ML18219C361: Difference between revisions

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{{#Wiki_filter:NRC FOAM 195 U.S.NUCLEAR AEGULATORY COMMISSION 12 7B)NRC DISTRIBUTION FDA PART 50 DOCKET MATERIAL DOCKET NUMBER 50-315 FILE NUMBER INCIDENT REPORT J.G.Keppler FRQM: Indiana 8I Michigan Power Co: Bridgman, Michigan R.W.Jurgensen DATE OF DOCUMENT 4-7-76 DATE RECEIVED 4-9 76 OLETTEA, QORIGINAL ,l3COPY ONOTOR IZED g UN C LASS IF I E D~~~~'i PROP INPUT FORM NUMBER OF COPIES RECEIVED 30 DESCRIPTION Ltr.trans the followngg.......
{{#Wiki_filter:NRC FOAM 195                                               U.S. NUCLEAR AEGULATORY COMMISSION DOCKET NUMBER 12 7B)                                                                                                         50-315 FILE NUMBER NRC DISTRIBUTION FDA PART 50 DOCKET MATERIAL                                                 INCIDENT REPORT J.G. Keppler                               FRQM:   Indiana   8I Michigan Power Co:             DATE OF DOCUMENT Bridgman, Michigan                                   4-7-76 R.W. Jurgensen                               DATE RECEIVED 4-9 76 OLETTEA,               ONOTOR IZED                  PROP                  INPUT FORM                    NUMBER OF COPIES RECEIVED QORIGINAL                               ~ ~~~'i
ENCLOSURE RO P'6-14, on 3-25-76, Concerning Inadequate Data Review.......
    ,l3COPY g UN C LASS IF IE D 30 DESCRIPTION                                                         ENCLOSURE Ltr. trans the followngg.......                                     RO   P'6-14,           on   3-25-76, Concerning Inadequate Data     Review.......
(30 Cys.Received)~--p gt.+',4...1 DO NOT H,a~MOVE ACKNOWLEDGED PLANT NANE: COOk 8 1 NOTE!IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.COLLINS SAFETY BRANCH CHIEF: W 3 CYS FOR ACTION LIC~ASST:.FOR ACTION/INFORMATION
(30 Cys. Received)
'ENVIRO 9/CYS ACRS 16 CYS KNQXNQ/ENT TO LA~NRC PDR I&E 2 SCHROEDER/IPPOLITO NOVAK CHECK S HWEN E INTERNAL D IST RI BUTION TEDES 0 HACCA F BAER SHAO VOLLMER BUN H KRE E OL S LPDR:.eP TIC NSIC EXTERNAL DISTRIBUTION CONTROL NUMBER 3602 NRC FORM 155 (2-76)
                                                                              ~ - - p gt.+',4...1 DO NOT H,a~MOVE ACKNOWLEDGED PLANT NANE: COOk 8 1                                                 NOTE!         IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY                                     FOR ACTION/INFORMATION                        'ENVIRO BRANCH CHIEF:
J 0 0 I*~t, l Filo Cy, AQUA, r i INDIA NA 8 lÃICHIGA N'D VER CD DONALD C.COOK NUCLEAR P P.O.Box 4SB, Bridgman, Michigan April 7, 1976 Cp oo~((U5tgq'lSggg'ON geyy~ao 4g~~b I cF'Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No.50-315
W 3 CYS FOR ACTION LIC ~ ASST: .
9/   CYS ACRS   16 CYS   KNQXNQ/ ENT TO LA               ~
INTERNAL D IST RI BUTION NRC PDR I &E     2 SCHROEDER/IPPOLITO NOVAK CHECK S   HWEN E TEDES 0 HACCA F
BAER SHAO VOLLMER BUN H KRE E         OL   S EXTERNAL DISTRIBUTION                                                    CONTROL NUMBER LPDR:     . eP TIC NSIC                                                                                                               3602 NRC FORM 155 (2-76)


==Dear Mr.Keppler:==
J 0 0 I * ~
Pursuant,to the requirements of Appendix"A" Technical Specifications and the United States Nuclear Regulatory Comiission Regulatory Guide 1.16, Revision 4, Section 2.a the following report is submitted:
t, l
 
