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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 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 ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc 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 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted 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 ML20217J6131997-07-14014 July 1997 Part 21 Rept Re Incomplete Defined Changes Made to Standby DG W/Emd Diesel Engines by Mfg ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML20148B0181997-05-0202 May 1997 Part 21 Rept Re Failure of Plunger on Solenoid Number 1 to Return to de-actuated Position in Timely Manner When Solenoid Was de-energized.Caused by Plunger Moving While in Energized Condition.Added 'Noise' Test ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20134D8571996-10-28028 October 1996 Part 21 Rept Re Steam Isolation Valved Failed to Close within 3-5 Seconds Required by Ts.Caused by One Plunger from Solenoid Missed Machining Operation After Vitron Insert Pressed In.Solenoid Energized ML20095K3911995-12-21021 December 1995 Final Part 21 Rept 95-015 Re Bldg of Achor Darling Valves W/ Cavitation Trim.Plant Will Perform Monthly Testing of Running Loads on a Loop Valve Until Modified ML20078S1931994-12-21021 December 1994 Final Part 21 Rept Re Nonconservative Assumptions of Turbine Bypass Vot in Plant Transient Analyses for Unit 2.GE Analyses Determined That Deviation Created Potential Substantial Safety Hazard ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20059G3041993-10-22022 October 1993 Part 21 Rept Re Defective Dual Plate Check Valves W/Viton Seats Supplied by C & Valve Co Since 900928.Immediate Corrective Action Taken to Identify Locations of Defective Valves & Conduct Periodic Surveillance of Ccsw Pressure ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20127K6261993-01-12012 January 1993 Part 21 Rept Re Model Std 130 Differential Pressure Transmitters Manufactured by Honeywell in Accordance W/ Requirements of 10CFR21.21(a)(2) ML20072R6731991-03-27027 March 1991 Part 21 Rept Re Increased Air Leakage in Pathway Bellows Corp Bellows Assembly.Assembly Replaced by Parker-Metal Bellows Corp ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20212E5631986-12-19019 December 1986 Part 21 Rept Re Valve Problem.Houghto 620 Lubricant Attacks & Degrades Aluminum in Valves.Valves Have Been or Being Rebuilt ML20215D2371986-12-0909 December 1986 Part 21 Rept Re Environ Qualification of AMP Butt Splices in GE Drywell Penetrations.Splices Retested by Simulating Postulated LOCA & Failed Due to Excessive Leakage.Ge Contacted Re Repair of Splices ML20213F9661986-11-10010 November 1986 Part 21 Rept Re Failure of Battery inter-rack Connecting Cable Assembly Supplied by Gnb Batteries,Inc.Initially Reported on 861107.Battery Cables Replaced ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20141D8051986-04-0101 April 1986 Part 21 Rept Re Model 402 Series Level Control Used for safety-related Application Shipped W/O Torque Check. Customers Will Be Notified by 860428 & Requested to Perform Torque Check.List of Plants Using Component Encl ML20154K3611986-03-0505 March 1986 Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328 ML20133N4691985-08-0505 August 1985 Part 21 Rept Re Raychem Wcsf Shrink Sleeving for Sensor/ Connecting Assembly of Safety Relief Valve Monitoring Sys. Testing & Retesting in Progress.Sensor Installation Utilizing Shrink Sleeving Recommended ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC ML20117L5891985-05-14014 May 1985 Part 21 Rept Re Hatch Transfer Starters & Transfer Starter Assemblies.Evaluation of Implementation of QA Program Performed on 850429-0503.Results of Evaluation Verified Seismic Adequacy of Equipment ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20111C5431985-03-0404 March 1985 Part 21 Rept Re Degradation of 125-volt Dc Battery.Thirty Cells on Battery Show Corrosion Around Weld Between Plates & Internal Bus Bar.Gnb Batteries,Inc 58 Cell NCT-1344 Lead Calcium Battery Purchased to Replace Existing Battery ML20086U4251984-02-24024 February 1984 Followup Part 21 Rept Re Defective Mechanical Snubber Capstan Springs Supplied by Pacific Scientific.Affected Utils Listed.Purchasers Have Been Notified & Advised to Work Directly W/Pacific Scientific in Disposition ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20085E7651976-08-0505 August 1976 Final Deficiency Rept Re Incorrect Installation of Reactor Pressure Vessel (RPV) Seismic Stabilizer Plates.Initially Reported on 760513.Formal QA Program Developed & Implemented Since Pvs Stabilizer Assembly Installed ML20085K0671974-01-0404 January 1974 Final Deficiency Rept Re Control Logic of HPCI & RCIC Sys. Initially Reported on 731110.Four Addl Qualified High Reactor Water Level Switches Will Be Installed 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217A9931999-09-30030 September 1999 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 ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With 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 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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 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 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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 ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With 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 ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with 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 ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced 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 ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc 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 ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.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 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 ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With 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 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 ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.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-98-346, 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 1999-09-30
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GENERAL INFORMATION or OTHER EVENT NUMBER: 34119 LICENSEE: SIEMENS POWER CORP-NUCLEAR DIVISION NOTIFICATION DATE: 04/22/98 CITY: RICHLAND REGION: 4 NOTIFICATION TIME: 12:40 [ET)
COUNTY: BENTON STATE: WA EVENT DATE: 04/21/98 LICENSE #: SNM-1227 AGREEMENT: Y EVENT TIME: 12 : 00 [PDT]
DOCKET: LAST UPDATE DATE: 04/22/98 NOTIFICATIONS ELMO COLLINS, R4 RDO l NRC WOTIFIED BY: DON CURET JIM GAVULA, R3 RDO HQ OPS OFFICER: DICK JOLLIFFE VERN HODGE NRR EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION: 1 CCCC 21.21 UNSPECIFIED PARAGRAPH l EVENT TEXT 10CFR PART 21 REPORT - NONCONSERVATIVE PREDICTION OF MONITORED CORE MCPR -
SIEMENS POWER CORPORATION (SPC) PERSONNEL DETERMINED THAT ADDITIVE CONSTANTS USED IN MINIMUM CRITICAL POWER RATIO (MCPR) DETERMINATION FOR SIEMENS ATRIUM-9B FUEL BY THE CORE MONITORING SYSTEM WERE FOUND TO BE l NON-CONSERVATIVE (UP TO 7.6% BASED ON THE ORIGINAL ADDITIVE CONSTANTS).
