS'YS Kniel Lee ENT TO LA FOR ACTION/INFORMATION ENVIRO SAB 6-10-76 INTERNAL DISTRIBUTION NRC PDR ICE 2 SCHROEDER/IPPOLITO NOVAK CHECK IES S.E TEDESCO HACCA EN BAER SHAO VOLLH~BH BUNCH KRE E 0 N LPDR:~TIC NSIC EXTERNAL DISTRIBUTION CONTROL NUMBER 5879" 3 I~3~3 I'3 Ilt II
ACKNOWLEDGED DO NOT REMOVZ PLANT NA1IE.        Cook b      1 NOTE:   IF PERSONNEL EXPOSURE IS INVOLVED..
~egtffatoty QL cd@Afar o4 INDIANA 8 NICHIGAN I'DN'E DONALD C.COOK NUCL P.O.Box 458, Bridgmnn,>hi June 2, 1976 IANy PL@~>'km gran 4SLIC 3 ig gog7.92 g~q teton p~g Clerk Hr.J.G.Keppler, Regional Direc a Office of'Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 ANION 876~<95.%%%lNtK.'t
SEND DIRECTLY TO KREGER/J, COLLINS
~jg I.Operating License DPR-58 Docket No.50-315
      - SAFETY                                        FOR ACTION/INFORMATION                ENVIRO          SAB    6-10-76 BRANCH CHIEF:                                 Kniel W 3 CYS FOR ACTION LIC ~   -ASST:                               Lee W/     CYS ACRS       'YS                     ENT TO LA INTERNAL DISTRIBUTION NRC PDR ICE         2 SCHROEDER/IPPOLITO NOVAK CHECK IES S   . E TEDESCO HACCA EN BAER SHAO VOLLH~BH BUNCH KRE E           0     N EXTERNAL DISTRIBUTION                                          CONTROL NUMBER LPDR:         ~
TIC NSIC 5879"


==Dear lhr'.Keppler:==
3 I~
Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 4, Section 2.b, the following reports are submitted:
3 ~ 3 I' 3 Ilt II
R0-50-315/76-23 RO-50-315/76-24 Sincerely, r R.M.ge en Plant tan er/bab cc: R.S.Hunter-J.E.Dolan G.E.Lien R.Kilburn R.J.Vollen BPI R.C.Callen 1/PSC K.R.Baker RO:III P.W.Steketee, Esq.R.Walsh, Esq.G , Charnoff, Esq G.Olson J.N.Hennigan PNSRC R.S..Keith
'Dir., IE (30 copies)Dir., 1<IPC{3 copies)


