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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19210A1511976-02-12012 February 1976 Abnormal Occurrence 76-7/1P:on 760212,empty Snubber Fluid Reservoir Found at Location DHH-198.Leakage Due to Damaged Seal.Snubber Removed & Replaced ML19322A4301976-02-0505 February 1976 Abnormal Occurrence 76-6/1P on 760204:radiation Leak Detection Sys Out of Svc for 22-h.No Reactor Bldg Atmospheric Samples Taken.Caused by Cover Plate to Monitor Left Open Following Insp.Procedures Reviewed W/Personnel ML19210A1581975-12-26026 December 1975 Abnormal Occurrence 50-289/75-43:on 751218,one of Six Pressure Switches Tripped at Less Conservative Limits than Tech Specs During Channels Surveillance Test.Caused by Calibr Drift in Associated Pressure Switch PS-290 ML19210A1451975-12-19019 December 1975 Abnormal Occurrence 50-289/75-42:on 751210,outside Containment Isolation Valve for Steam Generator Sample Line CA-V5B Failed to Close.Caused by Valve Manual Operator Inadvertently Left Open by Reactor Personnel ML19210A1731975-11-25025 November 1975 Abnormal Occurrence 50-289/75-40:on 751112,stuck Contacts on Diesel Generator 1A Voltage Relays Threatened Function of Engineered Safety Feature.Caused by Pitting of Relay Contact.Relays Checked at Each Startup Pending Design Mods ML19261F1481975-11-24024 November 1975 Abnormal Occurrence 50-289/75-41:on 751114,personnel Failed to Strictly Follow Drain & Blanketing Procedure.Vented Center Control Rod Drive Mechanism Allowed Radioactive Gas Into Reactor Bldg.Personnel Counseled on Proper Procedures ML19210A1831975-11-21021 November 1975 Abnormal Occurrence 50-289/75-39:on 751112,control Rod 4 in Group 7 Dropped Into Core,Resulting in Asymmetrical Rod Signal & Automatic Power Reduction.Caused by Failure of Stator Winding.Stator Winding Replaced & Tested ML19210A1891975-10-31031 October 1975 Abnormal Occurrence 50-289/75-38:on 751021,control Rod Verification Program Not in Compliance W/Tech Specs.Caused by Procedure Misinterpretation.Revised Surveillance Program Will Clearly State Requirement of Individual Rod Movement ML19210A1911975-10-31031 October 1975 Abnormal Occurrence 50-289/75-37:on 751021,blocked Strainer on Outlet to Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Improper Design Allowing for One Strainer W/No Bypass Caused Blockage ML19210A2021975-10-29029 October 1975 Abnormal Occurrence 50-289/75-36:on 751019,auxiliary Operator Failed to Obtain Radiation Work Permit & Carry Monitoring Device.Caused by Improper Administrative Procedures ML19210A1971975-10-21021 October 1975 Abnormal Occurrence 75-37:on 751021,blocked Strainer on Outlet of Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Plant Returned to Svc in 15 Minutes ML19210A2151975-10-20020 October 1975 Abnormal Occurrence 50-289/75-35:on 751010,improper Mix of Boric Acid Crystals Caused Blockage in Mix Tank.Crystals Settling to Bottom of Tank Clogged Line to Reclaimed Boric Acid Storage Tank.Mixture Mod Should Correct Failures ML19210A2211975-10-10010 October 1975 Abnormal Occurrence 75-37:on 751010,during Transfer of Boric Acid from Storage Tank to Reclaim Tank,Blockage Noticed in Outlet Line.Caused by Boric Acid Crystals Settling to Drain Due to Improper Mixture ML19210A2241975-10-0808 October 1975 Abnormal Occurrence 50-289/75-34:on 750928,inoperative Hydraulic Shock Suppressor Threatened Function of Engineered Safety Feature.Low Fluid Level in Snubber Caused Failure. All Other Snubbers Checked Satisfactorily ML19322A4371975-09-30030 September 