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i O                                 O P. O. Box 361, Platteville, Colorado 80651 October 2, 1975   -
i O
i
O P. O. Box 361, Platteville, Colorado 80651 October 2, 1975 i
                                                                                  *. \ '   .
*. \\ '
                                                                            ,A             ,.s Mr. E. !! orris Howard, Director                           '
,A
                                                                        /-   4:
,.s Nuclear Regulatory Commission 02[.g Mr. E. !! orris Howard, Director
02[.g Nuclear Regulatory Commission        -
/-
Region IV Office of Inspection and Enforec=ent                         '
4:
                                                                                              ~
Region IV Office of Inspection and Enforec=ent
Suite 1000                                                                   .
~
nuington, Texas 76012                                       -
Suite 1000 nuington, Texas 76012 P.EF: Facility Operating License Nn. DFR-34 Docket No. 50-267
P.EF: Facility Operating License                                           ,
                                              .      Nn. DFR-34 Docket No. 50-267                                     ,


==Dear Mr. Howard:==
==Dear Mr. Howard:==
Enclosed please find a copy of Unusual Event Report. No. 50-267/75/17, Preliminary, submitted pcr the requirements of the Technical Specifi-Cations.
Enclosed please find a copy of Unusual Event Report. No. 50-267/75/17, Preliminary, submitted pcr the requirements of the Technical Specifi-Cations.
Very truly'yours,
Very truly'yours,
                                            ,Frederic E. Svart Superintendent, Nuclear. Production
,Frederic E. Svart Superintendent, Nuclear. Production
                                            ~rort St. Vrain Nuclear                                                     -
~rort St. Vrain Nuclear Generating Station FES/alk Mr. Roger S. Boyd
Generating Station FES/alk Mr. Roger S. Boyd                                                                         '/
'/
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                                                                                                          .(
8311080628 751002 PDR ADDCK 05000267 S
8311080628 751002 PDR ADDCK 05000267                                                                                 '
PDR
S                  PDR