~LICENSES SVSNT aePORTi CONTROL 0LOCK: 1 LtCENSf f NAhtf 0 14 15 AFT'OAT Af POAT CAT EOOAY TYPE SOUSE[oagcow T~7 0 57'9 59'0 0 LtCLNSE t6uhtIILA 0 0 0: 0 0-0 0 5 OOCKET kuhIOIA L050-03 15/0 LCT NSE IVPL.EVENT TYPE 4 1 1 1 1+0+]30 31 32 fVENT OA'If Aft'CAT OATF 5 O 8 Z 6~0 74 75 (PLEASE PRINT ALL REOUIREO INFORIVI ATION)EVENT DESCRIPTION Jog WHILE IN t'lODE 5 DURING SURVEILLANCE TESTIttG OF CONTAINMENT ISOLATION VALVES VARIOUS 7 0 9 toOj R roO5j 7 0 9 roOsj l P TYP.AK'P N A P IFICATIOt<S PARAGRAPH 3.6.1.2.b.(RO-50-31 5/76-23)UD UD UO 7 0 9 PfdV F SvSTT M CAUSE COht FUN TNT COCE COOE COMPONEt4T COOE SUPPLEA[oar]~SD 6 V'L V 6 X~0 7 0 9 10 11 12 17 43 CAUSE OESCRlPTION EXCESSI EAKAGE DUE T DEPOSIT BUILDUP ON COht PON'I k T ht Ahui*C I UPf A X 9 9 9 VOLATION 48 VALVE SEATS AND WEAR BY VALVE OPERA N 7 0 9 UO~o9 ALL VALVES WITH EXCESSIVE LEAK RATES WERE REPAIRED AND RETESTED;TOTAL LEAKAGE WAS 7 0 9 Q~o WI TH I N SPECIFICATION.
                                                        ~egtffatoty        QL cd
OTHER STATUS PROBABLE COttSEQUEttCES Jig>NA 7 09 f AC A I'fv STATt1S POWER[ll1]6~00 0 NA 7 0 9 10 12 13 FOPhl OF ACT lVITY CO')T EN T AFLEASfo OF PELE*Sf At tOUtTT OF ACTIVITY Jig~Z Z NA 7 0'10 11 PERSONNEL EXPOSURES EG3 LILLI~LZJ 7 0 9 11 12 13 PERSONNEL INJURIES feuhtS=A OESCA1PTtON
        @Afar o4 INDIANA 8 NICHIGAN I'DN'E                  IANy DONALD C. COOK NUCL            PL@~>'km P.O. Box 458, Bridgmnn,>hi  gran 4SLIC 3
[i)4]~00 0 tlA 7 09 11 12 htETHOO OF OTSCOVF AY B 44 40 NA 44 45 01SCOVEAY OESCIVPIlON SURVEILLANCE TESTING LOCATlON Of AELEASE UO 7 8 9 LOSS OR DAMAGE TO FACILITY T v PE OESCA:P T TON Z NZ 9 10 PUULICIT Y tIA 00 7 8 9 pg 7 t'DDITIONAL I'ACTORS I ttA gH l~7 09 JACK RISCHLIttG UO p~,ig.~616 465 59~01 368)G>0 ddI 46 1
ig    gog7.92 June 2, 1976 ANION 876~
g~q teton p~g  Clerk
                                                                              <95.     %%%lNtK.'t Hr. J.G. Keppler, Regional Direc                        a                                  ~jg Office of 'Inspection and Enforcement United States Nuclear Regulatory Commission                                        I.
Region        III 799 Roosevelt          Road Glen    Ellyn, IL        60137 Operating License DPR-58 Docket No. 50-315


'4 P SUPPLEt1EHT TO REPORTABLE OCCURREtfCE RO-50-315 76-23 SUPPLEHENT TO EVEtiT DESCRIPTION THE FOLLOMIt<G VALVES MERE FOUND=TO HAVE EXCESSIVE LEAKAGE: DCR-621 ECR-15 GCR-314 NCR-105 NCR-106 NSW-244-2 NSW-244-3 NSM-244-4 MCR-958 HSW-417-4 NSM-415-1 NSW-415-2 MCR-905 HSW-415-3 NSW-415-4 WCR-922 WCR-921 HSW-417-3 VCR-106 VCR-206 SI-189 N-102 SH-1 t>>l,i CONTROL BLOCK:~LICENSEE EVENT REIoORI (PLEASE PAINT ALL AEOUIREO INFORMATION)
==Dear lhr'. Keppler:==
LiCKNST E NL'V E LL IttSE tiUMBLR toOjI t1 I D C C 1 0 0-0 0 0 0 7 09 14 15 LtCI ttSE.TYPE IVTNT I v I'E 4 t i l l~03)20 Jo 31 32 CLTT Gonv[oagcour~7 0 57 50 Afponr ntpont~L 59 00 OOCKK t t'UMrB'LR 0 5 0-0 3 f VINT Ontf ntPORT OATK 1 5 0 5 0 6 7 6 0 6 0 I 7 6 60 09 74 75 UO EVENT OESCRIPTION
 
