ML19351D634: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:-
{{#Wiki_filter:-
                                                          -.
                                                                                                                  ,
    '
.      PART 21 IIB 1TIFICATION NO, to-t%-coo                            C0iPANY INE_ con 1AM              5--
.      PART 21 IIB 1TIFICATION NO, to-t%-coo                            C0iPANY INE_ con 1AM              5--
IAIO: ETTER.        n\tedso                DIKET l0,        Bo- 3%
IAIO: ETTER.        n\tedso                DIKET l0,        Bo- 3%
                                                                                                                   ;
                                                                                                                   ;
  -
DATE. DISTRIBUTED alvelto        n.m .
DATE. DISTRIBUTED alvelto        n.m .
                                                "
ORIGIRAL REPORT      1      SU?PElENTARY DISTRIBUTION:
ORIGIRAL REPORT      1      SU?PElENTARY DISTRIBUTION:
REACTOR (R)  %                    FEL CYCE &                        SACEGlARDS (S)
REACTOR (R)  %                    FEL CYCE &                        SACEGlARDS (S)
Line 32: Line 27:
AD/RCI          ,
AD/RCI          ,
AD/ FREI                          AD/ROI EGIGG 1,II,lll,IV,V                REGIONS I,II,III,IV,V            REGIGG I,II,III,lV,V VSO3R BR, R-IV                      Vs00R BR, R-IV                    VB03RBR,RIV LEB / FPA FIG 5715                  ffES/FGS        SS-395          NPND7u AEOD        I4B 7602                LDEB/FPA        FIB 5715          g,ES / SG SS-881 NRR/IE                            AEOD            FIG 7602          LDEB/FPA          F16 5735 NPNDSI                            ASBP. EAl ' 450                    AEOD              FIG 7602 T                '
AD/ FREI                          AD/ROI EGIGG 1,II,lll,IV,V                REGIONS I,II,III,IV,V            REGIGG I,II,III,lV,V VSO3R BR, R-IV                      Vs00R BR, R-IV                    VB03RBR,RIV LEB / FPA FIG 5715                  ffES/FGS        SS-395          NPND7u AEOD        I4B 7602                LDEB/FPA        FIB 5715          g,ES / SG SS-881 NRR/IE                            AEOD            FIG 7602          LDEB/FPA          F16 5735 NPNDSI                            ASBP. EAl ' 450                    AEOD              FIG 7602 T                '
SAP /SP FIG-7210A                  ASLBP        E/W 450
SAP /SP FIG-7210A                  ASLBP        E/W 450 NRR/ DOL CENTPALFILES          016        CENTRALFILES          016 ASLBP      E/W 450                                                    CBERAL FIES CBRPAL FIES ( GRON)                                  (GRON)
                            -
CBERAL FIES        016                PDR                              CBiTRAL FILES        SS-395 CENTRAL FIES      (GR0fD                LPDR                            PDR PDR                                  L TERA                            [PDR
NRR/ DOL CENTPALFILES          016        CENTRALFILES          016 ASLBP      E/W 450                                                    CBERAL FIES CBRPAL FIES ( GRON)                                  (GRON)
CBERAL FIES        016                PDR                              CBiTRAL FILES        SS-395 CENTRAL FIES      (GR0fD                LPDR                            PDR
                                  '                          '
PDR                                  L TERA                            [PDR
[PDR                                                                    TERA xRA
[PDR                                                                    TERA xRA
                                  '
       ~ACT10th PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ItOICATES LEAD RESPONSIBILITY FOR FOLLOWJP AS SFOhN BELOW:
                                                                                              '
       ~ACT10th PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ItOICATES LEAD RESPONSIBILITY FOR
                                                                ,
FOLLOWJP AS SFOhN BELOW:
IE
IE
         .    [                      .
         .    [                      .
Line 50: Line 37:
OTHS1  _
OTHS1  _
     @SG                                                                                                ..          ,
     @SG                                                                                                ..          ,
FFMSI                                                                                          Pa', 8/1/80    l
FFMSI                                                                                          Pa', 8/1/80    l 8010 3 4 p3'(5            .          .  .
                                                                              ,
                                                                                                          ***
8010 3 4 p3'(5            .          .  .
s          .        .          .
s          .        .          .
                                                                                                .
                                                                                                                    ,