                                                                                                                                                                      -64 o
-64 e
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_         9
_ 9 Unusual DISTRIBtTfIONS Events and Abnormal Unusual Operating Monthly occurrence Occurrence
* DISTRIBtTfIONS Unusual
^ Cost Letter Reports R epor *.s Report s Addressee San Francisco Operations Office ERDA 1333 Broad ay Oakland, California 94612 2
* Events and Abnormal               Unusual                 Operating Monthly                 occurrence Occurrence                           ^ Cost Reports             R epor *.s               Report s Letter                                                                                      _
2 2
Addressee San Francisco Operations Office
4 Atta: Manager
* ERDA 1333 Broad ay                                                                                                                                                 '
~
Oakland, California 94612                                                         2                           2                 2                         -
Pinance & Budget 1
Atta: Manager                                                               *                            *                ~                         4 Pinance & Budget                                                 1                           1                 -                        -
1 Calif. Patent Group Division of Reactor Research and Development ERDA Washington, D. C.
Calif. Patent Group Division of Reactor Research and Development ERDA                                                                                                                                                       - -
20545 1
Washington, D. C.         20545                         ,
1 1,
1                           1                1,                       ~
~
Atta: Director                                                                 ~                           ~
Atta: Director
Asst. Dir. for UEBR Programs                                       2                             2                 2                         -
~
Asst. Dir. for Gas Cooled teactor Project                           1                     -      1                 1                         -
~
Asst. Dir. for Engrg. and Technology                               1                           1                 1                         -
Asst. Dir. for UEBR Programs 2
Asst. Dir. for Reactor Safety
2 2
                                                                        #                                                1                 1                         1 1
Asst. Dir. for Gas Cooled teactor Project 1
ERDA -SCRPO-SD                                       .
1 1
P. O. Box 81325                                                                                   .
Asst. Dir. for Engrg. and Technology 1
San Diego, California 92138                                       .
1 1
1                            1 W. Soule', Project Engr.
Asst. Dir. for Reactor Safety 1
ERDA -SCRPO                                                                                 .
1 1
P. O. Box 1446 Canoga Park', California _91304 1                             1                 1
1 ERDA -SCRPO-SD P. O. Box 81325 San Diego, California 92138 1
* Wrsco
1 W. Soule', Project Engr.
* Director                             *                                                                                  ,
ERDA -SCRPO P. O. Box 1446 Canoga Park', California _91304 1
bttr
1 1
* ERDA -SCRPO t2  ++    P. O. Box 1446                                           .
Wrsco
      +*    Canoga Park, California 91304                                         .
* Director bttr ERDA -SCRPO P. O. Box 1446 t2
3                           3 Technical Information Center
++
            .ERDA P. O. Box 62                                                                       ..          .
Canoga Park, California 91304
Oak Ridge, Tennessee 37830 10                           10 ,                 2 John R. Zanot, Project Manager (FFLC)'
+*
* General Atomic Company                                                               '
3 3
P. O. Box 81608 San Diego, California 92138 I"#E f,
Technical Information Center
Por Monthly Letter only:                                   B1ick Bob Clark                    1 P. O. Box 426 Platteville, CO 80651                       R. Walker                   1                           'l 1                            1                  1 P. Svart 1                           'l L. Brey                               **
.ERDA P. O. Box 62 Oak Ridge, Tennessee 37830 10 10,
D. Rodgers'                   1 E. Eill                     1 P. Mathie                   1 1                           'l
2 John R. Zanot, Project Manager (FFLC)'
                                              -                      J. Cahm D. Alexander                 1 J. Liebelt                 1-K. Stannard                 1 (Room 526)                                                                  1 NRC, Director of Regulations, k'ashington,D.C. 20545                                                       d NCoPy of Howard letter & xe                   ** g r8of''
General Atomic Company P. O. Box 81608 San Diego, California 92138 I"#E Por Monthly Letter only:
R. Boyd
f, B1ick P. O. Box 426 Bob Clark 1
      =                                                                                          1                            1                  1 (Chairman.NFSC) Oscar Lee                         i Control Room D. Warembourg               i                           1 1 (letter) copy of letter to Boyd E. Novard i                                                                     P. Bronson                   1
Platteville, CO 80651 R. Walker 1
* M..J. Cooney                 1 Philadelphia Electric Company                                                                                    1                   1 2301 Market St.                                         PORC Committee Philadelphia, Pa.18101
'l P. Svart 1
1 1
L. Brey 1
'l D. Rodgers' 1
E. Eill 1
P. Mathie 1
J. Cahm 1
'l D. Alexander 1
J. Liebelt 1-(Room 526)
K. Stannard 1
1 NRC, Director of Regulations, k'ashington,D.C. 20545 d NCoPy of Howard letter & xe g r of 8 ''
R. Boyd (Chairman.NFSC) Oscar Lee 1
1 1
=
Control Room i
D. Warembourg i
11 (letter) copy of letter to Boyd E. Novard i
P. Bronson 1
Philadelphia Electric Company M..J. Cooney 1
1 1
PORC Committee 2301 Market St.
Philadelphia, Pa.18101


