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Category:Inspection Report
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) IR 05000237/20230032023-11-13013 November 2023 Integrated Inspection Report 05000237/2023003 and 05000249/2023003 and Exercise of Enforcement Discretion IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 IR 05000237/20230102023-03-0909 March 2023 Biennial Problem Identification and Resolution Inspection Report 05000237/2023010 and 05000249/2023010 IR 05000237/20220062023-03-0101 March 2023 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2022006 and 05000249/2022006) IR 05000237/20220042023-02-10010 February 2023 Integrated Inspection Report 05000237/2022004, 05000249/2022004 and 07200037/2022002 IR 05000237/20224022023-01-0505 January 2023 Security Baseline Inspection Report 05000237/2022402 and 05000249/2022402 IR 05000237/20224012022-11-30030 November 2022 Security Baseline Inspection Report 05000237/2022401 and 05000249/2022401 (Cover Letter Only) IR 05000237/20220032022-10-31031 October 2022 Integrated Inspection Report 05000237/2022003 and 05000249/2022003 ML22270A1032022-09-27027 September 2022 Notification of NRC Baseline Inspection and Request for Information (05000249/2022004) IR 05000237/20220122022-09-0606 September 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000237/2022012 and 05000249/2022012 IR 05000237/20220052022-08-22022 August 2022 Updated Inspection Plan for Dresden Nuclear Power Station (Report 05000237/2022005; 05000249/2022005) IR 05000010/20220012022-08-0808 August 2022 NRC Inspection Report No. 05000010/2022001(DNMS) - Dresden Nuclear Power Station, Unit 1 IR 05000237/20220022022-08-0808 August 2022 Integrated Inspection Report 05000237/2022002; 05000249/2022002 and 07200037/2022002 and Exercise of Enforcement Discretion ML22180A2512022-06-30030 June 2022 2022 Dresden Cover Letter IR 05000237/20220012022-04-20020 April 2022 Integrated Inspection Report 05000237/2022001 and 05000249/2022001 IR 05000237/20220112022-04-12012 April 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000237/2022011 and 05000249/2022011 IR 05000237/20210062022-03-0202 March 2022 Annual Assessment Letter (Report 05000237/2021006 and 05000249/2021006) IR 05000237/20210042022-02-0707 February 2022 Integrated Inspection Report 05000237/2021004 and 05000249/2021004 IR 05000237/20214032022-01-26026 January 2022 Security Baseline Inspection Report 05000237/2021403 and 05000249/2021403 IR 05000237/20213022021-12-29029 December 2021 NRC Initial License Examination Report 05000237/2021302; 05000249/2021302 IR 05000237/20220102021-12-21021 December 2021 Notification of NRC DBAI (Programs) and Initial RFI Inspection Report 05000237/2022010 05000249/2022010 IR 05000010/20210012021-11-0909 November 2021 NRC Inspection Report No. 05000010/2021001(DNMS) - Dresden Nuclear Power Station, Unit 1 IR 05000237/20210032021-11-0101 November 2021 Integrated Inspection Report 05000237/2021003 and 05000249/2021003 IR 05000237/20210112021-09-30030 September 2021 Triennial Fire Protection Inspection Report 05000237/2021011 and 05000249/2021011 IR 05000237/20210052021-09-0101 September 2021 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3, Report 05000237/2021005 and 05000249/2021005 IR 05000237/20215012021-08-25025 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2021501 and 05000249/2021501 IR 05000237/20210022021-08-0909 August 2021 Integrated Inspection Report 05000237/2021002 and 05000249/2021002 IR 05000237/20214042021-08-0909 August 2021 Security Baseline Inspection Report 05000237/2021404 and 05000249/2021404 IR 05000237/20213012021-06-17017 June 2021 NRC Initial