l
l
  ;
  ;
         ,    REGISTERED      7782
         ,    REGISTERED      7782
'
       -                                                                  bec:  C.A. Ankrum            i RETURN RECEIPT REQUESTED J.'Balderston          j l          Original &~3 Copies
       -                                                                  bec:  C.A. Ankrum            i RETURN RECEIPT REQUESTED J.'Balderston          j l          Original &~3 Copies
* 6                l                                                      .f.F                  !
* 6                l                                                      .f.F                  !
:                                                                          E.D. Greene          ,
:                                                                          E.D. Greene          ,
September 22, 1980
September 22, 1980 hggHa ey t                                                                              G. Olson J.W. Tangye l            Office of Inspection & Enforcement                                R. Koons, BPSI
,
!'          U.S. Nuclear Regulatory Comission 799 Roosevelt Road Glen Ellyn, Ill. 60137 Attention:      Mr. James G. Keppler, Director, Region III l             
hggHa ey t                                                                              G. Olson
.
J.W. Tangye l            Office of Inspection & Enforcement                                R. Koons, BPSI
!'          U.S. Nuclear Regulatory Comission
'
799 Roosevelt Road Glen Ellyn, Ill. 60137 Attention:      Mr. James G. Keppler, Director, Region III l             


==Subject:==
==Subject:==
Colt Industries-Fairbanks Morse Engine Division
Colt Industries-Fairbanks Morse Engine Division Emergency Diesel Generators
.
Emergency Diesel Generators
!                            South Carolina Electric & Gas Co.-Sumer Station 5a-M6 Part 21 Report - Beloit Power Systems Generators 3 Possible Field Insulation Damage Gentlemen:
!                            South Carolina Electric & Gas Co.-Sumer Station 5a-M6 Part 21 Report - Beloit Power Systems Generators 3 Possible Field Insulation Damage Gentlemen:
!
  "
;
;
i This  is to confirm our verbal report (R.H. Beadle to D.W. Hayes) of September 19, 1980.
i This  is to confirm our verbal report (R.H. Beadle to D.W. Hayes) of September 19, 1980.
,
A Beloit Power Systems generator in commercial service at Sitka, Alaska lost its field because a lead between the collector rings and the field coils shorted to the rotor and burned in two pieces at the point of the short. Subsequent
A Beloit Power Systems generator in commercial service at Sitka, Alaska lost its field because a lead between the collector rings and the field coils shorted to
,
the rotor and burned in two pieces at the point of the short. Subsequent
{
{
examination of anoth.er generator of identical design at the same installation
examination of anoth.er generator of identical design at the same installation
:
  ;
  ;
showed frayed insulation at a clamp (same location as the burn through) which
showed frayed insulation at a clamp (same location as the burn through) which
Line 103: Line 70:
Our plan is to inspect the Limerick generators and repair any poor workmanship which may be found.
Our plan is to inspect the Limerick generators and repair any poor workmanship which may be found.
Beloit Power Systems a,lso reports verbally that the design in this area for 5 and 6 frame alternators has been similar for a number of years and it is therefore possible that the problem may extend to operating units.
Beloit Power Systems a,lso reports verbally that the design in this area for 5 and 6 frame alternators has been similar for a number of years and it is therefore possible that the problem may extend to operating units.
The list of Fairbanks Horse Model 38TDC-1/8 OP generator sets equipped with
The list of Fairbanks Horse Model 38TDC-1/8 OP generator sets equipped with 5 or 6 frame Beloit Power Systems generators is as follows; W-      .  ,l"3
,
,
5 or 6 frame Beloit Power Systems generators is as follows;
,
W-      .  ,l"3
_
                                                                                        .
                                                      .__                          _


