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{{#Wiki_filter:... -* -** . *------CommoClth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 81 SJJ/ . s.:t u.-:llQ6..L BBS Ltr. 114 Mr. James Directorate of R Mail Soetit>ft Ood<ol tlcirlt U. S. Nuclear Regulate 799 Roosevelt Road Glen Ellyn, Illinois 60137 May 27, 1976 III Enclosed please find Reportable Occurrence number 50-249/1976-7.
{{#Wiki_filter:... -* -** . *---- --
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, 6. 6. B.  
CommoClth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 81 SJJ/~~~,....
... f v Station Superintendent
              .                 s.:t
* Dresden Nuclear Power Station BBS:smp Enclosure cc: Director of Inspection  
                      ~      u.-:llQ6..L BBS Ltr. 114                                         May 27, 1976 Mail Soetit>ft Ood<ol tlcirlt Mr. James Directorate of R                                        III U. S. Nuclear Regulate 799 Roosevelt Road Glen Ellyn, Illinois                     60137 Enclosed please find Reportable Occurrence number 50-249/1976-7.
& Enforcement Director of Management Information  
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Sec,~ion 6. 6. B.
& Program Control File/NRC 0 '* 5591 0 0 LICENSEE EVENT REPORT l. , .
                                                    ~&deg;mf<~
BLOCK:,. 1 I I I I I .LEASE PRINT ALL REQUIRED INFORMATION) 6 * . LICENSEE LICENSE . LICENSE NUMBER TYPE
                                                ~. ~. St~phenson          ...
* NAME @El l.LILIDIRISl31 lo IO I-lo lo lolo IO I-lo IOI 14 I / I I I ) I /I 7 B 9 14 15 25 26 30 CATEGORY @E]coN'T I I I REPORT REPORT TYPE SOURCE W' LbJ DOCKET NUMBER IO 7 B 57 5B 59 60 61 6B SYSTEM CAUSE CODE CODE COMPONENT CODE EVENT DATE 10 141 c:: 18 1"7 16'1 69 COMPONENT MANUFACTURER 74 VIOLAOON @0 IM IBI LW l:ZICf 19191 . LM 7 B 9 10 11 12 17 44 47 . 4B 75 EVENT TYPE 31 32 REPORT DATE I I I CAUSE pESCRIPTION I c.cu;Se Q f t\..e.. e..1'.P los l.OV) fS MJ' k YIOW\1
f v Station Superintendent
* bo we.  
* Dresden Nuclear Power Station 0
,, / J'S ) ' 7 B 9 I @&sect; I S w s A fhe>v+ ihe.
BBS:smp Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 0
* WAS: 7 B9 . r J J C...c..ust..A
                                                                      '*
\,, .. 1 t Y\ 1 *+<l..d . -1,,v g_ S/2a Y k ( C-o V\7\'1 v ) 7 B 9 ) > EEJ 7 B rn 7 B FACILITY STATUS L&#xa3;J 9 FORM OF % POWER IOISl71 10 12 13 ACTIVITY CONTENT OTHER STATUS )/)? RELEASED OF RELEASE AMOUNT OF ACTIVITY I 44 till L&J I c..a <-5 9 10 1 .... 1 _.;;;.......,;;;.......;;;;.....;:;;..
5591 0
__ __;_ __ _.44 PERSONNEL EXPOSURES NUMBER METHOD OF DISCOVERY 45 46 -45 , DISCOVERY DESCRIPTION A/J BO I BO I BO I BO BO BO EE] 1010101 7 8 9 11 TYPE DESCRIPTION N A PERSONNEL INJURIES NUMBER DESCRIPTION
: l. ,   .
[!EJIOIOIOI
LICENSEE EVENT REPORT C~TROL          BLOCK:,.                                 I I I I I                                                             .LEASE PRINT ALL REQUIRED INFORMATION) 1                                                6
___ 7 8 9 11 12 80 OFFSITE
  *           .         LICENSEE                                                                                                                                     LICENSE .             EVENT
[iliJ . t" ' ... 5 .E. p V fYOl?S 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE [2]] DESCRIPTION I -NA I 7 B 9 10 BO PUBLICITY . Em .1 &es s re lecyS e I 7 B 9 BO ADDITIONAL FACTORS I Pa >-LJ'c.s,,
* NAME                                                                LICENSE NUMBER                                                             TYPE                TYPE
ye le.a..")e I 7 B 9. BO NAME:_--..
  @El l.LILIDIRISl31                                         lo IO I-lo lo lolo IO I-lo IOI 14 I / I I I ) I /I                                                                           ~131 7   B 9                                       14           15                                                                                     25       26                   30     31    32 REPORT          REPORT CATEGORY             TYPE          SOURCE                                  DOCKET NUMBER                                                    EVENT DATE                      REPORT DATE
__ ....::C _  
  @E]coN'T       I I I W' LbJ IO                                                         1s101-101~14191                                            10 141 c:: 18 1"7 16'1                      I I I 7   B           57         5B           59           60                   61                                                             6B     69                          74    75                      BO SYSTEM           CAUSE                                                                                                                 COMPONENT CODE           CODE                     COMPONENT CODE                                                                             MANUFACTURER             VIOLAOON 7
....
@0 IM IBI B 9     10 LW 11 1*z1~IL:IZl~r21 12                                                 17 l:ZICf 19191 44                   47
_____ PHONE: 91-C:.-E.. 9 (;CJ GPO 881
                                                                                                                                                                          . LM
* 887
                                                                                                                                                                            . 4B CAUSE pESCRIPTION 7
