|
|
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:8' Commonw.A. 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 -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 to your office in 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 e I I I I I.** LsE PRINT AU REQUIRED 1NFORMA.T10NJ LICENSEE NAME . 6 LICENSE NUMBER UC EN SE TYPE ILlolRlsl3I I o I o 1-1 o I o I o I o I ol -1 o I o I l 4 I I I 1 I 1 I 1 I 7 8 9 14 15 25 26 30 . CATEGORY TYPE. SOURCE @mcoN'T I I . L!:J lJ:J 7 . 8 57. 58 '. _59 60 OOCKET NUMBER I o I s I o I _:_ I o 1-2 I 4 l 9 I 61 68 . EVENT OA TE . I o I 21 21 11 71 '71 69 74 EVENT DESCRIPTION * * -* EVENT TYPE Io I 3 I 31 REPORT DATE 1013121317171 75 80* fol2l __ __ __ s_t_e_a_m_l_t_i_n_e __ __ i_s_o_l_a_t_i_o_n __ s_w_i_t_c_h ____ __JI 7 . 8 9 80 lol3I __ __ w_a_s __ f_o_u_n_d __ __ __ __ __ ____ __JI 7 *8 9 80 10151,J I ine would have provided the required isolation had.an _anGal high-flow con-:-l 7* .8 (Q]§J .. ___ . _d_i_t_io_n __ o_c_c_u_r_r_e_d_. ___ T_h_i_s __ i._s __ __ o_c_c_u_r_r_e_n_ce __ * ___ -------------11 7 8 9 PRIME . 80 SYSTEM CODE' @£] 1*c1 ol FACILITY STATUS fill] Ll.J 7 .8 9 FORM OF' ACTIVITY* *rn RELEASED LzJ 7 8 9 PERSONNEL " POWER OTHER STATUS IQ I 4 I 3 I 10 12 13 CONTENT OF RELEASE AMOUNT OF ACTIVITY W . I 10 11 EXPOSURES * NUMBER TYPE OESCRIPTION I ol ol ol L1J N 7 8 9 11 12 13 PERS'ONNEL INJURIES NUMBER OESCRIPTION COMPONENT SUPPLIER COMPONENT MANUFACTURER w I BI 0 I 8 I 0 I 43 44 47 METHOD OF DISCOVERY I I 44 45 46 NA \/10LATl)N I tY1 I 48 * LOCATION OF RELEASE 80 I, ... 44".,,: 45 ..... -* _ _,_... ___________ ___,I .. w. 80 80 ITEJ lol ol ol* 7 8 9* 11 12 BO OFFSITE. CONSEQUENCES . EE NA 7 8 9 ao LOSS OR DAMAGE .. TO FACILITY . TYPE OESCRIPTION . (Ifilll.J .,__ ___ N_A _________________________________ __,_ __________ ...__....__ __ 7 8 9 10 80 PUBLICITY . EfZl *-NA 7 B 9"-------.:.:.:..:--.-...;. ____________________________ _,.. __________________________________ ADDITIONAL FACTORS NA 7 8 9 80 .. __ --____ _______________ 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 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. | | {{#Wiki_filter:8' Commonw.A. 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 -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 to your office in 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 e I I I I I.** LsE PRINT AU REQUIRED 1NFORMA.T10NJ LICENSEE NAME . 6 LICENSE NUMBER UC EN SE TYPE ILlolRlsl3I I o I o 1-1 o I o I o I o I ol -1 o I o I l 4 I I I 1 I 1 I 1 I 7 8 9 14 15 25 26 30 . CATEGORY TYPE. SOURCE @mcoN'T I I . L!:J lJ:J 7 . 8 57. 58 '. _59 60 OOCKET NUMBER I o I s I o I _:_ I o 1-2 I 4 l 9 I 61 68 . EVENT OA TE . I o I 21 21 11 71 '71 69 74 EVENT DESCRIPTION * * -* EVENT TYPE Io I 3 I 31 REPORT DATE 1013121317171 75 80* fol2l __ __ __ s_t_e_a_m_l_t_i_n_e __ __ i_s_o_l_a_t_i_o_n __ s_w_i_t_c_h ____ __JI 7 . 8 9 80 lol3I __ __ w_a_s __ f_o_u_n_d __ __ __ __ __ ____ __JI 7 *8 9 80 10151,J I ine would have provided the required isolation had.an _anGal high-flow con-:-l 7* .8 (Q]§J .. ___ . _d_i_t_io_n __ o_c_c_u_r_r_e_d_. ___ T_h_i_s __ i._s __ __ o_c_c_u_r_r_e_n_ce __ * ___ -------------11 7 8 9 PRIME . 80 SYSTEM CODE' @£] 1*c1 ol FACILITY STATUS fill] Ll.J 7 .8 9 FORM OF' ACTIVITY* *rn RELEASED LzJ 7 8 9 PERSONNEL " POWER OTHER STATUS IQ I 4 I 3 I 10 12 13 CONTENT OF RELEASE AMOUNT OF ACTIVITY W . I 10 11 EXPOSURES * NUMBER TYPE OESCRIPTION I ol ol ol L1J N 7 8 9 11 12 13 PERS'ONNEL INJURIES NUMBER OESCRIPTION COMPONENT SUPPLIER COMPONENT MANUFACTURER w I BI 0 I 8 I 0 I 43 44 47 METHOD OF DISCOVERY I I 44 45 46 NA \/10LATl)N I tY1 I 48 * LOCATION OF RELEASE 80 I, ... 