_    _
                                                                                                       \
                                                                                                       \
l
l Office of Inspecticn & Enforcement                                          '
* Office of Inspecticn & Enforcement                                          '
       .U.S. Nuclear Regulatory Comission Glen Ellyn, Ill.                                              September 22, 1980
       .U.S. Nuclear Regulatory Comission Glen Ellyn, Ill.                                              September 22, 1980
                                                                                                    ,
'    '
: l. 1 Unit    -
: l. 1 Unit    -
2665 KW for Northeast Utilities, Millstone Nuclear Plant - Unit fl.
2665 KW for Northeast Utilities, Millstone Nuclear Plant - Unit fl.
Line 127: Line 82:
: 5. 2 Units - 3000 KW for Metropolitan Edison, Three Mile Island Nuclear Plant fl.
: 5. 2 Units - 3000 KW for Metropolitan Edison, Three Mile Island Nuclear Plant fl.
: 6. 4 Units - 3250 KW for Philadelphia Electric Co., Peachbottom Nuclear Station
: 6. 4 Units - 3250 KW for Philadelphia Electric Co., Peachbottom Nuclear Station
,
                               #2 & f3.
                               #2 & f3.
: 7. 3 Units - 3250 KW for Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Stations #1 and #2.
: 7. 3 Units - 3250 KW for Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Stations #1 and #2.
Line 144: Line 98:
: 18. 8 Units - 3250 KW for Philadelphia Electric Company, Limericak Nuclear Station il & #2.
: 18. 8 Units - 3250 KW for Philadelphia Electric Company, Limericak Nuclear Station il & #2.
It is suggested that'the generator field leads be inspected for insulation dama0e at the clamps attaching these leads to the generator rotor.
It is suggested that'the generator field leads be inspected for insulation dama0e at the clamps attaching these leads to the generator rotor.
A conference call with NRC duty officer, Personnel from Prairie Island Nuclear
A conference call with NRC duty officer, Personnel from Prairie Island Nuclear Plant R.H. Beadle, and C. Evenson of Beloit Power Systems was arranged for 9:30 AM 9/20/80 so that the method of inspection could be explained and taped for use by the NRC in explaining the inspection required to other sites. Mr. Evenscn was the spokesman and described the method of inspection to visually check for insulation distress at clamps and for clearance between generator field leads and the generator fan.
"
Plant R.H. Beadle, and C. Evenson of Beloit Power Systems was arranged for 9:30 AM 9/20/80 so that the method of inspection could be explained and taped for use by the NRC in explaining the inspection required to other sites. Mr. Evenscn was the spokesman and described the method of inspection to visually check for insulation distress at clamps and for clearance between generator field leads and the generator fan.
Edited written instructions covering the inspection method have been requested of Beloit Power Systems. We will contact NRC upon receipt to discuss method of distribution.
Edited written instructions covering the inspection method have been requested of Beloit Power Systems. We will contact NRC upon receipt to discuss method of distribution.
Very truly yours,
Very truly yours,
                                                                  -%
                        ,
                             ,                          .H. Moriarty MAtlAGER UTILITY SA ES JMM/jl      -
                             ,                          .H. Moriarty MAtlAGER UTILITY SA ES JMM/jl      -
cc:    U.S. Nuclear Regulatory Comission                              ~
cc:    U.S. Nuclear Regulatory Comission                              ~

Revision as of 22:56, 30 January 2020

Part 21 Rept Re Beloit Power Sys Generator Losing Field. Caused by Lead Between Collector Rings & Field Coils Shorting to Rotor & Burning in Two Pieces at Point of Short. Insp of Another Generator Showed Frayed Insulation
ML19351D634
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 09/22/1980
From: Moriarty J
COLT INDUSTRIES, INC.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-PT21-80-286-000 NUDOCS 8010140343
Download: ML19351D634 (2)


Text

-

. PART 21 IIB 1TIFICATION NO, to-t%-coo C0iPANY INE_ con 1AM 5--

IAIO: ETTER. n\tedso DIKET l0, Bo- 3%

DATE. DISTRIBUTED alvelto n.m .

ORIGIRAL REPORT 1 SU?PElENTARY DISTRIBUTION:

REACTOR (R)  % FEL CYCE & SACEGlARDS (S)

'lE FIES [RTERIALS (tD IEFILES IEFILES AD/RDI AD/SG '.

AD/RCI ,

AD/ FREI AD/ROI EGIGG 1,II,lll,IV,V REGIONS I,II,III,IV,V REGIGG I,II,III,lV,V VSO3R BR, R-IV Vs00R BR, R-IV VB03RBR,RIV LEB / FPA FIG 5715 ffES/FGS SS-395 NPND7u AEOD I4B 7602 LDEB/FPA FIB 5715 g,ES / SG SS-881 NRR/IE AEOD FIG 7602 LDEB/FPA F16 5735 NPNDSI ASBP. EAl ' 450 AEOD FIG 7602 T '

SAP /SP FIG-7210A ASLBP E/W 450 NRR/ DOL CENTPALFILES 016 CENTRALFILES 016 ASLBP E/W 450 CBERAL FIES CBRPAL FIES ( GRON) (GRON)

CBERAL FIES 016 PDR CBiTRAL FILES SS-395 CENTRAL FIES (GR0fD LPDR PDR PDR L TERA [PDR

[PDR TERA xRA

~ACT10th PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ItOICATES LEAD RESPONSIBILITY FOR FOLLOWJP AS SFOhN BELOW:

IE

. [ .

NPR [ rpSS2

~

OTHS1 _

@SG .. ,

FFMSI Pa', 8/1/80 l 8010 3 4 p3'(5 . . .

s . . .

l

, REGISTERED 7782

- bec: C.A. Ankrum i RETURN RECEIPT REQUESTED J.'Balderston j l Original &~3 Copies

  • 6 l .f.F  !
E.D. Greene ,

September 22, 1980 hggHa ey t G. Olson J.W. Tangye l Office of Inspection & Enforcement R. Koons, BPSI

!' U.S. Nuclear Regulatory Comission 799 Roosevelt Road Glen Ellyn, Ill. 60137 Attention: Mr. James G. Keppler, Director, Region III l

Subject:

Colt Industries-Fairbanks Morse Engine Division Emergency Diesel Generators

! South Carolina Electric & Gas Co.-Sumer Station 5a-M6 Part 21 Report - Beloit Power Systems Generators 3 Possible Field Insulation Damage Gentlemen:

i This is to confirm our verbal report (R.H. Beadle to D.W. Hayes) of September 19, 1980.

