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{{#Wiki_filter:8' Commonw.A. | {{#Wiki_filter:8' Commonw.A. Edison Dresden Nucle~~er Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #77-239 March 23, 1977 Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region I I I U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 (nclosed please find Reportable. Occurrence report number 50-249/1977-4. | ||
Edison Dresden Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #77-239 March 23, 1977 Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations | This repo{t is being sub~itted to your office in a~cordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B. | ||
-Region I I I U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 (nclosed please find Reportable. | BBS: j o Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Cohtrol Fi le/NRC MAR 2 5 1977 | ||
Occurrence report number 50-249/1977-4. | |||
This repo{t is being to your office in with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B. BBS: j o Enclosure cc: Director of Inspection | LICENSEE EVENT REPORT CONtROL BLOCK: | ||
& Enforcement Director of Management Information | l 1 | ||
& Program Cohtrol Fi le/NRC MAR 2 5 1977 LICENSEE EVENT REPORT CONtROL BLOCK: l | eI I I . I 6I.** L s E PRINT AU REQUIRED 1NFORMA.T10NJ LICENSEE UC EN SE EVENT NAME LICENSE NUMBER TYPE TYPE | ||
CATEGORY TYPE. SOURCE @mcoN'T I I . L!:J lJ:J | ~l1 ILlolRlsl3I I oI o1-1 oI oI oI oI ol -1 o I o I l 4 I I I1 I 1 I1 I Io I 3 I 7 8 9 14 15 25 26 30 31 ~2 | ||
* * -* | . REPORT~---REPORT CATEGORY TYPE. SOURCE OOCKET NUMBER . EVENT OA TE . REPORT DATE | ||
@mcoN'T I I . L!:J lJ:J I oI s I oI _:_ I o 1- 2 I 4 l 9 I I oI 21 21 11 71 '71 1013121317171 7 .8 57. 58 '. _59 60 61 68 69 74 75 80* | |||
EVENT DESCRIPTION * * -* | |||
fol2l ~1--.,--D_u_r_in~g,._r_o_u_t_i_n_e__s_u_r_v_e_i~l_l_a_n_c_e__ te_s_t-'-in~g~,:..-.;.m_a_i_n__s_t_e_a_m_l_t_i_n_e__h~ig~h--f_l_o_w__i_s_o_l_a_t_i_o_n__ s_w_i_t_c_h____ __JI 7 . 8 9 80 lol3I '~--.-3-_2_6__1-~2_B__w_a_s__f_o_u_n_d__t_o_...t_r_i~p_a_t__1_1~7~*~5'-"p_s_i~.--i_n_c_r~e_a_s_i_ng.._~(T_e~c-h__S~p-e_c__l~i-m_i_t_:__**_1_1*~5_.~9_p~s--*i______JI 7 *8 9 80 9 | |||
i~l4J ~'~---~i~n=c~re=a~s-.....in~9-*-..w~h~i~c~h-....c~o~r~r~e=s~b=o~n=d=s._....to......_1~2~0~%..._.f~l~o~w~)~.--~R-e=d=u~n=da~n=t-.s~.~~~.~it.c~h~e~s;.....;:o_n;.....;:t_h~e-=-s~t~e~a~m--------.JJ 8l 10151,J I ine would have provided the required isolation had.an _anGal high-flow con-:- | |||
7* .8 9~-------------.,..------------------------------------------..-..;.--------,_;;;._-------------------9-10 (Q]§J . ~I___. _d_i_t_io_n__o_c_c_u_r_r_e_d_.___T_h_i_s__i._s__n_o_t_a_...r_e~p_e_t_i_t_i_v_e__o_c_c_u_r_r_e_n_ce__* ___(5~0_-_2_4_9_/_1_9_7_7_-_4_)_.-------------11 7 8 9 PRIME . 80 SYSTEM COMPONENT COMPONENT CODE' SUPPLIER MANUFACTURER \/10LATl)N | |||
@£] 1*c1 ol w43 44 I BI 0 I8I0I 47 I tY1 I 48 FACILITY METHOD OF STATUS " POWER OTHER STATUS DISCOVERY fill] Ll.J IQ I 4 I 3 I ~8 I ~ I NA 7 .8 9 10 12 13 44 45 46 80 FORM OF' ACTIVITY* CONTENT | |||