44".,,: 45 ..... -* _ _,_... ___________ ___,I .. w. 80 80 ITEJ lol ol ol* 7 8 9* 11 12 BO OFFSITE. CONSEQUENCES . EE NA 7 8 9 ao LOSS OR DAMAGE .. TO FACILITY . TYPE OESCRIPTION . (Ifilll.J .,__ ___ N_A _________________________________ __,_ __________ ...__....__ __ 7 8 9 10 80 PUBLICITY . EfZl *-NA 7 B 9"-------.:.:.:..:--.-...;. ____________________________ _,.. __________________________________ ADDITIONAL FACTORS NA 7 8 9 80 .. __ --____ _______________ 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 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. |
| | |
| }} | | }} |
Revision as of 02:20, 21 March 2018
|
---|
Category:Letter
MONTHYEARML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24129A1352024-05-0808 May 2024 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24083A0022024-03-22022 March 2024 IEMA-OHS Comment Dresden HI-STORM Exemption EA & Fonsi RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24061A1702024-03-0101 March 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS 2024-09-04
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARRS-11-124, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-07-28028 July 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 SVPLTR 09-0044, Day Response on Inadvertent Control Rod Withdrawal2009-09-21021 September 2009 Day Response on Inadvertent Control Rod Withdrawal SVPLTR 09-0027, Written Follow Up Report on Release of Radionuclide2009-07-0606 July 2009 Written Follow Up Report on Release of Radionuclide RS-08-073, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima22008-05-23023 May 2008 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima2 ML0216407762002-06-0707 June 2002 Offsite Dose Calculation Manual (OCDM) Required Action Not Met During Units 2/3 Main Chimney Particulate, Iodine, and Noble Gas Sampling System Inoperability ML17252A3201977-11-23023 November 1977 LER 77-047/03L-0 for Dresden Unit 3 Regarding During Normal Unit 3 Operation, Surveillance Program Review Revealed Violation of T.S.1.0.CC.b Maximum Combined Interval Time by 3.5 Days for HPCI Monthly Valve and Pump Operability ML17252A2881977-05-0303 May 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-8 ML17252A2911977-04-22022 April 1977 License Event Report - Rod Withdrawal at Approx. 44% Power, Discovered Rod Block Monitor Channels 7 and 8 Automatically Bypassed ML17252A2901977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-10 ML17252A2711977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-9 ML17252A2721977-04-20020 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-7 ML17252A2751977-03-23023 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2821977-03-0202 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2581977-01-20020 January 1977 Transmittal of Reportable Occurrence Report No. 50-249/1976-36 ML17252A2701976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 IR 05000249/20190761976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 ML17252A2461976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B ML17252A2451976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-25 in Accordance with Technical Specifications, Section 6.6.B ML17252A2391976-10-22022 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-20 in Accordance with Technical Specifications, Section 6.6.B ML17252A2411976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-18 in Accordance with Technical Specifications, Section 6.6.B ML17252A2401976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-19 in Accordance with Technical Specifications, Section 6.6.B ML17252A2231976-10-12012 