[oO]WHILE It(NCDE 5, DURING ICE CONDENSER INLET DOOR OPENING TORQUE SURVEILLANCE TESTING, 7 0 9 UO'LOWER INLET DOOR 1-R OPENING TORQUE WAS FOUND IN EXCESS'OF TECHNICAL SPECIFICATION 7 0 9 Qpjn PARAGRAPH 4.6.5.3.1 b3 LllklT OF 195 ItlCkt POUNDS.LOWER INLET DOOR 3-L.INITIAL UO 7 0 9 0 toOQ bl Llt1IT OF 675 It(CH POUt<DS.DOOR 1-R SPRING TEttSIOt<(SEE SUPPLEtkENT)(RO-50-315/76<i 7 0 9 SYSTKti CAUSE COOK CODE Pnnr E CCrrtrt 4 O4'I'Uf R COLrPONINT M LtuUt LOT Urrt R W 1 2 0 COVPONENT CODE[nn')~so F 7 0 0 10 11 12 CAUSE OESCRIPTION
Pursuant to the requirements              of  Appendix        A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide
[oa~j DOOR 1-R Llt>IT WAS EXCEEDED X X X X X X 17 43 44 DUE TO SPRING TENSION DRIFT.DOOR 3-L INITIAL OPENING 7 0 9 UO Jag OPENlt,G TOR UE WAS FOUr(D TO BE IN EXCESS OF TECHNICAL SPECIFICATION PARAGRAPH 4.6.5.3.1 7 0 9 00 X EEDED L"ItlITS BECAUSE OF AN ICE BUILDUP FROtl CONDENSATION ON THE LOWER SILL.otiiKA sTntUs NA aMourtt of nctiv:tv AOOITIONAL FACTORS Qg I rtA 7 8 9 9]NA 7 04J J.RISCHLlttG 7 0 9~1O 7 09 TLCtLIT Y STLTUS POtttf n Lsj~00 o 7 0 9 10 12 13 FOtttl OF ACTIVITY CO@TENT 7 0 9 10 11 PERSONNEL EXPOSURES tiUMBER TYPE OESCRlPTtON
: 1. 16, Revision 4, Section 2.b, the following reports are submitted:
~00 0 T ttA 7 09 11'l2 13 PERSONNEL INJURIES tiUMBEA OESCRIPTtON
R0-50-315/76-23 RO-50-315/76-24 Sincerely, r
[i')~00 0 ttA 7 0 9 11 12 PROBABLE CONSEQUENCES t115j tiA 7 0'9 LOSS OR DAMAGE TO FACILITY T'vpE oEscnpooti tIIsj Z tlA 7 09 10 PUULICITY[lli)t'iA 0 9 MEIHOO OF OISCOVf A V 45 40 NA nn 45 otscovf AY of scn'.ptIQN SURVEILLANCE TESTING LOfnttON OF RELKnSE P>IOIIE{616)4G5 5901(368 UO'u)UU Uo Gt'4t e tt I~a 0 1 SUPPLEt'iEt<T TO REPORTABLE OCCURRENCE RO-50-315/76-4 SUPPLEMENT TO EVENT DESCRIPTION WAS ADJUSTED TO PROVIDE A 189 INCH POUND OPENING TORQUE.DOOR 3-L BOTTOM SILL WAS CLEANED At40 INITIAL OPEttING TORQUE h'AS REMEASURED AT, 287 INCH'POUNDS.}}
R.M.          ge    en Plant      tan      er
/bab cc:    R.S. Hunter
      -J.E. Dolan G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen 1/PSC K.R. Baker RO:III P.W.      Steketee, Esq.
R. Walsh, Esq.
G    , Charnoff,    Esq G. Olson J.N. Hennigan PNSRC R.S..Keith
      'Dir.,      IE (30  copies)
Dir.,      1<IPC {3 copies)
 