*rn RELEASED OF RELEASE AMOUNT OF ACTIVITY | |||
__ | * LOCATION OF RELEASE 7 | ||
LzJ 9 | |||
W10 | |||
. 11I ~8. I, . . | |||
44".,,: | |||
~--~NA 45 | |||
.....-*_ _,_...___________ ___,I . | |||
80 w. | |||
8 PERSONNEL EXPOSURES | |||
* NUMBER TYPE OESCRIPTION | |||
~ I ol ol ol L1J N 7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER OESCRIPTION ITEJ8 9*lol ol ol* ~-~~~N~A~~~~~~~~~~~~----~----'-----_..;...~~---~~ | |||
7 11 12 BO OFFSITE. CONSEQUENCES . | |||
* ___ | EE8 9 7 | ||
-------------11 7 8 9 PRIME . 80 SYSTEM CODE' @£] 1*c1 ol FACILITY STATUS fill] Ll.J 7 .8 9 FORM OF' ACTIVITY* | NA ao LOSS OR DAMAGE ..TO FACILITY | ||
*rn RELEASED | . TYPE OESCRIPTION . | ||
* | (Ifilll.J .,_____N_A___________________________________,___________...__....____~ | ||
7 8 9 10 80 PUBLICITY | |||
..... -* _ _,_... ___________ | . 7EfZlB 9"-------.:.:.:..:--.-...;. | ||
___,I . | *-NA _____________________________,..__________________________________ ~----~B~O ADDITIONAL FACTORS | ||
., | ~ | ||
~*. | |||
...__.... | NA 7 8 9 80 | ||
.. ~.E; __--____G;;..*;._;L;;..;.__;_B.;.;;;o.;.;.;rn~b~a--_______________ PHONE: _ _E_x_t_._42 ........ | |||
: 1. - - | |||
GPO 811t*eG7 | |||
ADDITIONAL FACTORS NA 7 8 9 80 .. | |||
__ -- | CAUSE DESCRIPTION (Continued) | ||
_______________ | It is believed that the water originated from a leaking area cooler (Which has since been repaired) located above the jun~tion box. | ||
PHONE: | The switch was cleaned and reset to trip at the correct setpoint. In addition, the cable penetr(~t~,Q~ri:from the junction box was sealed. Examina-tion of the hearby switches indicated that water in~leakage was limited to this particu~ar switch. DPIS 3-261-26 is a Barton model 278 unit with a range of 0 - 200 psig.}} | ||
........ 1. --GPO 811t*eG7 CAUSE DESCRIPTION (Continued) | |||
It is believed that the water originated from a leaking area cooler (Which has since been repaired) located above the box. The switch was cleaned and reset to trip at the correct setpoint. | |||
In addition, the cable the junction box was sealed. tion of the hearby switches indicated that water was limited to this switch. DPIS 3-261-26 is a Barton model 278 unit with a range of 0 -200 psig.}} |
Latest revision as of 12:17, 4 February 2020
ML17252A275 | |
Person / Time | |
---|---|
Site: | Dresden |
Issue date: | 03/23/1977 |
From: | Stephenson B Commonwealth Edison Co |
To: | James Keppler NRC/RGN-III |
References | |
50-249/1977-4 | |
Download: ML17252A275 (3) | |
Text
8' Commonw.A. Edison Dresden Nucle~~er Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #77-239 March 23, 1977 Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region I I I U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 (nclosed please find Reportable. Occurrence report number 50-249/1977-4.
This repo{t is being sub~itted to your office in a~cordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.