License Examination Report 05000237/2021301; 05000249/2021301 IR 05000237/20214012021-05-21021 May 2021 Cyber Security Inspection Report 05000237/2021401 and 05000249/2021401 IR 05000237/20210012021-04-13013 April 2021 Integrated Inspection Report 05000237/2021001 and 05000249/2021001 IR 05000237/20214022021-03-16016 March 2021 Security Baseline Inspection Report 05000237/2021402 and 05000249/2021402 IR 05000237/20200062021-03-0404 March 2021 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2020006 and 05000249/2020006) IR 05000237/20210102021-02-23023 February 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000237/2021010 and 05000249/2021010 IR 05000237/20200042021-02-10010 February 2021 Integrated Inspection Report 05000237/2020004 and 05000249/2020004 IR 05000237/20200902020-12-17017 December 2020 Reissue Dresden Nuclear Power Station, Units 2 and 3 - NRC Inspection Report 05000237/2020090 and 05000249/2020090 IR 05000237/20204032020-12-16016 December 2020 Security Baseline Inspection Report 05000237/2020403 and 05000249/2020403 ML20342A2832020-12-0707 December 2020 NRC Inspection Report 05000237/2020090 and 05000249/2020090 IR 05000237/20200032020-11-10010 November 2020 Integrated Inspection Report 05000237/2020003 and 05000249/2020003 ML20307A4832020-11-0202 November 2020 NRC Inspection Report No. 05000010/20200001 (DNMS) - Dresden Nuclear Power Station, Unit 1 IR 05000237/20200052020-09-0101 September 2020 Updated Inspection Plan for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2020005 and 05000249/2020005) IR 05000237/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000237/2020301; 05000249/2020301 2024-02-02
[Table view] Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] |
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U. S. ATOMIC ENERGY COMMISSION
- . DIRECTORATE OF REGULATORY OPERATIONS.
- -----~-{-* ----"-- ----- -------------- --------------REGION. III - ---- - - ----- - --- - -
Report of Operations Inspection RO .Inspection Report No. 050-249/74-07 Licensee: Commonwealth Edison Company P.O. Box 767 Chicago, Illinois 60690 Dresden Uriit 3 License No. DPR-25
. 'I Morris, Illinois Category: C Type of Licensee: GE, BWR, 809 Mwe Type of Inspection: *Special, _Announce.d Dates of Inspection: June 25, July 1, 2 and 10, 1974 Dates of Previous Inspection:. June 10-14, ~5 and 26, 1974 (Operations)
Principal Inspector: ~~~ f' /;)3b(
'(Dale)
~~t~ t_'
Accompanying Inspector:
....,c'~ lBrown 1
f,@317'/
(Dite)
Other Accompanying Personnel: L. Beratan, RO:HQ R. Lofy, Parameter, Inc.
R. Dean, Parameter, Inc.
~':;_._,.,,db;~ ,J~
c:;6t'-c?~~c....-L.t::-l:'-l--*c.. ~k:_.
Reviewed By: H. C. Dance, Senior Reactor Inspector Nuclear Support Operations Branch
SUMMARY
OF FINDINGS Enforcement Action: ___ None--------------------------------
Licensee Action On-Previously Identified Enforcement Items: Not Inspected Unusual Occurrence Feedwater System Hydraulic Shock. ,
Other Significant Findings A. Current Findings A hydraulic shock occurred in Unit 3 Feedwater System on June i3, 1974.
The shock caused pipe movement-and e-quipment damage. *The licensee was performing a pipe and equipment inspection before restarting the Unit.
B. Status Of Previously Reported Unresolved Items: None Management Interview The following subjects were discussed on the completion of the June 25,- 1974, inspection with Messrs. B. Stephenson, Station_ Superintendent; T. Watts, Supervi~ing Engineer; T. Lang, Engineer; G. Lampy, Engineer.
A. The inspector stated that he understood that all the feedwater piping would be visually inspected and magnetic particle inspected at stres_s points. The licensee concurred.
B.