O                                     o REPORT DATE:
O o
October 2, 1975                         UNUSUAL EVENT 75/17 Page 1 of 5 OCCURRENCE DATE:
REPORT DATE:
September 12, 1975 FORT ST. VRAIN NUCLEAR GENERATING STATION                   .
October 2, 1975 UNUSUAL EVENT 75/17 Page 1 of 5 OCCURRENCE DATE:
PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLAITEVILLE, COLORADO 80651 REPORT No. 50-267/75/17 Preliminary IDENTIFICATION OF                                             .
September 12, 1975 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLAITEVILLE, COLORADO 80651 REPORT No. 50-267/75/17 Preliminary IDENTIFICATION OF OCCURRENCE:
OCCURRENCE:
At approximately 1030, September 12, 1975, the orifice valve assembly associated with control rod drive serial nomber 010 was observed to have fallen vertically downward from its nor=al, install'ed position on the control rod drive unit while
At approximately 1030, September 12, 1975, the orifice valve assembly associated with control rod drive serial nomber 010 was observed to have fallen vertically
~
                                                                      ~
it was positioned in a special work stand located over an equipment storage well This control. rod drive unit was in position in the work on the refueling floor.
downward from its nor=al, install'ed position on the control rod drive unit while it was positioned in a special work stand located over an equipment storage well on the refueling floor. This control . rod drive unit was in position in the work stand
stand
* for approximately two days and ha'd not been moved prior to the orifice valve becoming disengaged.
* for approximately two days and ha'd not been moved prior to the orifice valve becoming disengaged.
This has been identified as an unusual event per AC 7.6', Non1 Routine' Reports, Section C.2 of the' Fort St. Vrain Technic,a1' Specifications.
This has been identified as an unusual event per AC 7.6', Non1 outine' Reports, R
CONDITIONS PRIOR                                                         Routine Shutdown TO OCCURRENCE:
Section C.2 of the' Fort St. Vrain Technic,a1' Specifications.
Steady State Power
CONDITIONS PRIOR Routine Shutdown TO OCCURRENCE:
                                                                          -      ' Routine Load Change Hot Shutdown X
Steady State Power Hot Shutdown
Cold Shutdown Other (specify)
' Routine Load Change Other (specify)
Reft $eling Shutdown Routine Startup The major plant parameters at the time of the event were as follows:
X Cold Shutdown Reft $eling Shutdown Routine Startup The major plant parameters at the time of the event were as follows:
RTR            ~*             Wth Power E E'CT
~*
* We Pressure
Wth Power RTR E E'CT We psig Secondary Coolant Pressure
* psig Secondary Coolant Temperature      *            'F Flow
'F Temperature f/hr.
* f/hr.
Flow Primary Coolant Pressure psig
Pressure
*P Core Inlet-Temperature
* psig Primary Coolant Temperature      *-            *P Core Inlet-
~
                                                                                              ~             '