ALSO SPC PERSONNEL DETERMINED THAT THE UNCERTAINLY IN THE ADDITIVE CONSTANT FOR THIS FUEL DESIGN WAS LARGER THAN PREVIOUSLY ESTIMATED. THE REVISED i UNCERTAINTY HAS THE POTENTIAL TO AFFECT THE MCPR SAFETi LIMIT.
SPC PERSONNEL NOTIFIED ALL SPC CUSTOMERS WITH ATRIUM-9B LEAD TEST ASSEMBLIES OR RELOAD QUANTITIES OF THE FUEL OF THE POSSIBLE NONCONSERVATIVE l PREDICTION OF THE MONITORED MCPR AT CONDITIONS WHERE A SEVERELY UP-SKEWED AXIAL POWER SHAPE COULD OCCUR.
PLANTS AFFECTED ARE DRESDEN UNIT 3 (CYCLE 15), QUAD CITIES UNIT 2
! (CYCLE 15) AND KUOSHENG UNITS 1 & 2.
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PAGE 10F 2 NRC FORM 361A U.S. NUCLEAR REGULATORY COMMISSION LICENSE NUMBER:
(11/04)
' FUEL CYCLE AND MATERIALS SNM-1227 EVENT NOTIFICATION WORKSHEET (NRC Docket No.
OgM 70-1257)
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NC UNDERSTN y NO STATE 7 X DID ALL SYSTEMS FUNCTON YES LOCALT y No( rs Deka)
OTHER GOVERNMENT AGENCIES 9 X ADDITONAL INFoRMATON YES X (attached)
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EVENT DESCR:PTlON tconanue on separate sheetitnecasanry) l See attached summary of defect related to the non-conservative credictinn nf l
monitored MCPR for core conditions at severe nn-skouma wi=1 -
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Date of report. Defect has been evaluated under Siemens Power cernermeinn Condition Report - CR 6508 dated Febmng 2's.144A. !
NAC FORM MtA(11/94)
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I NRC Operati6ns Center U.S. Nuclear Regulatory Commission Washington, D. C.
! Attachment to Siemens Power Corooration - Nuclear Division 10 CFR Part 21 Reoort (Fuel Cvele and Materials Event Notification Worksheet/NRC Form 361 A) of April 21.1998 10 CFR Part 21 Notifcation of Defect Relative to Non-Conservative Predletion of Monitored Core MCPR.
I Additive constants used in MCPR determination for Siemens ATRIUM *-98 fuel by the core monitoring system were found to be non-conservative. Also the uncertainty in the additive constant for this fuel design was determined to be larger than previously ,
estimated. The revised uncertainty has the potential to affect the MCPR safety limit I
However, an interim additive constant uncertainty larger than the value calculated using new CHF data, had been used in safety limit calculations. Because the monitored MCPR could be non-conservative (up to 7.6%) based on the original additive constants, the MCPR safety limit could have been exceeded during the limiting transient while operating with less than 7.6% MCPR margin and with a severely up skewed axial power shape in l
the limiting MCPR assembly.
SPC took immediate steps to determine the potential safety impact on plants operating with ATRIUM-98 fuel and completed an operability assessment on February 26,1998.
The assessment addressed the potentialimpact on both monitored MCPR and the MCPR operating limit. Where necessary, the operability assessment identified conserve ive compensatory actions to ensure that MCPR limits were adequate for ATRIUM-98 fuel. For operation with a positive axial offset (up-skewed power profile), restrictions on the Maximum Fraction of Limiting CPR (MFLCPR) were determined which ensure that adequate MCPR margin exists to cover the potential non-conservatism in ANFB. MFLCPR restrictions of up to 8% were calculated for plants using ATRIUM-98 fuel. For operation when the axial power offset is less than zero (down-skewed power profile), the ANFB correlation is conservative and no limitation on MFLCPR is required.
All SPC customers with ATRIUM-98 lead test assemblies or reload quantities of the fuel were notified of the possible non-conservative prediction of the monitored MCPR at conditions where a severely up-skewed axial power shape could occur.
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