The inspector inquired as to the rest of the licensee's program before the Uni.t was restarted~ The licensee stated that a program was being developed by the C. E. Engineering group to check all the equipment and.
piping in the system and then make required repairs~ The system would be checked for operation and completed program reviewed by C. E. Engineering before the Unit was restarted. -
- c. The inspector inquired into the desirability to perform a *stress analysis of the piping in question and determine if its useful life*
.... has been reduced, using the most conservative movement noted. The
*licensee stated that their Engineering Department and Sargent and Lundy Engineers had determined such calculations were not required.
D. The inspector stated that after reviewing the recorder charts it is apparent that the in_itiating cause was not the rupture of the control air lines of the low flow regulating valve, but the closing of the main 2 -
feedwater regulating valve. Closure of the main valve was probably caused by. spikes in the feedwater flow signal. The licensee stated the investigation will continue in* an effort t.o determine and cor-rect the problem.. _________________________ ---- ------- ---- ------------
-~-----*----
At the July 10,1974 meeting, (See Section II of this report) Com-monwealth Edison representatives agreed to conduct .a stress analysis of the affected systems and submit a summary of the findings to Regulatory Operations. *
... ';""'--r*~~**-**.. -***-*-***---** ..
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--""* ......... *---***,*--------------- -* ... _ . - \ . - - . ***** *-*
REPORT DETAILS
-*--~----- ___________________ ---~~-r:_ !_~r~~a_r~~~!--~*- H~ _Br_~~ __________ *--* ________.__ _
Persons Contacted B. S.tephenson, Dresden Station Superintendent T. Vatts, Dresden Supervisory Engineer, Technical Staff T. Lang, Engineer, Technical Staff G. Lampy, Engineer, Technical Staff D. Galle, Mechanical and Structural Engineer, CECO
*G. Kitz, Sargent and Lundy F. Spakoski, Sargent and Lundy E. Branch, Sargent and Lundy D. Sedgurck, Sargent and Lundy J. Muffett, Sargent and Lundy ~
J. Irish, Sargent and Lundy * *
- 1. Feedwater System Hydraulic Shock On June 23, 1974 at 2217 the feedwater system for Unit 3 experienced a hydraulic shock that caused displacement of equipment and piping. The
.Unit was operating .at 660 Mwe (79%) with two reactor feed pumps
*Operating. The movement caused damage to some concrete supports and i*.. -
several piping restraints.
*During the inspection conducted on June 25, the following recorder
-charts were reviewed:
Reactor Vessel Level Reactor Feedwater Flow APRM Reactor Pressure (Narrow Range)
Turbine Steam Flow Condensate Demineralizer Lj P
- F~edwater Temperature The Shift Supervisor's log was reviewed with the following entries relating to the event.
3A feedwater regulating valve had been controlling feedwater at .the*
time of the event.
2214 - 3B Feedwater regulating valve lockout alarm received.
2216 - Feedwater preheaters 3Dl, 3D2, 3D3, 3Bl, 3B2, and 3C2 tripped *
.2217 - 3A Feedwater regulating valve lockout alarm received.
2218 - Cleanup recirculating pump tripped.
2219 - Reset 3A Feedwater regulating valve lockout.
__ . ---....--,------- - .. -*- ..- **~ ***** *-** ..., ***- - *-** -
-------::r I
*- Air lines to 3B Feedwater regulating valve and low flow regulating valve were reported damaged. ~,
2240~_<;],_~~Jl'Jp__ pump _restarted------ --- -
--. - - - ----------2248 - Preheaters reset. .
The key recorder charts showed the following changes at the time of the event.
Reactor Feedwater Flow was indicat~ng about 7 x 106 lb/hr prior ~o the event tgen spiked down to 2.6 x 10 lb/hr and back to full scale of _
12 x 10 lb~hr and held at 8.6 x 106 lb/hr for a short time then back
*to 7.0 x 10 lb/hr. The chart was marked at this point stating that 3A regulating valve was reset.