O                                   o IMUSUAL EVENT 75/17 Page 2 of 5 CONDITIONS PRIOR
O o
* TO OCCURRENCE (continued):
IMUSUAL EVENT 75/17 Page 2 of 5 CONDITIONS PRIOR TO OCCURRENCE (continued):
Temperature
'F Core Outlet Primary Coolant Temperature (continued) f/hr.
                                                                      *            'F Core Outlet Primary Coolant (continued)                   F16w
F16w
* f/hr.
*No bearing on this event.
              *No bearing on this event.
DESCRIPTION OF OCCURRENCE:
DESCRIPTION OF OCCURRENCE:
Vrain are in the process of modifica-All of the control rod drives at Fort St.
Vrain are in the process of modifica-All of the control rod drives at Fort St.
tion to eliminate internal gas flow leakage paths (CWP-51). Control rod. drive serial number 010 had been removed from region five of the PCRV and placed in a special work stand on the refueling floor for implementation of the necessary modifications. All operations and handling associated with this control rod drive were routine and normal.
Control rod. drive tion to eliminate internal gas flow leakage paths (CWP-51).
                    ~
serial number 010 had been removed from region five of the PCRV and placed in a special work stand on the refueling floor for implementation of the necessary All operations and handling associated with this control rod modifications.
drive were routine and normal.
~
a functional Upon completing the prescribed approved modifications to this unit,All tests resulted.
a functional Upon completing the prescribed approved modifications to this unit,All tests resulted.
operating test was performed using established procedures.Just prior to preparing in normal response from the control rod drive unit.
operating test was performed using established procedures.Just prior to preparing in normal response from the control rod drive unit.
this unit for return to the PCRV, the orifice valve was observed to have fallen from its normal position at the lower end of the control . rod drive unit.
this unit for return to the PCRV, the orifice valve was observed to have fallen from its normal position at the lower end of the control. rod drive unit.
The dust cover (6) which protects the bolted support assembly           for the orifice -
The dust cover (6) which protects the bolted support assembly for the orifice -
All of the parts were re-valve and actuator shaft was removed for inspection.
All of the parts were re-valve and actuator shaft was removed for inspection.
covered in tact: 1 self-locking. nut (42), 6 belleville washers (41),.1 bearing w:asher (49), and 1 stop plate (15) (see drawing SLR D1201-400G attached). The
covered in tact: 1 self-locking. nut (42), 6 belleville washers (41),.1 bearing w:asher (49), and 1 stop plate (15) (see drawing SLR D1201-400G attached). The
    '' control rod drive unit was then further disassembled as required to allow addi-tional internal inspection of the orifice drive mechanism.
'' control rod drive unit was then further disassembled as required to allow addi-tional internal inspection of the orifice drive mechanism.
APPARENT CAUSE Design                                Unusual Service Cond.
APPARENT CAUSE Unusual Service Cond.
OF OCCURRENCE:                                                         Including Environ.
OF OCCURRENCE:
Manufacture                          Component Failure.
Design Including Environ.
Installation /Const.           X     Other (specify)
Component Failure.
Operator Improper final assembly of the Procedure           . control rod drive unit at time _
Manufacture Installation /Const.
X Other (specify)
Improper final assembly of the Operator Procedure control rod drive unit at time _
of manufacture.
of manufacture.
                                                                                      ~
~
The apparent cause of this occurrence is failure to fully eng ge the lock nut with the threaded portion of the support shaf t'. The locking action of _ the
The apparent cause of this occurrence is failure to fully eng ge the lock nut The locking action of _ the
                                                                  ~
~
with the threaded portion of the support shaf t'.
lock nut requires full engage.ient so that this improper assembly allowed the lock nut to disengage from the shaft.
lock nut requires full engage.ient so that this improper assembly allowed the lock nut to disengage from the shaft.
                                        .                                      6 9
6 9


