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{{#Wiki_filter:... -* -** . *---- --
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CommoClth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 81 SJJ/~~~,....
CommoClth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 81 SJJ/ ~~~,....
              .                  s.:t
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                      ~       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.
~ 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.
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Sec,~ion 6. 6. B.
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Sec,~ion 6. 6. B.  
                                                    ~&deg;mf<~
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* Dresden Nuclear Power Station 0
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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)
EVENT DESCRIPTION (continued) and reactor power was reduced to clear the alarms.
              "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.
After the alarms had cleared, power was slowly increased until 0450 hours, when an apparent off-gas explosion occurred.
Corrective action implemented was replacement .of the failed diaphragms
Reactor power was further reduced to approximately 360 MWe.
            . and the "3B" off-gas filter. (050-249/76-7)
Standby steam jet air ejector (SJAE)  
        . -CAUSE DESCRIPTION (continued)
"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.
The explosion apparently failed both SJAE diaphragms at the same time.
Off-gas system explosions have occurred previously on both units 2 and 3.
            **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.
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.}}
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.}}

Latest revision as of 11:37, 8 January 2025

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 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.

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 BBS:smp Enclosure cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 0

5591 0

0

LICENSEE EVENT REPORT

l.,

C~TROL BLOCK:,.

1 I I I I I

.LEASE PRINT ALL REQUIRED INFORMATION) 6 LICENSEE LICENSE.

LICENSE NUMBER TYPE 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 1s101-101~14191 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 1*z1~IL:IZl~r21 l:ZICf 19191

. LM 7

B 9 10 11 12 17 44 47

. 4B 75 EVENT TYPE

~131 31 32 REPORT DATE I I I CAUSE pESCRIPTION

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8 9 11 TYPE DESCRIPTION N A l~I 1~~~~~~~~~---'---'-'~~~~~~~~~~~~-.-~~~-e~J PERSONNEL INJURIES NUMBER DESCRIPTION

[!EJIOIOIOI l--~~~~~~-U_A

___ ~~~~~~~~~~~--

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

[iliJ

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NA I

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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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