                                                              ~ LICENSES                SVSNT          aePORTi CONTROL 0LOCK:                                                                                (PLEASE PRINT ALL REOUIREO INFORIVIATION) 1                            0 LtCENSf  f                                                                                            LCT NSE                EVENT NAhtf                                        LtCLNSE t6uhtIILA                                          IVPL.                  TYPE 0            0    0    0:    0    0  0          0            4  1    1    1    1      +0+]
                      ~'9 14      15                                                      5                                30    31    32 AFT'OAT    AfPOAT CAT EOOAY                                                  kuhIOIA                                fVENT OA'If                      Aft'CAT OATF
                                                '0 TYPE    SOUSE                  OOCKET
[oagcow        T L050            03              15/            0      5      O  8    Z    6      ~0 7    0                57                  59                                                                                                74    75 EVENT DESCRIPTION Jog          WHILE IN t'lODE 5                    DURING SURVEILLANCE TESTIttG OF CONTAINMENT ISOLATION VALVES                                                  VARIOUS UD AC l                P          TYP      .        AK'              P 7    0 9                                                                                                                                                                  UD toOj          R                                  N    A      P    IFICATIOt<S PARAGRAPH                3.6.1.2.b.
UO roO5j 7 0    9 roOsj (RO-50-31 5/76- 23)
I'fv 7    0 9                                                                            PfdV F SvSTT M        CAUSE                                              COht FUN TNT              COht PON'I k T COCE          COOE                  COMPONEt4T COOE                SUPPLEA              ht Ahui*CI UPf A              VOLATION
[oar]  ~SD                    6            V'          L    V  6  X          ~0                X    9      9      9 7  0 9        10              11          12                            17          43                                                  48 CAUSE OESCRlPTION EXCESSI                  EAKAGE DUE T              DEPOSIT BUILDUP            ON    VALVE SEATS AND WEAR BY VALVE OPERA                                N 7    0 9                                                                                                                                                                  UO
~o9          ALL VALVES WITH EXCESSIVE LEAK RATES                                    WERE      REPAIRED AND RETESTED; TOTAL LEAKAGE WAS 7 0 9                                                                                                                                                                      UO Q~o          WI TH I N        SPECIFICATION.
7 09 f                                                                            htETHOO OF STATt1S                    POWER                  OTHER STATUS              OTSCOVF AY                            01SCOVEAY OESCIVPIlON
[ll1]                6            ~00          0          NA 44 B                SURVEILLANCE TESTING 7    0          9                  10              12    13                                              40 FOPhl OF ACT lVITY          CO') T EN T AFLEASfo          OF PELE*Sf                At tOUtTT OF ACTIVITY                                                    LOCATlON Of AELEASE Jig      '
                  ~Z                  Z          NA                                                  NA 7    0                                10      11                                        44        45 PERSONNEL EXPOSURES 7
EG3 0 9 LILLI~              11 LZJ 12      13 PERSONNEL INJURIES feuhtS=A              OESCA1PTtON
[i)4]  ~00              0            tlA 7    09                      11    12 PROBABLE COttSEQUEttCES Jig>          NA 9                                                                                                                                                                  00 LOSS OR DAMAGE TO FACILITY T v PE          OESCA:P T TON Z              NZ 7    8 9              10 PUULICITY tIA 7    8 9 t'DDITIONAL I'ACTORS pg    I          ttA 7
7 gH 09 l~                                                                                                                                                                UO JACK RISCHLIttG                                                                    p~,ig.~616 465          59~01  368)
G>0 ddI 46 1
 
                  '4           P SUPPLEt1EHT TO REPORTABLE OCCURREtfCE RO-50-315 76- 23 SUPPLEHENT TO EVEtiT DESCRIPTION THE FOLLOMIt<G VALVES MERE FOUND=TO HAVE EXCESSIVE LEAKAGE:
DCR-621                   MCR-905 ECR-15                   HSW-415-3 GCR-314                   NSW-415-4 NCR-105                   WCR-922 NCR-106                   WCR-921 NSW-244-2               HSW-417-3 NSW-244-3                 VCR-106 NSM-244-4                 VCR-206 MCR-958                   SI-189 HSW-417-4                 N-102 NSM-415-1                SH-1 NSW-415-2
 