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O                                         o UNUSUAL EVENT 75/17 Page 4 of 5 ANALYSIS OF
O o
* OCCURRENCE:
UNUSUAL EVENT 75/17 Page 4 of 5 ANALYSIS OF OCCURRENCE:
All of the bolted support parts (12, 42, 49, 41, and 15) (SLR-D1201-400)                         were No' abnormal indi-removed from the control rod drive and       closely   inspected.
All of the bolted support parts (12, 42, 49, 41, and 15) (SLR-D1201-400) were No' abnormal indi-removed from the control rod drive and closely inspected.
cations of any kind could be found. The orifice valve support shaf t and ac-tuator were removed from the control rod drive unit and carefully inspected, with considerable emphasis being given. to the threaded end of the stiaft to which the bolted support is attached. All       threads looked normal; no signs of distress or abnormality could be seen.       All  of the parts were then reassembled This was done to determine that the physical mating of all parts was normal.               Further, tihe self-satisfactorily and 'all parts fit properly and smoothly.
The orifice valve support shaf t and ac-cations of any kind could be found.
locking nut (42) threaded down to its proper position and tightenedThis                    snugly, is nor-was in fact    locked such that a wrench   was   required     to   remove       it.                          .
tuator were removed from the control rod drive unit and carefully inspected, with considerable emphasis being given. to the threaded end of the stiaft to All threads looked normal; no signs of which the bolted support is attached.
'              mal and proper.                            .
All of the parts were then reassembled distress or abnormality could be seen.
'                The only conclusion which can be drawn in view of the observed facts is that                         -
This was done to determine that the physical mating of all parts was normal.
the self-locking nut had never been tightened down properly during initial assembly of the unit. Because the nut was not properly tightened, vibrations and pulsing of the nearby orifice drive motor could have                     caused the nut to back off sufficiently to release the orifice valve. This threaded support is essentially unstressed during normal installation and operation of.the control rod drive which would allow the nut free movement if it were,not preperly tightened.                                       ,
Further, tihe self-satisfactorily and 'all parts fit properly and smoothly.
CORRECTIVE ACTION:                                                                                                     <
(42) threaded down to its proper position and tightened snugly, locking nut This is nor-locked such that a wrench was required to remove it.
Seven spare control rod drives plus the 25 units still to be removed from the PCRV will be inspected to verify that the orifice valve support bolt is properly assembled, and that the retaining nut is tightened to the proper It is felt that this unusual event is an position on the isolated case. mating threads.If any additional discrepancies are found, the additional units, presently installed in the PCRV, will be removed for inspection.
was in fact mal and proper.
The only conclusion which can be drawn in view of the observed facts is that the self-locking nut had never been tightened down properly during initial Because the nut was not properly tightened, vibrations assembly of the unit.
and pulsing of the nearby orifice drive motor could have caused the nut to This threaded support is back off sufficiently to release the orifice valve.
essentially unstressed during normal installation and operation of.the control rod drive which would allow the nut free movement if it were,not preperly tightened.
CORRECTIVE ACTION:
Seven spare control rod drives plus the 25 units still to be removed from the PCRV will be inspected to verify that the orifice valve support bolt is properly assembled, and that the retaining nut is tightened to the proper It is felt that this unusual event is an position on the mating threads.If any additional discrepancies are found, the additional isolated case.
units, presently installed in the PCRV, will be removed for inspection.
FAILURE DATA /SIMILAR REPORTED OCCURRENCES:
FAILURE DATA /SIMILAR REPORTED OCCURRENCES:
* None PROGRAMfATIC IMPACT:
None PROGRAMfATIC IMPACT:
None                                                         .
None
                    ,0DE IMPACT:
,0DE IMPACT:
?-     ,
?-
l                                                       .
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                                                                                                                        -  e,
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                      ~
O O
                  ~
~
O                                          O                              .
~
UNUSUAL EVENT 75/17 Page 5 of 5 Submitted By:    kav C. #               a     _/'n-                                                 -
UNUSUAL EVENT 75/17 Page 5 of 5 kav C. #
a
_/'n-Submitted By:
Harvey W. Hillyard, Jr/
Harvey W. Hillyard, Jr/
Technical Services Supervisor                                         ,
Technical Services Supervisor l-Reviewed By:
l-Reviewed By:                                                                             .
Frank M. Mathie Superintendent Maintenance f?
Frank M. Mathie Superintendent Maintenance f?
Approved By:         /               e    '  .
e I
I pederic E. Swart Superintendent, Nuclear Production 9
Approved By:
/
pederic E. Swart Superintendent, Nuclear Production 9
e S
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a t                                                                                         .
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Latest revision as of 04:00, 14 December 2024

RO 50-267/75/17:on 750912,orifice Valve Assembly Associated W/Control Rod Drive Observed to Have Fallen Vertically Downward from Installed Position.Caused by Improper Final Assembly of Control Rod Drive Unit
ML20085M552
Person / Time
Site: Fort Saint Vrain 
Issue date: 10/02/1975
From: Hillyard H, Mathie F, Swart F
PUBLIC SERVICE CO. OF COLORADO
To: Howard E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
RO-50-267-75-17, NUDOCS 8311080628
Download: ML20085M552 (7)


Text

.

i O

O P. O. Box 361, Platteville, Colorado 80651 October 2, 1975 i

  • . \\ '

,A

,.s Nuclear Regulatory Commission 02[.g Mr. E. !! orris Howard, Director

/-

4:

Region IV Office of Inspection and Enforec=ent

~

Suite 1000 nuington, Texas 76012 P.EF: Facility Operating License Nn. DFR-34 Docket No. 50-267

Dear Mr. Howard:

Enclosed please find a copy of Unusual Event Report. No. 50-267/75/17, Preliminary, submitted pcr the requirements of the Technical Specifi-Cations.

