ML20084L090
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| ML20084L090 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/15/1974 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084L085 | List: |
| References | |
| NUDOCS 8305200234 | |
| Download: ML20084L090 (1) | |
Similar Documents at Quad Cities | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20217G7821997-07-22022 July 1997
[Table view]Special Rept:On 970227,ECCS Sys Was Actuated & Injected Water in Rcs.Declared HPCI Subsystem Operable Following Restoration of Subsystem to Normal Standby Lineup ML20097D4661992-05-27027 May 1992 Special Rept,Reflecting Quad-Cities Nuclear Power Station, Unit 2 Summary Status of Fuel Performance at End of Cycle 11. No Sipping Performed on Reload Fuel Assemblies at End of Cycle 11 ML20066J6331991-01-31031 January 1991 Forwards Summary Status of Fuel Performance for End of Cycle 11 ML20207P1881987-01-0606 January 1987 Special Rept:Summarizes Status of Fuel Performance as of End of Cycle 8.Of 2031 Assemblies used,289 Determined to Have Failed & Discharged as Leaker Assemblies.Aug 1986 Sipping Tests Showed No Indication of Assembly Failure ML20082P6541983-12-0505 December 1983 Telecopy RO 50-83/20-01T:on 831202,review of Ultrasonic Test Data Obtained During Current Refuel Outage Revealed Circumferential Linear Indication in Heat Affected Zone of Weld 02B-S9.Further Info Expected within 14 Days ML20078J8531983-10-12012 October 1983 Telecopy Ro:On 831011,during Performance of Ultrasonic Insp of Cleanup Sys Piping,Crack Indication Discovered in Heat Affected Zone of Weld 12S-S27 of Line 2-1202-6A.Further Info to Be Provided within 14 Days ML20084S1401977-05-13013 May 1977 Ro:On 770512,unit Experienced Sudden Turbine Control Valve Opening Resulting in Feedwater Flow Increase & Reactor Scram from APRM flux.Short-term Reactivity Increase Corresponding to Reactor Period of Less than 5s Experienced ML20084S1531977-05-0909 May 1977 Ro:On 770507,station Experienced Momentary Short Period of Less than 5s During Shutdown Margin Demonstration.Similar Experience Occurred on 770504.Addl Info Will Be Submitted in RO 50-254/77-23 ML20084S1901977-02-17017 February 1977 Telecopy Ro:On 770217,info Received by Station Indicated That MAPLHGR Limit Curves Given by Tech Specs Shall Be Additionally Lowered.Reduction Resulted from Review of ECCS Analysis.Maplhgr Curves Lowered Effective 770217 ML20084S2041977-01-18018 January 1977 Telecopy Ro:On 770118,info Received by Station Indicated That MAPLHGR Limit Curves Shall Be Lowered.Reduction Resulted from Review of ECCS Analysis.Curves Lowered ML20084S3501977-01-0404 January 1977 RO-50-254/76-37:on 761205,limit for Having No More than 2 Ci Activity in Radwaste Tank Farm in 24h Exceeded. Caused by Deterioration of Effectiveness of Radwaste Sys to Perform as Designed.Radwaste Sys Being Updated ML20084S3551976-12-30030 December 1976 RO 50-254/76-36:on 761202,cooling Water Suction Header Common to Both RHR Containment Cooling Loop 1A & Diesel Generator 1 Cooling Water Pump Airlocked.Caused by Procedure Inadequacy.Maint Procedures Will Be Revised ML20084S2861976-12-28028 December 1976 RO 50-254/76-38:on 761215,GE Notified Util That NRC Discovered Errors in Code Inputs to ECCS App K Analysis, Caused by GE Incorrectly Applying Data for ECCS App K Analysis.Maplhgr Curves Reduced by 4% ML20084S3391976-12-16016 December 1976 Ro:On 761215,preliminary Info Received by Station Indicated That MAPLHGR Curves Should Be Lowered by 4%.Change Resulted from Review of ECCS Analysis.Curves Lowered ML20084S3611976-12-16016 December 1976 RO 50-254/76-35:on 761203,discovered Discrepancy Between Tech Spec & Nedo 20360 Rod Worth Minimizer Operable Rated Power.Orders Written in Daily Order Book Requiring Rod Worth Minimizer Operability Below 20% ML20084S3701976-12-0303 December 1976 Ro:On 761203,info Received Indicated That Rod Worth Minimizer (RWM) Operability Requirements Should Be Changed from 10% to Below 20% Rated Power.Caused by Review of Rod Drop Accident Analysis ML20084S3791976-11-22022 November 1976 Updated RO 50-254/76-33:on 761029,repairs to RCIC Pump Consisted of Rebuilding