A Beloit Power Systems generator in commercial service at Sitka, Alaska lost its field because a lead between the collector rings and the field coils shorted to the rotor and burned in two pieces at the point of the short. Subsequent

{

examination of anoth.er generator of identical design at the same installation

showed frayed insulation at a clamp (same location as the burn through) which

secures the lead to the rotor.- This unit was operating satisfactorily but if the insulation damage were to progress the possibility of grounding the lead to ,

the rotor exists. ,

To detennine if the problem might exist at other locations our chief electrical engineer was sent to Provo, Utah which has four generators of identical design.

.He has reported by phone that two of the four at Provo have frayed insulation

-at the clamp but that there was no indication of loss of field.

Concurrent with our inspection at Provo, Beloit Power Systems was asked to evaluate the cause of frayed insulation and also if any other generators might have the same problem. Their verbal report to us is that the cause of fraying is poor workmanship in installation of the clamps and that there.are other generators of identical design in this area. Specifically the eight generators shipped

~

to Limerick where poor wo(Philadelphia Electric) are of the identical design in the area rkmanship is known to have caused a problem.

Our plan is to inspect the Limerick generators and repair any poor workmanship which may be found.

Beloit Power Systems a,lso reports verbally that the design in this area for 5 and 6 frame alternators has been similar for a number of years and it is therefore possible that the problem may extend to operating units.

The list of Fairbanks Horse Model 38TDC-1/8 OP generator sets equipped with 5 or 6 frame Beloit Power Systems generators is as follows; W- . ,l"3

\

l Office of Inspecticn & Enforcement '

.U.S. Nuclear Regulatory Comission Glen Ellyn, Ill. September 22, 1980

l. 1 Unit -

2665 KW for Northeast Utilities, Millstone Nuclear Plant - Unit fl.

2. 2 Units - 2500 KW for Carolina Power & Light, Robinson Nuclear Plant.
3. 2 Units - 3000 KW for florthern States Power, Prairie Island Nuclear Plant.
4. 2 Units - 3000 KW for Vermont Yankee Corp., Vermont Yankee 'Juclear Plant.
5. 2 Units - 3000 KW for Metropolitan Edison, Three Mile Island Nuclear Plant fl.
6. 4 Units - 3250 KW for Philadelphia Electric Co., Peachbottom Nuclear Station
  1. 2 & f3.
7. 3 Units - 3250 KW for Baltimore Gas & Electric Company, Calvert Cliffs Nuclear Stations #1 and #2.
8. 2 Units - 3000 KW for Florida Power Corporation, Crystal River No. 3
9. 2 Units - 3000 KW for Jersey Central Power and Light Company Three Mile Island Nuclear Station No. 2
10. 3 Units - 3250 KW for Georgia Power Company, Hatch Nuclear Fiant fl.

11, 2 Units - 3250 KW for Iowa Electric Light & Power Co., Duane Arnold Nuclear Plant.

12, 4 Units - 3000 KW for Virginia Electric & Power Co., North Anna Nuclear Plant #1 & f2.

13. 2 Units - 3250 KW for Northeast Utilities, Millstone Nuclear Plant - Unit f2.

~

14. 2 Units - 3250 KW for Alabama Power Company, Farley Nuclear Plant Units il & #2.

15 2 Units - 3250 KW for Arkansas Power & Light Company, Arkansas Nuclear One -

Unit f2.

16. 2 Units - 3250 KW for Georgia Power Company, Hatch Nuclear Plant f2 (with option for additional unit).
17. 4 Units - 3250. KW for Detroit Edison Company, Enrico -Femi #2.
18. 8 Units - 3250 KW for Philadelphia Electric Company, Limericak Nuclear Station il & #2.

It is suggested that'the generator field leads be inspected for insulation dama0e at the clamps attaching these leads to the generator rotor.

A conference call with NRC duty officer, Personnel from Prairie Island Nuclear Plant R.H. Beadle, and C. Evenson of Beloit Power Systems was arranged for 9:30 AM 9/20/80 so that the method of inspection could be explained and taped for use by the NRC in explaining the inspection required to other sites. Mr. Evenscn was the spokesman and described the method of inspection to visually check for insulation distress at clamps and for clearance between generator field leads and the generator fan.

Edited written instructions covering the inspection method have been requested of Beloit Power Systems. We will contact NRC upon receipt to discuss method of distribution.

Very truly yours,

, .H. Moriarty MAtlAGER UTILITY SA ES JMM/jl -

cc: U.S. Nuclear Regulatory Comission ~

c/o Document Management Branch Washington, D.C. 20555

, y-

.