1975 Abnormal Occurrence 75-34 Re Disconnected Hydraulic Snubber within Reactor Bldg Secondary Shield.Investigation of Circumstances Incomplete.Snubber Replaced During Ongoing Seal Replacement Program ML19210A2461975-09-26026 September 1975 Abnormal Occurrence 50-289/75-31:on 750917,core Flood Tank Water Level Below Tech Specs Requirements.Caused by Incorrect Reading on Lower Reading Channel CF2-LT3.Channel Will Now Be Monitored & Personnel Informed on Procedures ML19210A2411975-09-26026 September 1975 Abnormal Occurrence 50-289/75-33:on 750917,de-ice Makeup Valve NR-V-4A Failed in Open Position.Failure Caused by High Resistance Contact in Closing Control Circuit Not Fully Energizing.All Control Contacts to Be Checked & Cleaned ML19210A2391975-09-26026 September 1975 Abnormal Occurrence 50-289/75-32:on 750918,incorrect Open Position of Air Supply Valves PP-V-47 & 179 Could Have Prevented Proper Functioning of Door Seals in Event of Emergency Safeguards Actuation.Jj Colitz 750919 Ltr Encl ML19210A2451975-09-19019 September 1975 Abnormal Occurrence 75-33 Re Failure of de-ice Makeup Valve NR-V-4A to Close Using Control Room Remote Pushbutton.Caused by High Resistance Contact in Closing Control Circuit. Contact Cleaned,Tested & Returned to Svc ML19322A4361975-09-18018 September 1975 Abnormal Occurrence 75-31 Re Low Borated Water Level in Core Flood Tank B.Caused by Improper Level Channel Transmitter LT3 Readout.Transmitter Adjusted ML19210A1791975-09-0505 September 1975 Abnormal Occurrence 50-289/75-29:on 750827,reactor Bldg Purge Supply Valve AH-V-1D Failed to Close Prior to Engineered Safeguards Test.Caused by Corroded Robotarm Actuator.Robotarm Actuator Lubricated ML19210A2251975-09-0505 September 1975 Abnormal Occurrence 50-289/75-30:on 750827,valve CF-V-2B of Core Flood Tank B Sample Line Isolation Failed to Close Upon Receipt of Engineered Safeguards Actuation Signal.Caused by Valve Binding Against Valve Stem ML19210A1811975-09-0202 September 1975 Abnormal Occurrence 50-289/75-28:on 750823,MS-V-13A Valve Turbine Drive Emergency Feed Pump Failed to Remain Open. Caused by Control Circuit Pressure Switch Failure,Due Possibly to High Ambient Temp ML19210A1871975-08-29029 August 1975 Abnormal Occurrence 50-289/25-27:on 750821,crack & Leak Found in Auxiliary Makeup Pump a Suction Vent.Caused by Fatigue Due to Vibration.Cracks Repaired & Hydrostatically Tested.Failed Pipe Section Replaced ML19322A4351975-08-28028 August 1975 Abnormal Occurrence 75-30:on 750827,core Flood Tank B Sample Line Isolation Valve CF-V2B Failed to Close Following Engineered Safeguards Signal.Valve Manually Closed Using Handwheel ML19210A1861975-08-27027 August 1975 Abnormal Occurrence 75-29:on 750827,reactor Bldg Supply Valve AH-V-1D Failed to Fully Close.Investigation Into Cause Underway ML19210A1841975-08-23023 August 1975 Abnormal Occurrence 75-28:on 750820,during Test of Turbine Drive Emergency Feed Pump,Associated Valve Failed to Remain Open.Caused by Failed Pressure Switch ML19210A1901975-08-21021 August 1975 Abnormal Occurrence 75-27 on 750821:leaks Found in Socket Weld Joint at Makeup Pump a & Suction Line Connection W/Pump Suction Header.Cause of Problem Under Investigation ML19210A1941975-08-0101 August 1975 Abnormal Occurrence 50-289/75-26:on 750724,high Reactor Coolant Pressure Trip Set Points Less Conservative than Tech Specs.Caused by Calibr Drift.Specs Will Be Changed to Account for Instrument Error ML19210A1951975-07-31031 July 1975 Abnormal Occurrence 50-289/75-25:on 750721,failure of Diesel Generator a Frequency