Filo Cy, Cp oo~
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                                                                '
AQUA,                                ((
ri    INDIANA 8 lÃICHIGAN    'D  VER CD DONALD C. COOK NUCLEAR P                          lSggg'ON P.O. Box 4SB, Bridgman, Michigan              geyy~
ao 4g ~~
April 7,                                      b                            I 1976                                                          cF '
Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region    III 799 Roosevelt    Road Glen  Ellyn, IL    60137 Operating License DPR-58 Docket No. 50-315
 
==Dear Mr. Keppler:==
 
Pursuant,to the requirements of Appendix "A" Technical Specifications and the United States Nuclear Regulatory Comiission Regulatory Guide 1.16, Revision 4, Section 2.a the following report is submitted:
RO 50-315/76-14.
RO 50-315/76-14.
This event had been reported to NRC RO: III by telephone and letter on March 25, 1976.Sincerely,R.W.Jurgensen Plant Manager/bab cc: R.S.Hunter J.E.Dolan G.E.Lien R.Kilburn R.J.Yollen BPI~R.C.Callen MPSC K.R.Baker RO: III P.W.Steketee, Esq.R.Walsh, Esq.G.Charnoff, Esq.G.Olson J.M.Hennigan PNSRC R.S.Keith Dir., IE (40 copies)Dir., MIPC (4 copies)3602 C t Ik C t'h C t g C A CDNTROL 8LOCK: 1 LICENSEE EVENT REPORT (PL ASS PRINT ALL REOUIREO INFORMATION)
This event had been       reported to   NRC RO:   III by             telephone and letter on March 25, 1976.
LICENSEE NAME LICENSE NUMBER LICENSE TYPE EVENT TYPE.[oaj I 0 C C I 7 89 14 15 0 0-0 0 0 0 0 4 I 1 I 1~01 25 26 30.31 32 REPORT.AEPOAT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE~o~cow'r~P~L 0 5 0-0 3 1 5 0 3 2 5 7 6 0 4 0 I'6 7 0 57 58 59 60 61 60 69 74 75 80 EVENT DESCRIPTION toOg WHILE IN MODE 1 AT 81 PERCENT POWER, A REVIEW OF SURVEILLANCE TEST DATA TAKEN AS 7 09 00 conj 1975, INDICATED THAT FIVE ICE CONDENSER INLET DOORS EXCEEDED THE MAXIMUM OF 195 INCH-7 0 9 0O Qo5 POUNDS OPENING TORQUE WHEN 40 DEGREES OPEN.ADDITIONALLY, ONE DOOR INDICATED A HINGE top~)FRICTION FORCE IN EXCESS OF 40 INCH-POUNDS AS REQUIRED (SEE SUPPLEMENT)(RO-50-315-76
Sincerely, R.W. Jurgensen Plant Manager