Very truly'yours,

,Frederic E. Svart Superintendent, Nuclear. Production

~rort St. Vrain Nuclear Generating Station FES/alk Mr. Roger S. Boyd

'/

i A,

l f

.(

8311080628 751002 PDR ADDCK 05000267 S

PDR

-64 e

o

_ 9 Unusual DISTRIBtTfIONS Events and Abnormal Unusual Operating Monthly occurrence Occurrence

^ Cost Letter Reports R epor *.s Report s Addressee San Francisco Operations Office ERDA 1333 Broad ay Oakland, California 94612 2

2 2

4 Atta: Manager

~

Pinance & Budget 1

1 Calif. Patent Group Division of Reactor Research and Development ERDA Washington, D. C.

20545 1

1 1,

~

Atta: Director

~

~

Asst. Dir. for UEBR Programs 2

2 2

Asst. Dir. for Gas Cooled teactor Project 1

1 1

Asst. Dir. for Engrg. and Technology 1

1 1

Asst. Dir. for Reactor Safety 1

1 1

1 ERDA -SCRPO-SD P. O. Box 81325 San Diego, California 92138 1

1 W. Soule', Project Engr.

ERDA -SCRPO P. O. Box 1446 Canoga Park', California _91304 1

1 1

Wrsco

  • Director bttr ERDA -SCRPO P. O. Box 1446 t2

++

Canoga Park, California 91304

+*

3 3

Technical Information Center

.ERDA P. O. Box 62 Oak Ridge, Tennessee 37830 10 10,

2 John R. Zanot, Project Manager (FFLC)'

General Atomic Company P. O. Box 81608 San Diego, California 92138 I"#E Por Monthly Letter only:

f, B1ick P. O. Box 426 Bob Clark 1

Platteville, CO 80651 R. Walker 1

'l P. Svart 1

1 1

L. Brey 1

'l D. Rodgers' 1

E. Eill 1

P. Mathie 1

J. Cahm 1

'l D. Alexander 1

J. Liebelt 1-(Room 526)

K. Stannard 1

1 NRC, Director of Regulations, k'ashington,D.C. 20545 d NCoPy of Howard letter & xe g r of 8

R. Boyd (Chairman.NFSC) Oscar Lee 1

1 1

=

Control Room i

D. Warembourg i

11 (letter) copy of letter to Boyd E. Novard i

P. Bronson 1

Philadelphia Electric Company M..J. Cooney 1

1 1

PORC Committee 2301 Market St.

Philadelphia, Pa.18101

O o

REPORT DATE:

October 2, 1975 UNUSUAL EVENT 75/17 Page 1 of 5 OCCURRENCE DATE:

September 12, 1975 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO P. O. BOX 361 PLAITEVILLE, COLORADO 80651 REPORT No. 50-267/75/17 Preliminary IDENTIFICATION OF OCCURRENCE:

At approximately 1030, September 12, 1975, the orifice valve assembly associated with control rod drive serial nomber 010 was observed to have fallen vertically downward from its nor=al, install'ed position on the control rod drive unit while

~

it was positioned in a special work stand located over an equipment storage well This control. rod drive unit was in position in the work on the refueling floor.

stand

  • for approximately two days and ha'd not been moved prior to the orifice valve becoming disengaged.

This has been identified as an unusual event per AC 7.6', Non1 outine' Reports, R

Section C.2 of the' Fort St. Vrain Technic,a1' Specifications.

CONDITIONS PRIOR Routine Shutdown TO OCCURRENCE:

Steady State Power Hot Shutdown

' Routine Load Change Other (specify)

X Cold Shutdown Reft $eling Shutdown Routine Startup The major plant parameters at the time of the event were as follows:

~*

Wth Power RTR E E'CT We psig Secondary Coolant Pressure

'F Temperature f/hr.