---------------**-**--*-* _,,: ... w,. ' * "'-* EVENT DESCRIPTION (continued) and reactor power was reduced to clear the alarms. After the alarms had cleared, power was slowly increased until 0450 hours, when an apparent off-gas explosion occurred.
~ I J~e, B 9 c.cu;Se               Q       f           t\..e..       e..1'.P I
Reactor power was further reduced to approximately 360 MWe. Standby steam jet air ejector (SJAE) "3A''was placed in service..
los l.OV) fS                               MJ'     k YIOW\1     *
However, further inv,estigation indicated that the rupture diaphr_agm in both SJAE' s had been damaged, and a unit shutdown was initiated and completed by 1038 hours. Off-gas system explosions have occurred previously on both units 2 and 3. Corrective action implemented was replacement .of the failed diaphragms . and the "3B" off-gas filter. (050-249/76-7) . -CAUSE DESCRIPTION (continued)
                                                                                                                                                                        )
The explosion apparently failed both SJAE diaphragms at the same time. **It "i:s** assumed that the pressure wave failed the rupture diaphragms in both the operating SJAE "3B" and the standby SJAE "3A" due to leakage through the discharge valve. Although personnel on shift at_ the time reported hearing two explosions, no evidence could be found to support this theory. The "3B" off-gas filter in service at the time of the explosion was damaged and subsequently replaced.
bo we. ve...~.' ,,/       J'S BO I
Prior to the unit startup, both filters were tested and off-gas system valve lineups were verified to be correct. An investigation of this and other previous off-gas explosions has been initiated.*
7
The investigation will address the origin and prevention of off-gas system explosions.}}
@&sect; I S w s og'-<T~ A fhe>v+ ihe. hyJros~n
* WAS:
B9           .         r                                                               J         J t ~ Y\ 1*+<l..d       . -1,,v     g_ S/2a Y     k         BO I
~I            C...c..ust..A              \,, ..1 s=n:~'Jrc. e~le<!-Tv,*c..irv,                                                                              ( C-o V\7\'1 v ~J      )                             I 7   B 9                                       )                                                                                       >                                                                       BO FACILITY                                                                                                           METHOD OF STATUS                  % POWER                                          OTHER STATUS                             DISCOVERY                              DISCOVERY DESCRIPTION EEJ          L&#xa3;J                   IOISl71                                                )/)?                            I ~                                              A/J 7    B        9                   10                   12 13                                                           44                45      46                                                            BO FORM OF ACTIVITY           CONTENT 7
rn  B RELEASED till 9
OF RELEASE L&J 10        1I....
AMOUNT OF ACTIVITY c..a <-5_ _~,.
1 _.;;;.......,;;;.......;;;;.....;:;;..       __;__ __.44
                                                                                                                                          - 45            ,                                                    BO PERSONNEL EXPOSURES NUMBER                 TYPE          DESCRIPTION EE] 1010101 l~I 1~~~~~~~~~---'---'-'~~~~~~~~~~~~-.-~~~-e~J NA 7 8 9                     11 PERSONNEL INJURIES NUMBER                 DESCRIPTION
[!EJIOIOIOI l--~~~~~~-U_A___~~~~~~~~~~~--
7   8 9                   11     12                                                                                                                                                                             80 OFFSITE ~~S~UEJNCES
[iliJ             . t"     ' ... ;~                    5 .E. p                                                                                                     V fYOl?S 7   8 9 LOSS OR DAMAGE TO FACILITY TYPE         DESCRIPTION
[2]]   ~            I         -                                         NA                                                                                                                                       I 7   B 9         10                                                                                                                                                                                             BO PUBLICITY                       .
EmB .19 7
                          &es s                       re lecyS e                                                                                                                                               BO I
ADDITIONAL FACTORS
~ I                     Pa >-LJ'c.s,, /~Te.                                      ye le.a..")e                                                                                                                     I 7   B 9.                                                                                                                                                                                                       BO NAME:_--.._ _....::C                       _        _,~-.-....5.......,.cs......,y~~~Q...."-&#xa3;.'(\....;;.-...;../_ _ _ _ _              PHONE:     91-C:.- E.. 9   (;CJ GPO 881
* 887
 