]4 80 7 8 9 SYSTEM COOE PRME COMPONENT SUPPUER CAUSE COOE COMPONENT MANUFACTURER COMPONENT CODE IoO~]~EH~D x x x x x 7 0 9 10 11 12 CAUSE DESCRIPTION Qo0 THE CAUSE OF THE VIOLATION WAS X~N'W 1 2 0 Y 17 43 44 47 A DEFECTIVE SURVEILLANCE TEST PROCEDURE AND INADEQUATE 48 7 89 80 I.REQUIRED BY TECHNICAL SPECIFICATIONS PARAGRAPH 4.6.5.3.1b3 DURING JULY AND OCTOBER, 7 09 Qo9 DATA REVIEW.7 09'10 OISCOVEAY OESCILPTION 7 89 FACIUTY~'ETHOO OF STATUS 55 POWER OTHER STATUS OSCOVEAY E'08 I NA,.~8 ROUTINE DATA REVI EN 7 0 9 10 12 13 44 45.46 , FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE ca Z Z NA 7 o o 10 11 44 45.PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION t[<is]~00 0~2 NA 7 89 11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTION
  /bab cc:     R.S. Hunter J.E. Dolan G.E. Lien R. Kilburn R.J. Yollen BPI                                                               3602
~14~OJQJ NA 7 89 11 12 PROBABLE CONSEQUENCES Q~I ANALYSIS'WAS DONE WITH THE ACTUAL MEASURED VALUES AND THERE WERE NO SAFETY RELATFD 80 80 80 80 80 80 00 7 09 LOSS OR DAMAGE TO FACILITY TYPE OESCFUPTION 0~~3 Z NA 7 89 10 PUBLICITY Qc7]NA CONSEQUENCES.
        ~ R.C. Callen MPSC K.R. Baker RO: III P.W. Steketee, Esq.
0o 80 7 89 80 ADDITIONAL FACTORS gg PREVENTATIVE ACTION TAKEN TO AVOID RECURRENCE OF THIS TYPE OF PROBLEM INCLUDES~THE 7 00 00 Pg LFOLLOl'IING'II ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES ISEE SUPPL~EMENTI 7 89 NAME.T.F.PLUNKETT PHDNE 616 465 5901(331 CPO 88I~887 0 C~r SUPPLEMENT TO RO-050-315/76-14 SUPPLEMENT TO DESCRIPTION OF CONDITION BY TECHNICAL SPECIFICATIONS PARAGRAPH 4.6.5.3.lb5.
R. Walsh, Esq.
THE ACTUAL MEASURED VALUES WERE AS FOLLOWS: DOOR NUMBER 15L 15R 19R 22R 23L DOOR NUMBER 23L OPENING TOR UE (inch-pounds) 223 213 245 207~236 HINGE FRICTION FORCE (inch-pounds) 45 THE FAILURE TO RECOGNIZE THE DOORS DEFICIENT CONDITION AT THE TIME OF THE TEST'WAS DUE IN PART TO THE SURVEILLANCE TEST PROCEDURE NOT DIRECTLY SPECIFYING THE OPENING TORQUE AS A TECHNICAL SPECIFICATION ITEM AND IN'I PART TO INADEQUATE'DATA REVIEW AT THE TIK': OF THE TESTS.ON MARCH 25, 1976, THE PLANT WAS BROUGHT TO MODE 2 AND ALL INLET DOORS WERE TESTED WITH SATISFACTORY RESULTS.A TEMPORARY CHANGE SHEET WAS WRITTEN TO CORRECT SURVEILLANCE TEST PROCEDURE TKP 4030 STP.207 AND A PROCEDURE REVISION WAS INITIATED TO PROPERLY SPECIFY THE REQUIRED TORQUE VALUES ON THE DATA SHEET.SUPPLEMENT TO ADDITIONAL FACTORS ARE BEING REVISED TO ENSURE THAT THEY ACCURATELY REFLECT THE REQUIREMENTS
G. Charnoff, Esq.
.OF THE TECHNICAL SPECIFICATIONS.
G. Olson J.M. Hennigan PNSRC R.S. Keith Dir.,   IE (40 copies)
(2)ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES WILL BE REVISED TO CLARIFY THE ACCEPTABLE CRITERIA PORTION OF THE PROCEDURE AND INCLUDE DATA SPECIFICATIONS ON THE DATA SHEETS TO AFFORD BETTER REVIEW OF DATA TAKEN.
Dir.,   MIPC (4 copies)
C t
 