t>>
l,i
 
CONTROL BLOCK:
                                                          ~ LICENSEE                 EVENT REIoORI (PLEASE PAINT ALL AEOUIREO INFORMATION)
LiCKNSTE                                                                                              LtCI ttSE.              IVTNT NL'VE                                      LL IttSE tiUMBLR                                           TYPE                    I v I'E toOjI       t1   I     D     C     C   1           0   0       0     0   0     0                               4     t   i       l l         ~03
                    ~
                                                                                                                                                                  )
7    09                                14      15                                                              20                       Jo     31       32 Afponr      ntpont CLTT Gonv                                         OOCKK t t'UMrB'LR                               f VINT Ontf                        ntPORT OATK
[oagcour                            ~L                    0   5   0     0         3     1   5       0     5     0 6 7           6         0     6     0     I       7     6 7    0          57      50        59        00                                              60     09                               74     75                                 UO EVENT OESCRIPTION
[oO]         WHILE It( NCDE             5,   DURING ICE CONDENSER INLET DOOR OPENING TORQUE SURVEILLANCE TESTING, 7   0 9                                                                                                                                                                             UO
'
LOWER       INLET       DOOR     1-R OPENING       TORQUE WAS FOUND                 IN EXCESS'OF TECHNICAL SPECIFICATION 7   0 9                                                                                                                                                                             UO Qpjn         PARAGRAPH           4.6.5.3.1           b3 LllklT OF       195 ItlCkt POUNDS.               LOWER         INLET     DOOR     3-L. INITIAL 7    0 9                                                                                                                                                                            UO Jag          OPENlt,G TOR UE              WAS FOUr(D TO BE            IN EXCESS            OF TECHNICAL            SPECIFICATION PARAGRAPH                      4.6.5.3.1 7   0 9 toOQ         bl Llt1IT         OF   675 It(CH POUt<DS.             DOOR     1-R SPRING TEttSIOt< (SEE SUPPLEtkENT)                               (RO-50-315/76<i0 7   0 9                                                                       Pnnr E SYSTKti       CAUSE                                             CCrrtrt 4 O4'I           COLrPONINT COOK          CODE                COVPONENT CODE                      'Uf R             MLtuUt LOT UrrtR
[nn')   ~so               F             X    X    X  X    X X                                W    1    2      0 7   0 0 10                 11         12                           17          43            44 CAUSE OESCRIPTION
[oa~j       DOOR       1-R Llt>IT         WAS EXCEEDED DUE TO               SPRING TENSION DRIFT.                       DOOR       3-L INITIAL OPENING 7   0 9                                                                                                                                                                           00 X EEDED       L"ItlITS BECAUSE         OF AN     ICE BUILDUP FROtl CONDENSATION                           ON THE LOWER               SILL.
7   0 9
  ~1O 7   09       TLCtLITY                                                                  MEIHOO OF STLTUS                 POtttf n               otiiKA sTntUs                OISCOVf A V                          otscovf AY of scn'.ptIQN
                                  ~00 UO'u)
Lsj                            o           NA                                                SURVEILLANCE TESTING 7   0         9               10               12   13                                     45        40 FOtttl   OF ACTIVITY       CO@TENT aMourtt of nctiv:tv                                                      LOfnttON      OF RELKnSE NA 7   0         9                 10     11                                         nn        45 PERSONNEL EXPOSURES tiUMBER           TYPE       OESCRlPTtON
          ~00           0         T               ttA 7   09                 11       'l2   13 PERSONNEL INJURIES tiUMBEA             OESCRIPTtON
[i')0 9~00 7
0 11   12 ttA UU PROBABLE CONSEQUENCES t115j       tiA 7   0'9                                                                                                                                                                           Uo LOSS OR DAMAGE TO FACILITY T'vpE       oEscnpooti tIIsj     Z             tlA 7   09             10 PUULICITY
[lli)       t'iA 0 9 AOOITIONAL FACTORS rtA Qg      I 7    8 9 9]      NA 7    04J J. RISCHLlttG                                                                    P>IOIIE{616)4G5 5901(368 Gt'4t   e tt I ~ a 0 1
 
SUPPLEt'iEt<T TO REPORTABLE OCCURRENCE   RO-50-315/76- 4 SUPPLEMENT TO EVENT DESCRIPTION WAS ADJUSTED TO PROVIDE A 189 INCH POUND OPENING TORQUE.       DOOR 3-L BOTTOM SILL WAS CLEANED At40   INITIAL OPEttING TORQUE h'AS REMEASURED AT, 287 INCH
'POUNDS.}}

Revision as of 18:50, 20 October 2019

LER-1976-023-00 and LER-1976-024-00 for Donald C. Cook, Unit 1 - Failure of Various Containment Isolation Valves to Meet Acceptable Type B Lake Rate Specifications, and Excessive Opening Torque Found in Ice Condenser Lower Inlet Door
ML18219C352
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/02/1976
From: Jurgensen R
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-023-00, LER-1976-024-00
Download: ML18219C352 (10)
v • d • e


Text

NRC FORM 195 V.S. NUCLEAR RFOVLATORV COMMISSION DO TgtgVI 0 E FI I2 70) o FILE NVMOER NR DISTRIBUTION FDR PART 50 DOCI(ET MATERIAL INCIDENT REPORT To: J.G. Keppl er FRDM: Indiana 8 Michigan Power Co. DATE OF DOCUMENT Bridgman, Michigan 6-2-76 R.lJ. Jurgensen DATE RECEIVED 6-10-76 SLETTER NOTOR I Z E D PROP INPUT FORM NUMBER OF COPIES RECEIVED 0ORIGINAI EI V N C LASS I F I E D

'

QCOPV 30 DESCRIPTldN ENCLOSURE Licensee Event Report (%.0. II 76-23) on 5-2-76 Ltr. trans the followihg........ Concerning Various Valves (Isloation) failed to meet acceptable leak rate Specifications......