Pump Casing & Installing New Rotary Element.Pump Reassembled & Repairs Completed by 761111.Welds on Piping Acceptable ML20084S3771976-11-12012 November 1976 RO 50-254.76-34-on 761104,electromatic Relief Valves 1-203-3C & 1-203-3E Failed to Open When Actuated from Control Room.Caused by Excessive Steam Leakage Into Area Below Valve Disc.Investigation in Progress W/Manufacturer ML20084S3941976-11-10010 November 1976 RO 50-254/76-33:on 761029,while Performing RCIC Sys Pump Operability Surveillance,Discovered That Pump Could Not Achieve Flow & Pressure Required.Caused by Two of Five Stages Being Severely Damaged.Pump Being Rebuilt ML20084S5421976-10-30030 October 1976 Updated RO 50-254/76-26:on 760803,rod Worth Minimizer Not Operable for Withdrawal of First Twelve Control Rods to Fully Withdrawn Position While in Startup Mode.Caused by Burned Out Wire Runs on Relay Board.Software Modified ML20084S4031976-10-13013 October 1976 RO 50-254/76-32:on 761001,main Chimney Monitoring Sys & Reactor Bldg Vent Sample Sys Not Functioning Properly.On 760919,flexible Sample Hose Wrapped W/Tape to Stop Possible Leak.Caused by Failure of Flexible Suction Hose ML20084S5641976-10-0404 October 1976 Supplemental RO 50-254/76-25:electrical Nitrogen Vaporizers Installed on Nitrogen Makeup Sys.Installation Should Prevent Future Recurrences ML20084S4761976-10-0404 October 1976 RO 50-254/76-31:on 760920,station Informed by GE of Error in Reload 2 Licensing Submittal in Determining Max Change in Critical Power Ratio Due to Abnormal Operating Transient. Caused by Incorrect Analysis in Preparing Submittal ML20084S4831976-09-21021 September 1976 RO Re Notification by GE of Oversight in Reload 2 Licensing Submittal Leading to Possible Nonconservative Operation During Cycle 3.Work Request to Lower Rod Block Monitor Line to 10% at Full Flow Initiated ML20084S5031976-09-0909 September 1976 RO 50-254/76-29:on 760809,surveillance of Primary Containment Oxygen Concentration Revealed Increase in Concentration from 4.2 to 4.8%.Caused by Instrument Drift. Oxygen Analyzer Recalibr ML20084S5151976-09-0707 September 1976 RO 50-254/76-28:on 760809,position Indication Lost on Reactor Water Cleanup Sys Isolation Valve Mo 1-1201-2.Caused by Relay 595-125 Shorting Out & Burning Up Control Transformer.Relay & Transformer Replaced ML20084S5781976-08-26026 August 1976 RO 50-254/76-24:on 760727,reactor Bldg to Suppression Chamber Vacuum Breaker Pressure Switch PS-1-1622B Tripped at 0.536 Psid.Caused by Instrument Setpoint Drift.Switch Recalibr ML20084S5241976-08-19019 August 1976 RO 50-254/76-27:on 760806,ECCS Analysis Performed by GE for BWR-3 Type Plant Resulted in Calculated Peak Clad Temp Greater than 2,200 F for Reduced Core Flows.Caused by Severity of Conservatisms Associated W/Using App K ML20084S5511976-08-16016 August 1976 RO 50-254/76-26:on 760803,rod Worth Minimizer Multiple Output Distributor Error Detected.Caused by Burned Out Wire Runs on Relay Board.Board Repaired & Hardware & Software Mods & Procedural Changes Being Considered ML20084P7411976-06-23023 June 1976 Telecopy Ro:Initial Swipe Survey of Nuclear Fuel Svcs NFS-4 Cask Indicated Three of 38 Tests Exceeded Limits ML20084P7551976-06-17017 June 1976 Telecopy Ro:On 760617,HPCI Sys Motor Speed Changer Failed to Come Off Low Speed Stop During Monthly Surveillance.Caused by Motor Speed Changer Linkage Being Bound.Linkage Freed ML20084S4131976-03-30030 March 1976 Telecopy Ro:On 760330,suppression Chamber Water Level Instrumentation Found Miscalibrated.Suppression Chamber Water Level Immediately Returned to Normal.Addl Info Will Be Submitted in RO 50-265/76-04 within 14 Days ML20084Q1751976-03-26026 March 1976 Telecopy Ro:On 760326,chemical Waste Sample Tank Discharged to River at Rate in Excess of Limits ML20084S4151976-01-0909 January 1976 Telecopy Ro:On 760108,while in Cold Shutdown,Crack Indications Found on a & B Loops in valve-to-pipe Junctions on Sides of Bypass Valve That Cannot Be Isolated & in Heated Zones ML20084S5091976-01-0505 January 1976 RO 50-254/76-1:on 760105,w/unit in Cold Shutdown for Refueling,Pinhole Leak Found in Fillet Weld of 3/4 Inch Drain Line.Caused by