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Ik C  t g C
A
 
LICENSEE EVENT REPORT CDNTROL 8LOCK:                                                                       (PL ASS PRINT ALL REOUIREO INFORMATION) 1 LICENSEE                                                                                       LICENSE                EVENT NAME                                       LICENSE NUMBER                                     TYPE                   TYPE
.[oaj             I   0     C     C     I           0   0   0       0   0   0   0                       4   I     1     I   1     ~01 7 89                                      14      15                                              25   26                       30. 31     32 REPORT.     AEPOAT
  ~o~   cow'r~     CATEGORY 57    58 TYPE P
59 SOURCE
                                                  ~L 60 0   5 OOCKET NUMBER 0   0       3   1   5 60      69 0   3 EVENT OATE 2   5     7   6 74 0
75 4
REPORT OATE 0   I'       6 80 7 0                                                       61 EVENT DESCRIPTION I
toOg WHILE IN MODE 1 AT 81 PERCENT POWER, A REVIEW OF SURVEILLANCE TEST DATA TAKEN AS 7 89 7
conj 7 0 9 09
        . REQUIRED          BY TECHNICAL SPECIFICATIONS PARAGRAPH 4. 6. 5. 3. 1b3 DURING JULY AND OCTOBER, 1975, INDICATED THAT FIVE ICE                           CONDENSER       INLET   DOORS     EXCEEDED THE MAXIMUM OF 195                   INCH-80 00 0O Qo5       POUNDS OPENING TORQUE WHEN                         40   DEGREES     OPEN.       ADDITIONALLY, ONE             DOOR     INDICATED A HINGE top~)     FRICTION FORCE IN EXCESS OF 40 INCH-POUNDS AS REQUIRED                                             (SEE SUPPLEMENT)(RO-50-315-76                     ]4 7   8 9                                                                     PRME                                                                              80 SYSTEM       CAUSE                                            COMPONENT              COMPONENT COOE       COOE                  COMPONENT CODE              SUPPUER             MANUFACTURER IoO~]   ~EH             ~D               x     x     x   x   x   X        ~N
                                                                                              'W 1    2    0              Y 7   0 9 10               11           12                         17        43          44                  47            48 CAUSE DESCRIPTION Qo0     THE CAUSE OF THE VIOLATION WAS A DEFECTIVE SURVEILLANCE TEST PROCEDURE AND INADEQUATE 7 09                                                                                                                                                            80 Qo9     DATA REVIEW.
7 09                                                                                                                                                           80
'10 7   89                                                 'ETHOO                                                                                                 80 7    0
            ,
FACIUTY STATUS 9
E FORM OF
                            '08 10 55  POWER I
12 13
                                                      ~
NA,.OTHER STATUS 44 OSCOVEAY
                                                                                        ~8 45 OF
                                                                                                  .46 OISCOVEAY OESCILPTION ROUTINE DATA REVI EN 80 ACTIVITY       COATENT RELEASEO     OF RELEASE                 AMOUNT OF ACTIVITY                                             LOCATION OF RELEASE ca             Z                 Z           NA 7   o         o                 10       11                                   44       45                                                                   80
        . PERSONNEL EXPOSURES NUMBER           TYPE         OESCRIPTION                                                                   t
[<is]   ~00           0       ~2                   NA 7   89                 11       12       13                                                                                                                   80 PERSONNEL INJURIES NUMBER             OESCRIPTION
  ~14 7   89
          ~OJQJ11              12 NA 00 PROBABLE CONSEQUENCES Q~
7 I09      ANALYSIS         'WAS DONE         WITH THE ACTUAL MEASURED VALUES AND THERE WERE NO SAFETY RELATFD CONSEQUENCES.            0o LOSS OR DAMAGE TO FACILITY TYPE       OESCFUPTION 0~~3       Z           NA 7   89           10                                                                                                                                           80 PUBLICITY Qc7]       NA 7 89                                                                                                                                                           80 ADDITIONAL FACTORS gg00 PREVENTATIVE ACTION                           TAKEN TO AVOID RECURRENCE OF THIS TYPE OF PROBLEM INCLUDES ~THE 7                                                                                                                                                             00 ISEE SUPPL~EMENTI Pg LFOLLOl'IING'II ALL                           PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES 7   89 NAME.       T.F.       PLUNKETT                                                       PHDNE   616 465 5901(331 CPO   88I 887
                                                                                                                                                              ~
 
C~r 0
 
SUPPLEMENT TO   RO-050-315/76-14 SUPPLEMENT TO DESCRIPTION OF CONDITION BY TECHNICAL SPECIFICATIONS PARAGRAPH   4.6.5.3.lb5.     THE ACTUAL MEASURED VALUES WERE AS FOLLOWS:
DOOR NUMBER                     OPENING TOR UE     (inch-pounds) 15L                              223 15R                              213 19R                              245 22R                              207 ~
23L                              236 DOOR NUMBER                HINGE FRICTION FORCE       (inch-pounds) 23L                                45 THE FAILURE TO RECOGNIZE THE DOORS DEFICIENT CONDITION AT THE TIME OF THE TEST 'WAS DUE IN PART TO THE SURVEILLANCE TEST PROCEDURE NOT DIRECTLY SPECIFYING THE OPENING TORQUE AS A TECHNICAL SPECIFICATION ITEM AND IN
          'I PART TO INADEQUATE'DATA REVIEW AT THE   TIK': OF THE TESTS. ON MARCH   25, 1976,   THE PLANT WAS BROUGHT TO MODE 2 AND ALL INLET DOORS WERE TESTED WITH SATISFACTORY RESULTS. A TEMPORARY CHANGE SHEET WAS WRITTEN TO CORRECT SURVEILLANCE TEST PROCEDURE TKP   4030 STP.207 AND A     PROCEDURE REVISION   WAS INITIATED TO PROPERLY SPECIFY THE REQUIRED     TORQUE VALUES ON THE DATA SHEET.
SUPPLEMENT TO ADDITIONAL FACTORS ARE BEING REVISED TO ENSURE THAT THEY ACCURATELY REFLECT THE REQUIREMENTS
      . OF THE TECHNICAL   SPECIFICATIONS.
(2) ALL   PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES     WILL BE REVISED TO CLARIFY THE ACCEPTABLE CRITERIA PORTION OF THE PROCEDURE AND INCLUDE DATA SPECIFICATIONS   ON THE DATA SHEETS TO AFFORD BETTER REVIEW OF DATA TAKEN.
 
