|
---|
Category:Letter
MONTHYEARML24352A2072024-12-17017 December 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24323A0792024-11-15015 November 2024 Transmittal of Dresden, Units 2 and 3, Core Operating Limits Report Cycle 29 ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 RS-24-102, Supplement to 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-5912024-10-21021 October 2024 Supplement to 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-591 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24225A2132024-09-26026 September 2024 Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24253A0942024-09-23023 September 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249) ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24299A1922024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation2024-01-19019 January 2024 HPCI Inoperable Due to Air Void Accumulation 05000237/LER-2022-001-01, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-10-28028 October 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000237/LER-2022-002-01, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-10-28028 October 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-002, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-09-27027 September 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-001, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-09-0909 September 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000249/LER-2021-001-01, Reactor Scram Due to Main Power Transformer Failure2022-06-14014 June 2022 Reactor Scram Due to Main Power Transformer Failure ML20135G7442020-05-14014 May 2020 Final ASP Analysis - Dresden 2 (LER 237-90-006) 05000249/LER-2019-001, Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications2019-11-19019 November 2019 Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications 05000237/LER-2019-002, Scram Due to Main Turbine Low Oil Pressure Trip2019-07-0202 July 2019 Scram Due to Main Turbine Low Oil Pressure Trip 05000237/LER-2019-001, Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow2019-03-29029 March 2019 Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage2018-02-15015 February 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits2018-01-0202 January 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak2017-11-10010 November 2017 Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak 05000237/LER-1977-050, /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling2017-11-0303 November 2017 /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling 05000249/LER-1977-040, /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position2017-10-21021 October 2017 /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position 05000237/LER-1978-028, /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suct2017-08-28028 August 2017 /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Valves ML17252B4922017-08-28028 August 2017 LER 78-028/01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction 05000237/LER-1916-003, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria2017-05-26026 May 2017 Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000237/LER-2016-004, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement2017-01-0909 January 2017 Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000237/LER-2016-003, Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria2016-11-18018 November 2016 Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000249/LER-2016-001, Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire2016-08-25025 August 2016 Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-002, Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability2016-07-15015 July 2016 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-001, Regarding Secondary Containment Differential Pressure Transient2016-04-0808 April 2016 Regarding Secondary Containment Differential Pressure Transient 05000237/LER-2015-005-02, Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-03-31031 March 2016 Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-005-01, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-02-25025 February 2016 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-003, Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously2015-10-30030 October 2015 Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously 05000237/LER-2015-005, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2015-10-30030 October 2015 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value2015-10-29029 October 2015 Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value 05000237/LER-2015-002, Regarding 2C ERV Failed to Actuate During Extent of Condition Testing2015-04-0303 April 2015 Regarding 2C ERV Failed to Actuate During Extent of Condition Testing 05000237/LER-2015-001, Regarding Unit 2 Scram Due to Feedwater Level Control Issues2015-03-0606 March 2015 Regarding Unit 2 Scram Due to Feedwater Level Control Issues 05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing2015-01-0505 January 2015 Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing 05000237/LER-2014-003, Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer2014-06-0606 June 2014 Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer 05000237/LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure2014-06-0606 June 2014 Regarding Reactor Scram Due to Main Power Transformer Failure 05000237/LER-2014-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-05-27027 May 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-009, Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open2014-01-29029 January 2014 Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open 05000249/LER-2013-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-27027 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-008, Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier2014-01-24024 January 2014 Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier 05000237/LER-2013-007, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-15015 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-005, Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits2014-01-13013 January 2014 Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits 05000237/LER-2013-006, Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected2014-01-13013 January 2014 Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected 05000237/LER-2013-004, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-0606 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-003, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-11-22022 November 2013 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-002, Movement of Control Rods with Control Rod Block Monitor Inoperable2013-09-27027 September 2013 Movement of Control Rods with Control Rod Block Monitor Inoperable 05000237/LER-2013-001, Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-08-23023 August 2013 Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2011-005-01, For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure2012-12-18018 December 2012 For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure 05000237/LER-2012-001, Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver2012-12-0606 December 2012 Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver 05000249/LER-2012-001, Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure2012-09-10010 September 2012 Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure 05000237/LER-2012-002, Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities2012-07-23023 July 2012 Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities ML1015505692009-07-24024 July 2009 Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3. ML0602404072004-05-0505 May 2004 Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3 2024-01-19
[Table view] |
Text
,, .