Degradation of Reactor Coolant Primary Boundary.Work Request Being Issued ML20084S5311975-12-31031 December 1975 RO 50-265/75-47:on 751231,w/unit Operating at 805 Mwe, Reactor Core Isolation Cooling (RCIC) Trip Throttle Valve Could Not Be Reset Following Successful Monthly Surveillance Functional Testing.Hpci Tested & Found Operable ML20084U2081975-02-25025 February 1975 Ro:On 750212,following Verification of Reactor core,mixed- Oxide Fuel Assembly Identification Number Stamped in Wrong Orientation Discovered.Caused by Mfg Error.Fuel Insp Procedure Changed to Verify Number Orientation as Correct ML20084U2121975-02-20020 February 1975 Ro:On 750212,during Core Spray Operational Hydrostatic Test, Water Observed Overflowing Reactor Bldg Floor Drain Sump 1B.Caused by Premature Actuation of Core Spray Discharge Header Relief Valves.Test Procedure Amended ML20085C9241974-11-15015 November 1974 Ro:On 741011,control Rod Drive N-11 Jammed Fully Inserted Past Position 00 & Would Not Withdraw After Increasing Drive Pressure.Caused by Broken Seals on Stop Piston.Drive N-11 Replaced ML20085C9181974-11-15015 November 1974 Ro:On 741017,during Removal of Faulty Intermediate Range Monitor 18 Detector,Detector Became Stuck in Shuttle Tube. Caused by Coupling Between Shuttle & Drive Tubes Overtightened.New Shuttle Tube Ordered ML20084K5181974-06-26026 June 1974 Telecopy RO Re Setpoint Drift of Standby Liquid Control a Relief Valve.Valve Reset & Tested ML20084K6451974-06-22022 June 1974 AO 50-265/74-12:on 740612,high Differential Pressure Noted Across Combined High Efficiency & Carbon Filters.Caused by Exhausted High Efficiency Prefilter.Original Carbon Filters, New Rough Prefilters & New Efficiency Prefilters Installed ML20084K5461974-06-19019 June 1974 Telecopy Ro:On 740619,water Leak Discovered at Pressure Test Connection & Feedwater Line.Caused by Cracked Weld at Weldolet Line.Repairs in Process ML20084K5541974-06-19019 June 1974 Telecopy Ro:On 740619,water Leak Discovered at Pressure Test Connection & Feedwater Line.Caused by Cracked Weld at Weldolet Line.Repairs in Process ML20084K5891974-06-14014 June 1974 Telecopy Ro:On 740613,level Switch LIS-2-263-72D Failed. Switch Lightly Pressed & Functioned Normally.New Switch Ordered ML20084K5941974-06-14014 June 1974 Telecopy Ro:On 740613,level Switch LIS-2-263-72D Failed. Switch Functioned Normally When Lightly Pressed.New Switch to Be Installed ML20084K6291974-06-13013 June 1974 Telecopy Ro:Level Switch Failed to Actuate Control Room Annunciator.Cause Under Investigation ML20084L0441974-06-10010 June 1974 Telecopy Ro:On 740609,high Water Conductivity Discovered in Reactor.Shutdown & Water Cleanup Initiated ML20084K8401974-06-10010 June 1974 Telecopy Ro:On 740610,feedwater Valve Failed.Caused by Wall Thickness Being Less than Design Min.Cleanup, Decontamination & Water Processing Initiated ML20084K8361974-06-10010 June 1974 Telecopy Ro:On 740610,feedwater Low Flow Valve Failed.Caused by Not Maintaining Min Wall Thickness.Radiation Released Not Above Normal Level.Decontamination,Cleanup & Water Processing Initiated 1997-07-22 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30 |
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REFERENCE:
QUAD-CITIES NUCLEAR POWER STATION UNIT 1, DOCKET N14 DER 50-254, DPR-29, APPENDIX A, SECTIONS 1 0A.4i 1 0 A. 5, 6 6 8 1. A, 34.A TABLE 3.7 1 ON MAY I 4, 1974, WITH UNIT 1 IN THE ' COLD SHUT DOWN CONDITION DURING THE REFUELING OUTAGE, SURVEILLANC E TESTING REVEALED THE FOLLCAING: 1. SBLC RELEASE VALVE l-1105A 0'ERATED AT 165D PSIG, THUS EXCEEDING TECHNICAL SPECIFICATIONS.
4 THE RELEASE VALVE WILL BE READJUSTED AND TESTED TO BE WITHIN SPEC IF IC ATI ONS . 2.
NITROGEN PURGE VALVE A0-1-16PI-55 REGUIRED 39 SECONDS TO CLOSE, THUS EXCEEDING TECHNICAL SPECIFICATION 3 7. D.1. 3.
DRYWELL PURGE VALVE A0-1-l60.1-21 REGUIRED 13 I/2 i ~ ' SECONDS CLOSING TIME,
' THUS EXCEEDING TECHNICAL SPECIFICATION
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THESE VALVES WILL BE REPAIRED AND RETESTED TO BE WITHIN
' SPEC IF I C AT I ONS . DETAILS OF THESE INCIDENTS WILL BE REPORTED i
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