P}}
P}}

Revision as of 18:49, 20 October 2019

LER-1976-014-00 for Donald C. Cook, Unit 1 - Violation of Technical Specifications Paragraph 4.6.5.3.1b3
ML18219C361
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/07/1976
From: Jurgensen R, Shaller D
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-014-00
Download: ML18219C361 (8)


Text

NRC FOAM 195 U.S. NUCLEAR AEGULATORY COMMISSION DOCKET NUMBER 12 7B) 50-315 FILE NUMBER NRC DISTRIBUTION FDA PART 50 DOCKET MATERIAL INCIDENT REPORT J.G. Keppler FRQM: Indiana 8I Michigan Power Co: DATE OF DOCUMENT Bridgman, Michigan 4-7-76 R.W. Jurgensen DATE RECEIVED 4-9 76 OLETTEA, ONOTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL ~ ~~~'i

,l3COPY g UN C LASS IF IE D 30 DESCRIPTION ENCLOSURE Ltr. trans the followngg....... RO P'6-14, on 3-25-76, Concerning Inadequate Data Review.......

(30 Cys. Received)

~ - - p gt.+',4...1 DO NOT H,a~MOVE ACKNOWLEDGED PLANT NANE: COOk 8 1 NOTE! IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION 'ENVIRO BRANCH CHIEF:

W 3 CYS FOR ACTION LIC ~ ASST: .

9/ CYS ACRS 16 CYS KNQXNQ/ ENT TO LA ~

INTERNAL D IST RI BUTION NRC PDR I &E 2 SCHROEDER/IPPOLITO NOVAK CHECK S HWEN E TEDES 0 HACCA F

BAER SHAO VOLLMER BUN H KRE E OL S EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: . eP TIC NSIC 3602 NRC FORM 155 (2-76)

J 0 0 I * ~

t, l

Filo Cy, Cp oo~

U5tgq

'

AQUA, ((

ri INDIANA 8 lÃICHIGAN 'D VER CD DONALD C. COOK NUCLEAR P lSggg'ON P.O. Box 4SB, Bridgman, Michigan geyy~

ao 4g ~~

April 7, b I 1976 cF '

Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant,to the requirements of Appendix "A" Technical Specifications and the United States Nuclear Regulatory Comiission Regulatory Guide 1.16, Revision 4, Section 2.a the following report is submitted:

RO 50-315/76-14.

This event had been reported to NRC RO: III by telephone and letter on March 25, 1976.

Sincerely, R.W. Jurgensen Plant Manager

/bab cc: R.S. Hunter J.E. Dolan G.E. Lien R. Kilburn R.J. Yollen BPI 3602

~ R.C. Callen MPSC K.R. Baker RO: III P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC R.S. Keith Dir., IE (40 copies)

Dir., MIPC (4 copies)

C t

t

'h C

Ik C t g C

A

LICENSEE EVENT REPORT CDNTROL 8LOCK: (PL ASS PRINT ALL REOUIREO INFORMATION) 1 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