- Commonwe. Edison Dresden Nuclear wer Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 May 12, 1978 BBS Ltr /178~828 James G. Keppler, Regional Director*
Directorate.of.Regulatory Operations - Region III U.S. Nuclear.Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137.
Repor~~ble;Otcurrence Repo~t ff78~030/01T-0 Docket 11050-237 is hereby submitted *to your office in accordance.with Dresden Nuclear Power Station Technical Specification 6.6.B.l.(f), personnel error which prevents ~r could prevent, by itself, the fulfillment of.the functional requirements of . syste!Tls required. t6 .cope with accidents analyzed in. the SAR.
Statio.n Superintendent*
Dresden Nuclear Power Station
. BBS/deb*
cc: Director of Inspectiofi & Enforcement*
Director of Management Information & Program Control File/NRC
~7*-*1*J,*::J(l(li~1
'. *=* *- . - I 1*
e . . **.
NRC FORM 366 :,,, .. U.S .. NUCLEAR REGULATORY COMMISSION.
(7*7'Jl
\:.
eoNTROL BLOCK: .____.__..._I_ ....1_*__..I_"'_.-_.I_ _.10 * (PLEASE PRINT OR TYPE)iALL REQUIRED INFORMATION) 6
~ I I I LI DIR Is I 2 101 0 o I - I o I o I o I o I o I - Io Io IG)l 4 11 11 11 I 1 l©I I 10 7 8 9 LICENSEE COOE 14 15 LICENSE NUMBER 25
- 26 LICENSE TYPE :JO 57 CAT 58 CON'T
-~~~~~~ L!J© 1 oI s.10 I o I o I 2 I 3 60 . . 61 .* DOCKET NUMBER.
I 1 101 68 69 o I 4 I ~ I a I 1 I a I© I o I s I 1 EVENT DATE 74 75 REPORT.DATE
- 1- 2..1 1_LRlG) 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@ .
I During Unit .2 startup operations the "A" LPCI and Core Spray Subsystems were
[ITIJ inadvertantly tendered inoperable. At this time preparations were in progress on
[IIIJ L-..:U...::.n::i:..:t:.._:3:.._f:..:o:..:r:__*t:...h:..:..e.:.._'E_C..:....:..C'"""S_*...::.U...::.n_d_e_r_v_o_l_t_a.-::g::..e_F_u_n_c-'__t_i_on_a_l_T_e_s_t_.__S~u_b_s_e_q_,_u_e_n_t_ly"--_a_t_0_4_0_S_h_o_u_r"""s___.i_t_w_a_s___.
!Im. J. determined that the. eqtdprr.ent attendant had closed. the "A" and "B" LPCI pump and "A"
[ill] I
- Core Spray Pump. Manual Discharge ValVes on* Unit 2 instead of Unit 3. L
[TI?].
[ill]
7 s .9 *so SYSTEM CAUSE CAUSE ..
.CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE *
[TI2J
. S*
I SI Fl@ LA.J@ L!J@) LY Al LI Vj El x1e ~ LEJ@
9 10 11 12 13 lS 19 20 SEQUENTIAL . OCCURRENCE REPORT REVISION
0 LERiRO LVENT YEAR REPORT NUM.BER I2°17 I 8 22.I I23 *1.
REPORT No:
I* 0 I 3 I 0 26I 24 .
I2.7/I CODE I2S 0 I 129I wTYPE 30 l=J 31*
NO.
LQJ
.32
.ACTION TAKEN rUTURE ACTION EFFECT ON PLANT SHUTDOWN METHOD HO.URS ~.
6 ATTACHMENTSUBMITTED
PRIME COMP.
COMPONENT MANUFACTURER W@W@ W@ W 101010 10 I LU@ ~ ~@) IZ 19 19 19 I@'
33 34 . 35 36 37 40 41 42 43 44. . 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
Upon discovery.of the personnel error at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> the pump discharge valves were ITITI I returned to. their normally locked open position and verified by 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />. In IJ:TIJ I addition the "A LPCI and "A" Core Sray Subsytems were satisfactorily flo~ tested. I IJJIJ 1 ** Normal Unit 2 startup then continued *. Personnel involved were admonished for OJI] their error.