The APRM charts showed a maximum spike downscale of 7% and then* an upscale maximum spike of 5% from a ~minal 75% indicated reactor power level.
The Condensate DemineralizerilP chart indicated a rapid decrease in differeµtial pressure across the demineralizer beds from 37 to 4 psid.
The damage resulting from the shock included the following:
- a. The spring loaded pipe supports .for the discharge pipe of the
. two operating feedwater pumps, and one of the discharge lines from the high pressure preheaters were displaced.
- b. The concrete pipe support for the low flow regulating valve was
*.. i partially broken.
- c. The concrete grouting around supports for the high pressure heaters and the main feedwater regulating valves was broken loo.se.
- d. The pipe hangers on the discharge pipe of the high pressure pre-heaters had the pad tack welds broken and the hangers ~ere dis-placed.
- e. The air lines to the low flow regulating valve were broken which allowed the valve to go full open and the operator was rotated in its clamp approximately 30°. *
- f. One of the holddown bolts for the support on 3A feedwater regulating valve was sheared.
- g. 3A feedwater pump had been displaced en~ugh to bend the stack pins.
- b. The minimum flow line for 3A feedwater pump had sections of insu-lation broken off. ~
--=:--*--*-**-----:-----.. - --* ..... -
--**r*
At the time of the June 25, 1974 inspection. the licensee was con-
. ducting a magnetic particle insp.ec.tion of the feeqwater pipe. The
__ -*----- _______ !~~=~:::s~;:~::s~~~.~ ~-~~-t-~~~.~e~-~~~t~-~ _P_i~~~~~~~ -:-t~~ ~e--~~~pe~-~e.d_____ ._________ _
The initiating cause of this event is not know, but the system oscilations have been reduced by the licensee converting to a single element level control signal to the feedwater regulating system.
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.Y
**---- *-- :. .,)tEPORT' DETAILS -
*. .: ~ '*
- - * - _____________________________________ !a~~--!I~ __:_ ____________ _ -- --- - - - - - - - - -- - - - - - - - - - -
Prepared by:~+-~-.:o..~...x.._..:=.__,,4-4~:...._~c.........~~~~~~~~
L. L. Bera tan, J *or S true tural Engineer Technical Assi~ ance Branch
- Directorate of Regulatory Operations Dates of Inspection & Meeting: July 1, 2, and 10, 1974
- Reviewed by :_.L--..!..=.~:::........--l!..::....e:=::::::::::....~~~---------
-- K. V. Seyf ri t, Chi,,ef. Date *
*. Technical Assis tanc ranch Directo~ate of Regulatory_ Operations
- 1. Persons Contacted B. s*tephenson. Dresden Power Station G. A. Lampy, Dresden Power Station
. D. P. Calle, Commonwealth Edison Company G. Kitz, Sargent & Lundy '. **
F. Spak~ki, Sargent & Lundy C~ Brown, *RO: III .
L. L. Beratan, RO:HQ R. A. Lofy, Parameter, Inc., AEC Consultant
2. Background
On *June 23, 1974, severe vibrations were experienced in the Unit 3 feedwater system. The vibrations caused damage to the f~edwater regulation valves *and several pipe restraints. The unit was at approximately 630 megawatts at the time of the occurrence and in the process of increasing load. The sequence of events reported
*by the licensee were as follows:*
- Feedwater reguiation valve 3B locked up. Service air compressor 3B tripped (3A regulation valve was in service at the time of failure) ; --
- Feedwater heaters 3Di, 302, 303, *3Bl, 3B2 and 3C2 tripped;
**I .-4
2
- _ Feedwa ter regula :_~on -~a_l_ve _3_A _l_g<:~~g_ yp_. __ F'eedwa ter--flow--and-- ----- ---- ------
- .------------.- -- ---reactor--leve-1 appeared steady for- about 30 seconds, then both
---
- decreased; *level dropped fGom 30 inches -to 21 inches. Feedwater flow decreased from 7 x 10_ lbs/.hr to 2.6 x 106 lbs/hr; Cleanup recirculation pump tripped; Cleanup recirculation pump tripped; Reset 3A feedwater regulation valve. Feedwater flow increased to 12 x 106 lbs/hr and reactor level increased to 35 inches. The air line on the 3B feedwater regulation valve had broken loose and the minimum flow valve was damaged and remained in -the open position; Clean-up system back in service;
-* Feedwater heaters reset; A visual examination of the piping system was made and a shutdown was ordered to make a more detailed examination.
