ML20084J321
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| ML20084J321 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/11/1973 |
| From: | Stephenson B COMMONWEALTH EDISON CO. |
| To: | Giambusso A US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084J323 | List: |
| References | |
| BBS-73-89, NUDOCS 8305120541 | |
| Download: ML20084J321 (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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Post Ofhce Box 216
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h, g, BBS-73-89 ,z May 11, 1973 -
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c M -s y x >? g Mr. Ange'lo Giambusso N{V' #t s g Deputy Director for Reactor Projects Directorate of Licensing
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, 7._,4 Q g.-@ f U.S. Atomic Energy Commission Washington, D. C. 20545 Re ference: Quad-Cities Nuclear Power Station Docket Numbers 50-254 and 50-265 DPR-29 and 30, Appendix B, ,
Section 1.1 and 3 1.A.
Dear Mr. Gianbusso:
The purpose of this letter in to report chlorine residual concentrations in the discharge bay in excess of the limit-ing conditions for operation in the nonradiological technical specifications . The limit of 0.1 ppm free and combined chlorine in the discharre bay was exceeded on several occassions since my last report on this subject dated April 14, 1073 On April 13, 1973, station personnel sampled the discharge bay. The total chlorine residual registered as high as 0.65 ppm with 496 gallons of sodium hypochlorite being injected. On April 15, 1973, the unit two sodium hypo-chlorite system and condensers were taken out of service until April 27, 1973 for a planned spring outage. On April 18, 1973, the discharge bay was again sampled during the injection of 236 gallons of sodium hypochlorite to the unit one condenser. The maximum free and total chlorine levels detected were 1.0 ppm. On April 21, 1973, the unit one hypochlorite injection system was taken out of service until May 8,1973, for a planned spring outage.
Throughout this reporting period the system was operated three times a day with the flow manually set at 10 gallons per minute. During the April outage, both unit one and unit Jg two condenser tubes were cleaned. An attempt is now being
-No taken to determine a minimum injection rate required to maintain tubo cleanliness based on river demand and unit, g performance data.- , f ,, (,5 0
Ver t rulgy ou r,a','- ,$U ' y?,$p [ ["[I W e
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