Relay to Actuate,Threatening Nonperformance of Diesel Generator.Cause Presently Unknown ML19210A2001975-07-25025 July 1975 Abnormal Occurrence 50-289/75-23:on 750716,auxiliary Relay to Generator 1B Failed to Energize on Demand.Caused by Mfg Defect.Failed Relay Replaced & Remaining Relays Inspected ML19210A2071975-07-25025 July 1975 Abnormal Occurrence 50-289/75-24:on 750716,during Removal of River Water Pump NR-P1B from Svc,Discharge Valve Failed to Close.Caused by Open Phase on Winding Due to Severe Heat Resulting in Single Phasing of Other Windings ML19210A1991975-07-22022 July 1975 Abnormal Occurrence 75-25:on 750722,three Frequency Relays to Steam Generator a Found in Dropped Out State.Relays Replaced & Returned to Svc.Cause of Failure Yet to Be Determined ML19210A2171975-07-21021 July 1975 Abnormal Occurrence 50-289/75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump Suction Vent Line MU-PIA Leading to Valve MU-V156A.Caused by Improper Spacing Between Moving Anchor & First Pipe Restraint ML19210A2051975-07-18018 July 1975 Abnormal Occurrence 75-23:on 750716,one of Three Auxiliary Relays of Diesel Generator 1B Breaker G11-02 Failed. Remaining Relays Tested Satisfactorily.Cause of Failure Under Investigation ML19210A2121975-07-18018 July 1975 Abnormal Occurrence 75-24:on 750716,river Water Pump Discharge Valve Failed Due to Low Valve Motor Winding Resistance & Winding Motor Overheating ML19210A2221975-07-11011 July 1975 Abnormal Occurrence 75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump a Suction Line Vent.Caused by Pump Vibration ML19210A2311975-07-0303 July 1975 Abnormal Occurrence 50-289/75-21:on 750625,coolant Temp Trip Bistable Channel C Failed to Trip During Test of Reactor Protection Sys.Caused by Defective Printed Circuit Board Solder Joint in Signal Converter ML19210A2371975-06-27027 June 1975 Abnormal Occurrence 50-289/75-19:on 750618,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Caused by Channel C Trip Setpoint Out of Calibr Due to Instrument Drift ML19210A2301975-06-27027 June 1975 Abnormal Occurrence 75-03:on 750626,noble Gas Released to Auxiliary Bldg.Probable Cause:Evaporator Malfunction While Filling Makeup Tank or Coolant Bleed Tank.No Tech Specs Exceeded ML19210A1621975-06-27027 June 1975 Abnormal Occurrence 50-289/75-18:on 750615,QA Documentation from Vendor Found Inadequate for Repaired Decay Heat River Water Pump Motor Shaft.Caused by Lack of Administrative Controls ML19210A2351975-06-25025 June 1975 Abnormal Occurrence 75-21:on 750625,reactor Protection Sys Channel C Failed During Surveillance Test.Caused by Coolant Temp Trip Bistable Failure to Trip Due to Component Failure in Signal Converter ML19210A1721975-06-25025 June 1975 Abnormal Occurrence 50-289/75-17:on 750615,reactor Bldg Purge Isolation Valve Failed Local Leak Rate Test.Caused by Improper Valve Adjustment Procedures & Matl Defects Not Allowing Long Term Retention of Adjustment ML19308A5371975-06-23023 June 1975 Abnormal Occurrence 75-20:on 750622,while Returning to Full Power Operation After Forced Power Reduction,Reactor Power Increased Above Power Level Cutoff Before Xenon Reactivity Approached Stability.Procedures Under Review ML19210A2431975-06-19019 June 1975 Abnormal Occurrence 75-19:on 750618,less Conservative Variable Low Reactor Coolant Sys Pressure Trip Setpoint for One Channel of Reactor Protection Sys Violated Tech Specs. Caused by Instrument Drift for Channel C Setpoint Calibr ML19210A1661975-06-17017 June 1975 Abnormal Occurrence 75-18:on 750615,repaired Motor Shaft to