- Licensee Event Report (R.O. k'6-24) on 6-76 Concer'ning"Lower. Inlet. Door'-R* opening 'Torque being in excess of Tech. Sepc.......

(30 Carbon Sisgned Cys. REceived)

ACKNOWLEDGED DO NOT REMOVZ PLANT NA1IE. Cook b 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED..

SEND DIRECTLY TO KREGER/J, COLLINS

- SAFETY FOR ACTION/INFORMATION ENVIRO SAB 6-10-76 BRANCH CHIEF: Kniel W 3 CYS FOR ACTION LIC ~ -ASST: Lee W/ CYS ACRS 'YS ENT TO LA INTERNAL DISTRIBUTION NRC PDR ICE 2 SCHROEDER/IPPOLITO NOVAK CHECK IES S . E TEDESCO HACCA EN BAER SHAO VOLLH~BH BUNCH KRE E 0 N EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: ~

TIC NSIC 5879"

3 I~

3 ~ 3 I' 3 Ilt II

~egtffatoty QL cd

@Afar o4 INDIANA 8 NICHIGAN I'DN'E IANy DONALD C. COOK NUCL PL@~>'km P.O. Box 458, Bridgmnn,>hi gran 4SLIC 3

ig gog7.92 June 2, 1976 ANION 876~

g~q teton p~g Clerk

<95.  %%%lNtK.'t Hr. J.G. Keppler, Regional Direc a ~jg Office of 'Inspection and Enforcement United States Nuclear Regulatory Commission I.

Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315

Dear lhr'. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide

1. 16, Revision 4, Section 2.b, the following reports are submitted:

R0-50-315/76-23 RO-50-315/76-24 Sincerely, r

R.M. ge en Plant tan er

/bab cc: R.S. Hunter

-J.E. Dolan G.E. Lien R. Kilburn R.J. Vollen BPI R.C. Callen 1/PSC K.R. Baker RO:III P.W. Steketee, Esq.

R. Walsh, Esq.

G , Charnoff, Esq G. Olson J.N. Hennigan PNSRC R.S..Keith

'Dir., IE (30 copies)

Dir., 1<IPC {3 copies)

~ LICENSES SVSNT aePORTi CONTROL 0LOCK: (PLEASE PRINT ALL REOUIREO INFORIVIATION) 1 0 LtCENSf f LCT NSE EVENT NAhtf LtCLNSE t6uhtIILA IVPL. TYPE 0 0 0 0: 0 0 0 0 4 1 1 1 1 +0+]

~'9 14 15 5 30 31 32 AFT'OAT AfPOAT CAT EOOAY kuhIOIA fVENT OA'If Aft'CAT OATF

'0 TYPE SOUSE OOCKET

[oagcow T L050 03 15/ 0 5 O 8 Z 6 ~0 7 0 57 59 74 75 EVENT DESCRIPTION Jog WHILE IN t'lODE 5 DURING SURVEILLANCE TESTIttG OF CONTAINMENT ISOLATION VALVES VARIOUS UD AC l P TYP . AK' P 7 0 9 UD toOj R N A P IFICATIOt NA 9 00 LOSS OR DAMAGE TO FACILITY T v PE OESCA:P T TON Z NZ 7 8 9 10 PUULICITY tIA 7 8 9 t'DDITIONAL I'ACTORS pg I ttA 7

7 gH 09 l~ UO JACK RISCHLIttG p~,ig.~616 465 59~01 368)

G>0 ddI 46 1

'4 P SUPPLEt1EHT TO REPORTABLE OCCURREtfCE RO-50-315 76- 23 SUPPLEHENT TO EVEtiT DESCRIPTION THE FOLLOMIt<G VALVES MERE FOUND=TO HAVE EXCESSIVE LEAKAGE:

DCR-621 MCR-905 ECR-15 HSW-415-3 GCR-314 NSW-415-4 NCR-105 WCR-922 NCR-106 WCR-921 NSW-244-2 HSW-417-3 NSW-244-3 VCR-106 NSM-244-4 VCR-206 MCR-958 SI-189 HSW-417-4 N-102 NSM-415-1 SH-1 NSW-415-2

t>>

l,i

CONTROL BLOCK:

~ LICENSEE EVENT REIoORI (PLEASE PAINT ALL AEOUIREO INFORMATION)

LiCKNSTE LtCI ttSE. IVTNT NL'VE LL IttSE tiUMBLR TYPE I v I'E toOjI t1 I D C C 1 0 0 0 0 0 0 4 t i l l ~03

~

)

7 09 14 15 20 Jo 31 32 Afponr ntpont CLTT Gonv OOCKK t t'UMrB'LR f VINT Ontf ntPORT OATK

[oagcour ~L 0 5 0 0 3 1 5 0 5 0 6 7 6 0 6 0 I 7 6 7 0 57 50 59 00 60 09 74 75 UO EVENT OESCRIPTION

[oO] WHILE It( NCDE 5, DURING ICE CONDENSER INLET DOOR OPENING TORQUE SURVEILLANCE TESTING, 7 0 9 UO

'

LOWER INLET DOOR 1-R OPENING TORQUE WAS FOUND IN EXCESS'OF TECHNICAL SPECIFICATION 7 0 9 UO Qpjn PARAGRAPH 4.6.5.3.1 b3 LllklT OF 195 ItlCkt POUNDS. LOWER INLET DOOR 3-L. INITIAL 7 0 9 UO Jag OPENlt,G TOR UE WAS FOUr(D TO BE IN EXCESS OF TECHNICAL SPECIFICATION PARAGRAPH 4.6.5.3.1 7 0 9 toOQ bl Llt1IT OF 675 It(CH POUt<DS. DOOR 1-R SPRING TEttSIOt< (SEE SUPPLEtkENT) (RO-50-315/76<i0 7 0 9 Pnnr E SYSTKti CAUSE CCrrtrt 4 O4'I COLrPONINT COOK CODE COVPONENT CODE 'Uf R MLtuUt LOT UrrtR

[nn') ~so F X X X X X X W 1 2 0 7 0 0 10 11 12 17 43 44 CAUSE OESCRIPTION

[oa~j DOOR 1-R Llt>IT WAS EXCEEDED DUE TO SPRING TENSION DRIFT. DOOR 3-L INITIAL OPENING 7 0 9 00 X EEDED L"ItlITS BECAUSE OF AN ICE BUILDUP FROtl CONDENSATION ON THE LOWER SILL.

7 0 9

~1O 7 09 TLCtLITY MEIHOO OF STLTUS POtttf n otiiKA sTntUs OISCOVf A V otscovf AY of scn'.ptIQN

~00 UO'u)

Lsj o NA SURVEILLANCE TESTING 7 0 9 10 12 13 45 40 FOtttl OF ACTIVITY CO@TENT aMourtt of nctiv:tv LOfnttON OF RELKnSE NA 7 0 9 10 11 nn 45 PERSONNEL EXPOSURES tiUMBER TYPE OESCRlPTtON

~00 0 T ttA 7 09 11 'l2 13 PERSONNEL INJURIES tiUMBEA OESCRIPTtON

[i')0 9~00 7

0 11 12 ttA UU PROBABLE CONSEQUENCES t115j tiA 7 0'9 Uo LOSS OR DAMAGE TO FACILITY T'vpE oEscnpooti tIIsj Z tlA 7 09 10 PUULICITY

[lli) t'iA 0 9 AOOITIONAL FACTORS rtA Qg I 7 8 9 9] NA 7 04J J. RISCHLlttG P>IOIIE{616)4G5 5901(368 Gt'4t e tt I ~ a 0 1

SUPPLEt'iEt<T TO REPORTABLE OCCURRENCE RO-50-315/76- 4 SUPPLEMENT TO EVENT DESCRIPTION WAS ADJUSTED TO PROVIDE A 189 INCH POUND OPENING TORQUE. DOOR 3-L BOTTOM SILL WAS CLEANED At40 INITIAL OPEttING TORQUE h'AS REMEASURED AT, 287 INCH

'POUNDS.

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