                    ---- ---**- **--*-*
_,,: ...         w,.   ' * "'-*
EVENT DESCRIPTION (continued) and reactor power was reduced to clear the alarms. After the alarms had cleared, power was slowly increased until 0450 hours, when an apparent off-gas explosion occurred. Reactor power was further reduced to approximately 360 MWe. Standby steam jet air ejector (SJAE)
              "3A''was placed in service.. However, further inv,estigation indicated that the rupture diaphr_agm in both SJAE' s had been damaged, and a unit shutdown was initiated and completed by 1038 hours. Off-gas system explosions have occurred previously on both units 2 and 3.
Corrective action implemented was replacement .of the failed diaphragms
            . and the "3B" off-gas filter. (050-249/76-7)
        . -CAUSE DESCRIPTION (continued)
The explosion apparently failed both SJAE diaphragms at the same time.
            **It "i:s** assumed that the pressure wave failed the rupture diaphragms in both the operating SJAE "3B" and the standby SJAE "3A" due to leakage through the discharge valve. Although personnel on shift at_ the time reported hearing two explosions, no evidence could be found to support this theory. The "3B" off-gas filter in service at the time of the explosion was damaged and subsequently replaced. Prior to the unit startup, both filters were tested and off-gas system valve lineups were verified to be correct.
An investigation of this and other previous off-gas explosions has been initiated.* The investigation will address the origin and prevention of off-gas system explosions.}}