Flow Primary Coolant Pressure psig

  • P Core Inlet-Temperature

~

O o

IMUSUAL EVENT 75/17 Page 2 of 5 CONDITIONS PRIOR TO OCCURRENCE (continued):

'F Core Outlet Primary Coolant Temperature (continued) f/hr.

F16w

  • No bearing on this event.

DESCRIPTION OF OCCURRENCE:

Vrain are in the process of modifica-All of the control rod drives at Fort St.

Control rod. drive tion to eliminate internal gas flow leakage paths (CWP-51).

serial number 010 had been removed from region five of the PCRV and placed in a special work stand on the refueling floor for implementation of the necessary All operations and handling associated with this control rod modifications.

drive were routine and normal.

~

a functional Upon completing the prescribed approved modifications to this unit,All tests resulted.

operating test was performed using established procedures.Just prior to preparing in normal response from the control rod drive unit.

this unit for return to the PCRV, the orifice valve was observed to have fallen from its normal position at the lower end of the control. rod drive unit.

The dust cover (6) which protects the bolted support assembly for the orifice -

All of the parts were re-valve and actuator shaft was removed for inspection.

covered in tact: 1 self-locking. nut (42), 6 belleville washers (41),.1 bearing w:asher (49), and 1 stop plate (15) (see drawing SLR D1201-400G attached). The

control rod drive unit was then further disassembled as required to allow addi-tional internal inspection of the orifice drive mechanism.

APPARENT CAUSE Unusual Service Cond.

OF OCCURRENCE:

Design Including Environ.

Component Failure.

Manufacture Installation /Const.

X Other (specify)

Improper final assembly of the Operator Procedure control rod drive unit at time _

of manufacture.

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The apparent cause of this occurrence is failure to fully eng ge the lock nut The locking action of _ the

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with the threaded portion of the support shaf t'.

lock nut requires full engage.ient so that this improper assembly allowed the lock nut to disengage from the shaft.

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O o UNUSUAL EVENT 75/17 Page 4 of 5 ANALYSIS OF OCCURRENCE: All of the bolted support parts (12, 42, 49, 41, and 15) (SLR-D1201-400) were No' abnormal indi-removed from the control rod drive and closely inspected. The orifice valve support shaf t and ac-cations of any kind could be found. tuator were removed from the control rod drive unit and carefully inspected, with considerable emphasis being given. to the threaded end of the stiaft to All threads looked normal; no signs of which the bolted support is attached. All of the parts were then reassembled distress or abnormality could be seen. This was done to determine that the physical mating of all parts was normal. Further, tihe self-satisfactorily and 'all parts fit properly and smoothly. (42) threaded down to its proper position and tightened snugly, locking nut This is nor-locked such that a wrench was required to remove it. was in fact mal and proper. The only conclusion which can be drawn in view of the observed facts is that the self-locking nut had never been tightened down properly during initial Because the nut was not properly tightened, vibrations assembly of the unit. and pulsing of the nearby orifice drive motor could have caused the nut to This threaded support is back off sufficiently to release the orifice valve. essentially unstressed during normal installation and operation of.the control rod drive which would allow the nut free movement if it were,not preperly tightened. CORRECTIVE ACTION: Seven spare control rod drives plus the 25 units still to be removed from the PCRV will be inspected to verify that the orifice valve support bolt is properly assembled, and that the retaining nut is tightened to the proper It is felt that this unusual event is an position on the mating threads.If any additional discrepancies are found, the additional isolated case. units, presently installed in the PCRV, will be removed for inspection. FAILURE DATA /SIMILAR REPORTED OCCURRENCES: None PROGRAMfATIC IMPACT: None ,0DE IMPACT: ?- l e, v

O O ~ ~ UNUSUAL EVENT 75/17 Page 5 of 5 kav C. # a _/'n-Submitted By: Harvey W. Hillyard, Jr/ Technical Services Supervisor l-Reviewed By: Frank M. Mathie Superintendent Maintenance f? e I Approved By: / pederic E. Swart Superintendent, Nuclear Production 9 e S e 0 a t e e B e l i D}}