Decay Heat River Water Pump Not Returned W/Proper QA Documentation.Caused by Lack of Administrative Control ML19210A1751975-06-17017 June 1975 Abnormal Occurrence 75-17:on 750615,during Test of Reactor Bldg Purge Isolation Valve Local Leak Rate Test,Two Exhaust Valves Would Not Pressurize to Required Test Pressure.Caused by Valve AH-V1A Failing to Fully Close ML19210A1771975-06-16016 June 1975 Abnormal Occurrence 50-289/75-16:on 750605,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Specific Cause Not Established. Setpoints Will Be Checked to Assure Proper Calibr ML19291B5291975-06-13013 June 1975 Abnormal Occurrence 50-289/75-15:on 750605,pressure Transmitter Trip Setpoint of Reactor Protection Sys Channel B Tested Out of Calibr.Caused by Trip Setpoint Calibr Drift ML19210A1801975-06-0606 June 1975 Abnormal Occurrence 75-16:improper Trip Setpoints on Variable Low Reactor Coolant Sys Pressure Sys Violated Tech Specs 1976-02-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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METROPOLITAN EDISON COMPANY eoTr cr= ice eox 542 R E A DIN G. PEY:S V A'4I4 I M: TELEPHO'!E
- 5 - 920-2001 February 3,1975 GQL 0717 Director Directorate of licensing ...
.2 les.- %g;1.: r;- Oc =i:; . .-
Washington, D. C.
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Dear Sir:
Operating license DP3-50 Decket #50-239 In accordan e .rith the Technical Specifications for c'tr Three Mile Island I;uclear Station, Unit 1, ve re reporting the following abnor al occurrence:
, (1) Report !!urber: A0 SC-239/'*5-CL (2a) Report Date:
(2b) Occurrence Date: Jerue / 23-2L, 1975 (3) Facility: Three Mile ::.' end ;-2 clear Generating Station, Unit 1 (L) Identificaticn of Cccur ence:
Title:
Unplanned Fadicactive Pelease, Caused by an Inadvertent Less of the Pe:lai e.' 30r10 Acid Tank icep Seal Type: M abacr:al ecourrence as defined by the Technical Specifica-tiens, paragraph 1.c2., in that the Unplanned Radioactive Pelease, Caused by the Inaivertent Loss of the Reclaited 3cric Acid Tank 1:00 Se11, vas in an a .o':nt vhich was of significance with respect tc -= '4 ' s prescribed in the Technical Specifi-caticns, Appenii:c 3, pn. a;;raph 2.3.2.a.
(5) Conditi:ns Pricr to Oc:urrence: rne reacter va: in a hot standby cendition with majer plan: p1rameter: as fclievs:
Pover: Care: 1.1
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AC 75-OL 2 RC Flow: 133 x 1C5 lb/hr RC Pressure: 2155 psig RC Temp.: 5350F oc x<
PRZR Level: 210 in. D D n D)rorH,o w l' PR2R Tc=p.
oaJ bp ihY!/\ ._,
65007 (6) Description of Cecurrence:
The pressurizer spray valve (?C-71) was bachaeated to allev replacement of its li=itorque c; era cr. The preasuri:er spray bicek valve (RC-V3) was, therefore, closed and was to be operated only if required to control reacter coolant syste= pressure. When the bicek valve (RC-V3) vas closed, valve stem leak o f to the vent header in the Reacter Building increased to apprcxi=ately 10 gp=. This increased valve stem leak off caused an overpressure condition in the vent header nitrogen cover gas which blankets the R.C. Drain Tank and "A" Peelal=ed Beric Acid Tank, as well as other tanks within the Waste Disposal System. This overpressure in the reclai=ed Ecric Acid Tank ecver gas caused the water loss fro = the tank overflev lecp seal and the subsequent release of radioactive cover gas to the Auxiliary Euilding Ventilation
. System. The Auxiliary Building 'lentilation Systes subsequently discharged the released radicactive cover gas through the statien vent to the at=csphere.