Revision as of 19:32, 29 October 2019

Transmittal of Reportable Occurrence No. 50-249/1976-7
ML17252A199
Person / Time
Site: Dresden  
Issue date: 05/27/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #412-76 50-249/1976-7
Download: ML17252A199 (3)
v • d • e


Text

... -* -** . *---- --

CommoClth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 81 SJJ/~~~,....

. s.:t

~ u.-:llQ6..L BBS Ltr. 114 May 27, 1976 Mail Soetit>ft Ood<ol tlcirlt Mr. James Directorate of R III U. S. Nuclear Regulate 799 Roosevelt Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence number 50-249/1976-7.

This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Sec,~ion 6. 6. B.

~°mf<~

~. ~. St~phenson ...

f v Station Superintendent

  • Dresden Nuclear Power Station 0

BBS:smp Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 0

'*

5591 0

l. , .

LICENSEE EVENT REPORT C~TROL BLOCK:,. I I I I I .LEASE PRINT ALL REQUIRED INFORMATION) 1 6

  • . LICENSEE LICENSE . EVENT
  • NAME LICENSE NUMBER TYPE TYPE

@El l.LILIDIRISl31 lo IO I-lo lo lolo IO I-lo IOI 14 I / I I I ) I /I ~131 7 B 9 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

@E]coN'T I I I W' LbJ IO 1s101-101~14191 10 141 c:: 18 1"7 16'1 I I I 7 B 57 5B 59 60 61 6B 69 74 75 BO SYSTEM CAUSE COMPONENT CODE CODE COMPONENT CODE MANUFACTURER VIOLAOON 7

@0 IM IBI B 9 10 LW 11 1*z1~IL:IZl~r21 12 17 l:ZICf 19191 44 47

. LM

. 4B CAUSE pESCRIPTION 7

~ I J~e, B 9 c.cu;Se Q f t\..e.. e..1'.P I

los l.OV) fS MJ' k YIOW\1 *

)

bo we. ve...~.' ,,/ J'S BO I

7

@§ I S w s og'-<T~ A fhe>v+ ihe. hyJros~n

  • WAS:

B9 . r J J t ~ Y\ 1*+<l..d . -1,,v g_ S/2a Y k BO I

~I C...c..ust..A \,, ..1 s=n:~'Jrc. e~le<!-Tv,*c..irv, ( C-o V\7\'1 v ~J ) I 7 B 9 ) > BO FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEJ L£J IOISl71 )/)? I ~ A/J 7 B 9 10 12 13 44 45 46 BO FORM OF ACTIVITY CONTENT 7

rn B RELEASED till 9

OF RELEASE L&J 10 1I....

AMOUNT OF ACTIVITY c..a <-5_ _~,.

1 _.;;;.......,;;;.......;;;;.....;:;;.. __;__ __.44

- 45 , BO PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION EE] 1010101 l~I 1~~~~~~~~~---'---'-'~~~~~~~~~~~~-.-~~~-e~J NA 7 8 9 11 PERSONNEL INJURIES NUMBER DESCRIPTION

[!EJIOIOIOI l--~~~~~~-U_A___~~~~~~~~~~~--

7 8 9 11 12 80 OFFSITE ~~S~UEJNCES

[iliJ . t" ' ... ;~ 5 .E. p V fYOl?S 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

[2]] ~ I - NA I 7 B 9 10 BO PUBLICITY .

EmB .19 7

&es s re lecyS e BO I

ADDITIONAL FACTORS

~ I Pa >-LJ'c.s,, /~Te. ye le.a..")e I 7 B 9. BO NAME:_--.._ _....::C _ _,~-.-....5.......,.cs......,y~~~Q...."-£.'(\....;;.-...;../_ _ _ _ _ PHONE: 91-C:.- E.. 9 (;CJ GPO 881

  • 887

---**- **--*-*

_,,: ... w,. ' * "'-*

EVENT DESCRIPTION (continued) and reactor power was reduced to clear the alarms. After the alarms had cleared, power was slowly increased until 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />, when an apparent off-gas explosion occurred. Reactor power was further reduced to approximately 360 MWe. Standby steam jet air ejector (SJAE)

"3Awas placed in service.. However, further inv,estigation indicated that the rupture diaphr_agm in both SJAE' s had been damaged, and a unit shutdown was initiated and completed by 1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br />. Off-gas system explosions have occurred previously on both units 2 and 3.

Corrective action implemented was replacement .of the failed diaphragms

. and the "3B" off-gas filter. (050-249/76-7)

. -CAUSE DESCRIPTION (continued)

The explosion apparently failed both SJAE diaphragms at the same time.

    • It "i:s** assumed that the pressure wave failed the rupture diaphragms in both the operating SJAE "3B" and the standby SJAE "3A" due to leakage through the discharge valve. Although personnel on shift at_ the time reported hearing two explosions, no evidence could be found to support this theory. The "3B" off-gas filter in service at the time of the explosion was damaged and subsequently replaced. Prior to the unit startup, both filters were tested and off-gas system valve lineups were verified to be correct.

An investigation of this and other previous off-gas explosions has been initiated.* The investigation will address the origin and prevention of off-gas system explosions.

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