.[oaj I 0 C C I 0 0 0 0 0 0 0 4 I 1 I 1 ~01 7 89 14 15 25 26 30. 31 32 REPORT. AEPOAT

~o~ cow'r~ CATEGORY 57 58 TYPE P

59 SOURCE

~L 60 0 5 OOCKET NUMBER 0 0 3 1 5 60 69 0 3 EVENT OATE 2 5 7 6 74 0

75 4

REPORT OATE 0 I' 6 80 7 0 61 EVENT DESCRIPTION I

toOg WHILE IN MODE 1 AT 81 PERCENT POWER, A REVIEW OF SURVEILLANCE TEST DATA TAKEN AS 7 89 7

conj 7 0 9 09

. REQUIRED BY TECHNICAL SPECIFICATIONS PARAGRAPH 4. 6. 5. 3. 1b3 DURING JULY AND OCTOBER, 1975, INDICATED THAT FIVE ICE CONDENSER INLET DOORS EXCEEDED THE MAXIMUM OF 195 INCH-80 00 0O Qo5 POUNDS OPENING TORQUE WHEN 40 DEGREES OPEN. ADDITIONALLY, ONE DOOR INDICATED A HINGE top~) FRICTION FORCE IN EXCESS OF 40 INCH-POUNDS AS REQUIRED (SEE SUPPLEMENT)(RO-50-315-76 ]4 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT CODE SUPPUER MANUFACTURER IoO~] ~EH ~D x x x x x X ~N

'W 1 2 0 Y 7 0 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Qo0 THE CAUSE OF THE VIOLATION WAS A DEFECTIVE SURVEILLANCE TEST PROCEDURE AND INADEQUATE 7 09 80 Qo9 DATA REVIEW.

7 09 80

'10 7 89 'ETHOO 80 7 0

,

FACIUTY STATUS 9

E FORM OF

'08 10 55 POWER I

12 13

~

NA,.OTHER STATUS 44 OSCOVEAY

~8 45 OF

.46 OISCOVEAY OESCILPTION ROUTINE DATA REVI EN 80 ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE ca Z Z NA 7 o o 10 11 44 45 80

. PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION t

[<is] ~00 0 ~2 NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

~14 7 89

~OJQJ11 12 NA 00 PROBABLE CONSEQUENCES Q~

7 I09 ANALYSIS 'WAS DONE WITH THE ACTUAL MEASURED VALUES AND THERE WERE NO SAFETY RELATFD CONSEQUENCES. 0o LOSS OR DAMAGE TO FACILITY TYPE OESCFUPTION 0~~3 Z NA 7 89 10 80 PUBLICITY Qc7] NA 7 89 80 ADDITIONAL FACTORS gg00 PREVENTATIVE ACTION TAKEN TO AVOID RECURRENCE OF THIS TYPE OF PROBLEM INCLUDES ~THE 7 00 ISEE SUPPL~EMENTI Pg LFOLLOl'IING'II ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES 7 89 NAME. T.F. PLUNKETT PHDNE 616 465 5901(331 CPO 88I 887

~

C~r 0

SUPPLEMENT TO RO-050-315/76-14 SUPPLEMENT TO DESCRIPTION OF CONDITION BY TECHNICAL SPECIFICATIONS PARAGRAPH 4.6.5.3.lb5. THE ACTUAL MEASURED VALUES WERE AS FOLLOWS:

DOOR NUMBER OPENING TOR UE (inch-pounds) 15L 223 15R 213 19R 245 22R 207 ~

23L 236 DOOR NUMBER HINGE FRICTION FORCE (inch-pounds) 23L 45 THE FAILURE TO RECOGNIZE THE DOORS DEFICIENT CONDITION AT THE TIME OF THE TEST 'WAS DUE IN PART TO THE SURVEILLANCE TEST PROCEDURE NOT DIRECTLY SPECIFYING THE OPENING TORQUE AS A TECHNICAL SPECIFICATION ITEM AND IN

'I PART TO INADEQUATE'DATA REVIEW AT THE TIK': OF THE TESTS. ON MARCH 25, 1976, THE PLANT WAS BROUGHT TO MODE 2 AND ALL INLET DOORS WERE TESTED WITH SATISFACTORY RESULTS. A TEMPORARY CHANGE SHEET WAS WRITTEN TO CORRECT SURVEILLANCE TEST PROCEDURE TKP 4030 STP.207 AND A PROCEDURE REVISION WAS INITIATED TO PROPERLY SPECIFY THE REQUIRED TORQUE VALUES ON THE DATA SHEET.

SUPPLEMENT TO ADDITIONAL FACTORS ARE BEING REVISED TO ENSURE THAT THEY ACCURATELY REFLECT THE REQUIREMENTS

. OF THE TECHNICAL SPECIFICATIONS.

(2) ALL PERFORMANCE SECTION SURVEILLANCE TEST PROCEDURES WILL BE REVISED TO CLARIFY THE ACCEPTABLE CRITERIA PORTION OF THE PROCEDURE AND INCLUDE DATA SPECIFICATIONS ON THE DATA SHEETS TO AFFORD BETTER REVIEW OF DATA TAKEN.

P