BBS: j o Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Cohtrol Fi le/NRC MAR 2 5 1977
LICENSEE EVENT REPORT CONtROL BLOCK:
l 1
eI I I . I 6I.** L s E PRINT AU REQUIRED 1NFORMA.T10NJ LICENSEE UC EN SE EVENT NAME LICENSE NUMBER TYPE TYPE
~l1 ILlolRlsl3I I oI o1-1 oI oI oI oI ol -1 o I o I l 4 I I I1 I 1 I1 I Io I 3 I 7 8 9 14 15 25 26 30 31 ~2
. REPORT~---REPORT CATEGORY TYPE. SOURCE OOCKET NUMBER . EVENT OA TE . REPORT DATE
@mcoN'T I I . L!:J lJ:J I oI s I oI _:_ I o 1- 2 I 4 l 9 I I oI 21 21 11 71 '71 1013121317171 7 .8 57. 58 '. _59 60 61 68 69 74 75 80*
EVENT DESCRIPTION * * -*
fol2l ~1--.,--D_u_r_in~g,._r_o_u_t_i_n_e__s_u_r_v_e_i~l_l_a_n_c_e__ te_s_t-'-in~g~,:..-.;.m_a_i_n__s_t_e_a_m_l_t_i_n_e__h~ig~h--f_l_o_w__i_s_o_l_a_t_i_o_n__ s_w_i_t_c_h____ __JI 7 . 8 9 80 lol3I '~--.-3-_2_6__1-~2_B__w_a_s__f_o_u_n_d__t_o_...t_r_i~p_a_t__1_1~7~*~5'-"p_s_i~.--i_n_c_r~e_a_s_i_ng.._~(T_e~c-h__S~p-e_c__l~i-m_i_t_:__**_1_1*~5_.~9_p~s--*i______JI 7 *8 9 80 9
i~l4J ~'~---~i~n=c~re=a~s-.....in~9-*-..w~h~i~c~h-....c~o~r~r~e=s~b=o~n=d=s._....to......_1~2~0~%..._.f~l~o~w~)~.--~R-e=d=u~n=da~n=t-.s~.~~~.~it.c~h~e~s;.....;:o_n;.....;:t_h~e-=-s~t~e~a~m--------.JJ 8l 10151,J I ine would have provided the required isolation had.an _anGal high-flow con-:-
7* .8 9~-------------.,..------------------------------------------..-..;.--------,_;;;._-------------------9-10 (Q]§J . ~I___. _d_i_t_io_n__o_c_c_u_r_r_e_d_.___T_h_i_s__i._s__n_o_t_a_...r_e~p_e_t_i_t_i_v_e__o_c_c_u_r_r_e_n_ce__* ___(5~0_-_2_4_9_/_1_9_7_7_-_4_)_.-------------11 7 8 9 PRIME . 80 SYSTEM COMPONENT COMPONENT CODE' SUPPLIER MANUFACTURER \/10LATl)N
@£] 1*c1 ol w43 44 I BI 0 I8I0I 47 I tY1 I 48 FACILITY METHOD OF STATUS " POWER OTHER STATUS DISCOVERY fill] Ll.J IQ I 4 I 3 I ~8 I ~ I NA 7 .8 9 10 12 13 44 45 46 80 FORM OF' ACTIVITY* CONTENT
- rn RELEASED OF RELEASE AMOUNT OF ACTIVITY
- LOCATION OF RELEASE 7
LzJ 9
W10
. 11I ~8. I, . .
44".,,:
~--~NA 45
.....-*_ _,_...___________ ___,I .
80 w.
8 PERSONNEL EXPOSURES
- NUMBER TYPE OESCRIPTION
~ I ol ol ol L1J N 7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER OESCRIPTION ITEJ8 9*lol ol ol* ~-~~~N~A~~~~~~~~~~~~----~----'-----_..;...~~---~~
7 11 12 BO OFFSITE. CONSEQUENCES .
EE8 9 7
NA ao LOSS OR DAMAGE ..TO FACILITY
. TYPE OESCRIPTION .
(Ifilll.J .,_____N_A___________________________________,___________...__....____~
7 8 9 10 80 PUBLICITY
. 7EfZlB 9"-------.:.:.:..:--.-...;.
- -NA _____________________________,..__________________________________ ~----~B~O ADDITIONAL FACTORS
~
~*.
NA 7 8 9 80
.. ~.E; __--____G;;..*;._;L;;..;.__;_B.;.;;;o.;.;.;rn~b~a--_______________ PHONE: _ _E_x_t_._42 ........
- 1. - -
GPO 811t*eG7
CAUSE DESCRIPTION (Continued)
It is believed that the water originated from a leaking area cooler (Which has since been repaired) located above the jun~tion box.
The switch was cleaned and reset to trip at the correct setpoint. In addition, the cable penetr(~t~,Q~ri:from the junction box was sealed. Examina-tion of the hearby switches indicated that water in~leakage was limited to this particu~ar switch. DPIS 3-261-26 is a Barton model 278 unit with a range of 0 - 200 psig.