The "A" Reclai=ed Scric Acid Tank Leop Seal was refilled to ter=i-nate the gas release frc= the vent header, the Limitorque operater was replaced, RC-71 was returned to its ner=al shut cendition,1:d the motor operated pressurizer spray block valve (RC-V3) was back-seated to stop the valve ste= leak off. As a result , the source of the unplanned gas release was tenninated.
(7) It is believed that the appt ent cause of the inadvertent loss of the Reclaimed Ecric Acid Tank Loop Seal, and resultant unplanned radioactive release, =ay be due to inadequate design of the nitregen cover gas syste= and/or related syste=s , in that if the syste=(s) would have had sufficient capacity to handle the valve stem leak-off, the occurrence vould not have ha;pened.
(8) Analysis of Occurrence:
~
Analysis of statien vent radiation e';1uent recorder charts and Itcal air sa=ples frc= the statien vent indicate that 60 curies of predominately Ze-133 (865) were rele1 sed with a naximum release rate of 1.26 x 105 y3/sec. The average release rate ocep the.three hour and 37 =inute duratien of the release was 1.65 x 10" '!3/sec.
The 2h hcur average concentraticn in the affected area cf the 1482 166
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an incident re;;rtable ir se::riance vi:5 1C : ~~s.-03 (b) (2),
and additional ir.f:r:151:n vil_ ta f:rva ia' ' - a --"-d anc e vi h 10 CT? 20.L 5 (s). The iver ge :0 cen:r2tien is based on a
=essured 1200 CFM air fl:v thr ufa --a ' a-as cf the relesse.
Calculated concentrati::s ** '-a -a a=- devnvini unrestricted area, basa-1 cn a dilutien f t:: r of y/Q = 7.6 x lo-5 sec/: 13 are 2.6 x 10-5 uCi/=1 fer the 'G tinute naxi=um sni 3.Lh x 10-7 uC1/21 for the three hour and 37 minute durttien of the release.
No statien personnel vere in the 1res of the release, th-*efere no exposures cccur ei iu-ing the pesS. times cf the release. +w.
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release were dresse; in protec:;te 21.:ning ini 2.11-eu -a; breathing apparatus. Oositetric levices vern by these individus1s indicated only slight exposures (< 15 tres) .
Based on the above discussion, it has been determined that the health and safety of no indiviinal was endangered as a result of this c.ccurrence.
(9) Corrective Action:
As has been described above, irrediate corrective actions consisted of refilling the affected icop seal, restering FC-V1 to its normal shut cendition, and terninsting the scurce of the release by back-seating EC-V3 open.
The Plant Operations ?eview Cctrittee met shortly af ter the cecurrence, approved the inmediate corrective actions, and a a 1cng tern pre-ventative action recc neniei to the Statien Superintendent that an evaluati:n be conducted of the nitrogen cover gas cystem, and related systems, te deter:ine if there is a design inadequaey, and/cr cpera-ticnal procedural insdequacy, that could have caused this occurrence, and if so, what ein be done to prevent it frc happening again.
D Station Superintendent concurred with PCRC's findings , a censultant has been contracted, and the investigation is in pregress.
(10) Failure Data:
Nct applicable.
Sincerely, 9gned-R. C. ARNOLD R. C. Arnold .
' lice President RCA:DMG:eg
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Price Movers Cc==ittee J. J. Colit:
- Edison Electric Institute T. M. Cri== ins 90 Park Avenue 1 s. nelicate - 3es Iev York,::Y 10016 D. ::. Grac#
J. G. Herbein R. L'. Eevard (2)
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- 1. L. La.r/er J. P. C'Hani:n - Chairman, PCEO C:'I 1 J. F. Peters J. R. Thorpe - Chairman, GCR3 D'I 1
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1482 168
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