- 3. Findings of Detailed Examination*
The low fl9w feedwater regulation valve was found in the open position and rotated approximately 30 degrees. All air lines and electrical -
feeds to the low flow valve were found broken off or bent. Upstream pipe support for low flow valve found broken off its pad with the concrete base cracked. The "A" feedwater regulation valve upstream
_pipe support pad pulled out of its concrete base. The "B" feedwater regulation valve air supply line found broken off its main header.
All three reactor feed pump discharge line pipe supports showed signs of movement. "A" feedwater discharge line had bent the warming line.
The "C" reactor feed pump discharge line flow element tap looked as though it may have been bent. The welds on this line were tested and found to be satisfactory. The "A" pump* minimum flow to condenser had.
loose insulation. In the "D" heater bay, two pipe hangers on the heater outlet had tack welds broken. A heater line entering the ":X"'area had a displaced pipe support pedestal. In the turbine pipeway in the extraction steam piping, one pipe support pedestal showed 3/4 inch of movement, and one line had the pipe support pad cracked. The reactor feed pump suction heater under the hotwell, had three pipe support pedestal cement pads cracked.
----*-. -~*--------* - " ..... .
,....;. ____ ----- y y
~* .:
3
- 4. Corrective Actions Taken
* - The feedwater piping was in~pg_i:ted_and-:I'epa-~red;- -A-1-1--feed\vate*r-piping __________
---'-'---*------------welds-were--restea-*using--either magnetic particle or dye penetrant, with satisfactory results* *The feedwater regulation valves were checked
- for proper-operation with .special attention given to the "A" regulation_
valve lock~up ability. .
- 5 *. Exit Meeting After completing an inspection of the damaged piping and support systems; it was the position of RO and our consultant that the magnetic particle and dye penetrant.examination was.not adequate to insure that the piping sys-tern had not been over-stressed and their useful life reduced. It was further suggested that the licensee. shou.ld-conduct a stress analysis of the affected sys.terns by imposing. upon 'the system the estimated movements encountered. The licensee wanted to study the problem and requested a.
meeting on July 10, 1974 in the offices of their consultant, Sargent &
Lundy, to establish the parameters of -the stress analysis. This meeting was held as planned on July 10, 1974 irt the offices of Sargent & Lundy and. the parameters of the analysis.and techniques*discussed and agreed upon by the licensee, their consultant~ RO and our consultant, Parameter, Inc. *A list of* attendees of the July 10, 1974 meeting is attached~ It
.was agreed that Commonwealth Edison would submit a report to RO within 40 days. It was also agreed that an open. line of com.'llunication would be
.maintained between Sargent.& Lundy.and our consultant, Parameter Inc.,
in the event some technical question had to be reconciled.
j I.
. -. **- -**-*- --**---~.-******-* .- *- .. -***-*** ... ****-** ***:* ..
*~~LX1 MEETING - JULY 10, 1974 CECO - M&S Engineer G. T. Kitz Sargent & Lundy' F. L. Spakoski Sargent & Lt.indy E~ B. Branch Sargent & Lundy D. J. Sedgurck Sargent & Lundy ,.
J. w. Muffett Sargent & Lundy J. D. Irish Sargent & Lundy
- c. H. Brown us AEC, RO:III L. L. Bera tan US AEC, RO:HQ R. A. Lofy Parameter, Inc., Consultant for AEC R. s. -Dean Parameter, Inc., Consultant for AEC e
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