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-15 in Accordance with Technical Specifications, Section 6.6.B ML17252A2261976-09-30030 September 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-17 in Accordance with Technical Specifications, Section 6.6.B ML17252A2361976-07-0101 July 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-1 ML17252A2101976-02-0505 February 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-3 in Accordance with Technical Specifications, Section 6.6.B IR 05000249/19750361975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1761975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1711975-08-15015 August 1975 Report of A.O. Per Section 6.6.A of the Technical Specifications Isolation Condenser High Flow Sensor Setpoint Drift IR 05000249/19750321975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A1741975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A4471975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings IR 05000249/19750311975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings ML17252A7861975-03-27027 March 1975 Report of Abnormal Occurrence Per Section 6.6.a of the Technical Specification - Exceeding Set-point on Main Stream Line Hi Hi Rad ML17252A8271975-02-14014 February 1975 Report of Abnormal Occurrence Per Section 6.6.A of the Technical Specification - Reactor Feed Pump 3C Pump Casting Vent Line Weld Leak ML17252A8361975-01-14014 January 1975 Report of 4 Inch Recirculation Bypass Line Inspection 2011-07-28
[Table view] |
See also: IR 05000249/2019077
Text
8' Commonw.A. 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 -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 to your office in 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 e I I I I I.** LsE PRINT AU REQUIRED 1NFORMA.T10NJ LICENSEE NAME . 6 LICENSE NUMBER UC EN SE TYPE ILlolRlsl3I I o I o 1-1 o I o I o I o I ol -1 o I o I l 4 I I I 1 I 1 I 1 I 7 8 9 14 15 25 26 30 . CATEGORY TYPE. SOURCE @mcoN'T I I . L!:J lJ:J 7 . 8 57. 58 '. _59 60 OOCKET NUMBER I o I s I o I _:_ I o 1-2 I 4 l 9 I 61 68 . EVENT OA TE . I o I 21 21 11 71 '71 69 74 EVENT DESCRIPTION * * -* EVENT TYPE Io I 3 I 31 REPORT DATE 1013121317171 75 80* fol2l __ __ __ s_t_e_a_m_l_t_i_n_e __ __ i_s_o_l_a_t_i_o_n __ s_w_i_t_c_h ____ __JI 7 . 8 9 80 lol3I __ __ w_a_s __ f_o_u_n_d __ __ __ __ __ ____ __JI 7 *8 9 80 10151,J I ine would have provided the required isolation had.an _anGal high-flow con-:-l 7* .8 (Q]§J .. ___ . _d_i_t_io_n __ o_c_c_u_r_r_e_d_. ___ T_h_i_s __ i._s __ __ o_c_c_u_r_r_e_n_ce __ * ___ -------------11 7 8 9 PRIME . 80 SYSTEM CODE' @£] 1*c1 ol FACILITY STATUS fill] Ll.J 7 .8 9 FORM OF' ACTIVITY* *rn RELEASED LzJ 7 8 9 PERSONNEL " POWER OTHER STATUS IQ I 4 I 3 I 10 12 13 CONTENT OF RELEASE AMOUNT OF ACTIVITY W . I 10 11 EXPOSURES * NUMBER TYPE OESCRIPTION I ol ol ol L1J N 7 8 9 11 12 13 PERS'ONNEL INJURIES NUMBER OESCRIPTION COMPONENT SUPPLIER COMPONENT MANUFACTURER w I BI 0 I 8 I 0 I 43 44 47 METHOD OF DISCOVERY I I 44 45 46 NA \/10LATl)N I tY1 I 48 * LOCATION OF RELEASE 80 I, ... 44".,,: 45 ..... -* _ _,_... ___________ ___,I .. w. 80 80 ITEJ lol ol ol* 7 8 9* 11 12 BO OFFSITE. CONSEQUENCES . EE NA 7 8 9 ao LOSS OR DAMAGE .. TO FACILITY . TYPE OESCRIPTION . (Ifilll.J .,__ ___ N_A _________________________________ __,_ __________ ...__....__ __ 7 8 9 10 80 PUBLICITY . EfZl *-NA 7 B 9"-------.:.:.:..:--.-...;. ____________________________ _,.. __________________________________ ADDITIONAL FACTORS NA 7 8 9 80 .. __ --____ _______________ 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 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.