7 s 9 BO FACILITY *~30 METHOD OF * ~
. STATUS % POWER . OTHER STATUS.~* DISCOVERY . . . . . . DISCOVERY DESCRIPTION, ~* . .
[QIL~@
.7 . . 8 9 I0 I 10 01 0 1.2 l@I. NA
"-13'--.-----'"--....,...-4~4
. r l.AJ@)I
- .45 . . 46 Operational Event - Rx Level increas.e 80 ACTIVITY, CONTENT . . r::;;-. (.;';;\
- RELEASED OF RELEASE AMOUNT OF ACTIVITY . . LOC.ATION OF RELEASE\~.~,;:
.EITJ UJ @) WL-l___N=A.:........._
7 8 9 . 10 11 44 I
45 NA 80 r:;;:;,.
PERSONNEL. EXPOSURES NUMBER (::;:;\. TYPE
. C)ESCRIPTION e
ETil 1 0 I 0 I 0 lUJ@I 12 13
. ... NA ;
8 9 11' so.
PERSONNEL IN.JURIES * .. (;":;\
. NUMBE~ . . DESCRIPTION~-~/
'12:li]' I 0 I 0 I 0 I@ . .* . . NA
.8 9 . . 1.1 ~12~.-*--.----'~--'----,---:'---------------------------------------8-'0
'LOSS OF OR DAMAG.E TO FACILITY 14'3\.
TYPE DESCRIPTION* '\!.::)
.[Q2)
.LlJ@ ,.*
. NA .
- -;10::-'*-**--'-'=--------.,....---7-,----,----..,-----....,....-----'----._....,.._.,....-.,......;.._-----IBO PUBLICITY Q ISSUEDt,;°:;\ D~SCRIPTION ~ NRC U.SE ONLY "'
[IliJ8 U!.161 9 . NA
~--------'------------'68 I I I I I I I I I I I I I~
69 SO* 0:
NAME OF PREPARER _ _ _J_._W_u_,,j.._c_i_,g,._a _ _ _ _ _ _ _ _ __ PHONE =--x_-_2_6.,..,s,.,.,....._____.,...____ 0 a.
I,
' *' ~ '
~ .""). j ATTACHMENT TO LICENSEE EVENT REPORT 78-030/0lT-0 COMMONWEAL TH EDISON COMP ANY ( CWE)
DRESDEN UNIT-2 (ILDRS-2)
DOCKET 11050-237 During normal Unit 2 startup operations at 0005 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.s on April 28, 1978 the "A" Low Pressure Coolant Injection (LPCI) and "A" Core Spray. Subsystems were inadvertantly rendered inoperable. At*the time* of the event prep*arations were in progress (DOS 6600-6) **
on Unit 3 while in the shutdown condition for the Emergency Core Cooling System (ECCS) undervoltage Functional Test. Following initiation of the test, at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> it was determined.that the Equipment Attendant (EA) had closed the "A" and "B" LPCI pump*
and "A" Core Spray Pump Manual Discharge Valves on Unit 2 instead of Unit 3. At 0420hours the Unit 2 manual discharge valves were returned to their normally locked open position and verified'. In .
addition the "A" LPCI and. "A" Core Spray S~bsystems were satisfactorily flow tested. Unit 2*startup operations continued. During the approximate four (4) hour interval. when the Au LPCI and Core Spray Subsystems were inoperable the remaining two*(2) LPCI*
pumps ~ere available to fulfill the Containment Cooling Function.
- In additio11 the redundant 100% capacity Core Spray System was availkble*tb
. provide sufficient core cooling in the unlikely event of a loss of coolant accident. There are no previous events of a similar nature at Dresden~
A subsequent review of the event with the appropriate operations personnel revealed that the. Equipment Attendant (EA) assigned to
.Unit 3 for specific valving operations involving the ECCS test mistakenly closed the three discharge valves.discussed previously on Unit 2
- the personne:i, involved were admonished regarding* the{r errors.
At this time, -an investigative .committee ha*s been assigned to fur'ther
--i~~~stigate th~ event and provide recommendations to prevent .. *a.
A supplemental report will . be sub.mittea
. . I following .the investigation!
~5'ri'"T"~li?._£1M@lltqdt&<o!!ti£!"'~ -~~"':l?~~~,.--r.~,11)---zm:*,-,..__ __... ;:.-~~c---....iiw.---.....--*-----.
.,