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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 ML20195G9901999-06-0909 June 1999 Safety Evaluation Supporting Amend 227 to License DPR-49 ML20206N7551999-05-13013 May 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves ML20207G0251999-03-0303 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety- Related MOVs at Duane Arnold & That Licensee Adequately Addressed Actions Requested in GL 96-05 ML20202B4311999-01-26026 January 1999 Safety Evaluation Accepting Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr ML20202B3851999-01-26026 January 1999 Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues.Ampacity Derating Analysis Results Acceptable ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant ML20236W0021998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief NDE-R020 Re Third 10-yr ISI Interval of Plant,Per 10CFR50.55a(a)(3(i) ML20216J9171998-04-16016 April 1998 Safety Evaluation Accepting Relief Request MC-R001 for First 10-yr Interval of Containment Insp Program Per 10CFR50.55a (a)(3)(ii),per 971219 Request ML20217K7251998-04-16016 April 1998 Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp ML20217H8831998-04-0101 April 1998 Safety Evaluation Supporting Request for Relief for Third ISI Program ML20217K0471998-04-0101 April 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request NDE-R004 for Plant Third 10-yr ISI Interval,Based on Finding That Compliance W/Code Would Result in Hardship W/O Compensating Increase in Level of Quality & Safety ML20217F8841998-03-23023 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Program Plan Requests for Relief for Plant ML20199J6841997-11-21021 November 1997 SER Approving Relief Requests to Second 10-year Inservice Inspection Interval for Duane Arnold Energy Center ML20140F0121997-06-0606 June 1997 Safety Evaluation Authorizing Proposed Alternatives Contained in Relief Requests HT-014,NDE-019 & NDE-020 ML20140A7091997-05-29029 May 1997 Safety Evaluation Accepting Relief Requests & Action Item Responses for IST Program for Plant ML20141E1811997-05-19019 May 1997 Safety Evaluation Accepting Proposed EAL Changes for DAEC Consistent W/Guidance in NUMARC/NESP-007 ML20133M2921997-01-15015 January 1997 Safety Evaluation of Third Ten Year Interval Inservice Insp Program Plan Request to Use Code N-535 Ies Utilities Inc, Central Iowa Power Cooperative,Corn Belt Power Cooperative, Duane Arnold Energy Center ML20149L8741996-11-12012 November 1996 Safety Evaluation for Ies Utilities of IPE in Response to GL-88-20 & Associated Suppls for License DPR-49 ML20057D6031993-09-24024 September 1993 Safety Evaluation Granting Request for Relief from Certain Exam Requirement of Section XI of ASME Code.Request for Relief RR-001,denied ML20057C9031993-09-24024 September 1993 Safety Evaluation Granting Requested Relief from ASME Code Repair Requirements for Plant D Outboard MSIV ML20128K5231993-02-11011 February 1993 Safety Evaluation Supporting Licensee Response to Staff SE Item Numbers for Pump & Valve IST Program to License DPR-49 ML20198E3191992-11-25025 November 1992 SER Accepting Licensee Response to Suppl 1 to GL-87-02, Committing to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance ML20214N8121986-09-11011 September 1986 Safety Evaluation Accepting Mods to Emergency Diesel Generator Load Sequencer Described in .Mods Assure That Loading of ECCS Pump Motors on Emergency Diesel Generators Will Be Sequenced Per Plant Design Basis 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary NG-99-1415, Monthly Operating Rept for Sept 1999 for Daec.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Daec.With ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 NG-99-1226, Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With NG-99-1115, Monthly Operating Rept for July 1999 for Daec.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Daec.With NG-99-0963, Monthly Operating Rept for June 1999 for Daec.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Daec.With ML20195G9901999-06-0909 June 1999 Safety Evaluation Supporting Amend 227 to License DPR-49 NG-99-0835, Monthly Operating Rept for May 1999 for Daec.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Daec.With ML20206N7551999-05-13013 May 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves NG-99-0682, Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With NG-99-0530, Monthly Operating Rept for Mar 1999 for Daec.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Daec.With ML20207G0251999-03-0303 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety- Related MOVs at Duane Arnold & That Licensee Adequately Addressed Actions Requested in GL 96-05 NG-99-0330, Monthly Operating Rept for Feb 1999 for Daec.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Daec.With ML20202B4311999-01-26026 January 1999 Safety Evaluation Accepting Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr ML20202B3851999-01-26026 January 1999 Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues.Ampacity Derating Analysis Results Acceptable NG-99-0020, Monthly Operating Rept for Dec 1998 for Daec.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Daec.With ML20206N3211998-12-0707 December 1998 Final Part 21 Rept Re Piston Failure of MSIV Actuator at Daec.Rept Indicates That No Reportable Defect Exists,Per 10CFR21 NG-98-2010, Monthly Operating Rept for Nov 1998 for Daec.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Daec.With ML20196F9571998-11-24024 November 1998 Rev 20 to QA Program Description,Ufsar 17.2 for Daec NG-98-1875, Monthly Operating Rept for Oct 1998 for Daec.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Daec.With NG-98-1767, Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with1998-09-30030 September 1998 Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with NG-98-1717, Monthly Operating Rept for Sept 1998 for Daec.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Daec.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20153B4141998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DAEC NG-98-1389, Monthly Operating Rept for July 1998 for DAEC1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DAEC ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant ML20236W0021998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief NDE-R020 Re Third 10-yr ISI Interval of Plant,Per 10CFR50.55a(a)(3(i) ML20236S2541998-07-14014 July 1998 Special Rept 98-01:on 980629,diesel-driven Fire Pump Was Inoperable for Greater than Seven Days.Caused by Sheared Off Tie Rods on Accessory Drive End of Engine.Evaluated Condition,Procured Parts & Replaced Tie Rods ML20236R3251998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DAEC ML20249B5171998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DAEC ML20247P5651998-05-18018 May 1998 Part 21 Rept Re Model SA-A101 MSIV A' Actuator Showing Evidence of Internal Leakage,In Both Directions Past Pneumatic Piston.Situation Being Reviewed to Determine If Failure Could Pose Substantial Safety Hazard ML20247K1881998-05-0808 May 1998 Rev 0 to Cycle 16 COLR, for May 1998 ML20247H9381998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for DAEC ML20217K7251998-04-16016 April 1998 Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp ML20216J9171998-04-16016 April 1998 Safety Evaluation Accepting Relief Request MC-R001 for First 10-yr Interval of Containment Insp Program Per 10CFR50.55a (a)(3)(ii),per 971219 Request ML20217K0471998-04-0101 April 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request NDE-R004 for Plant Third 10-yr ISI Interval,Based on Finding That Compliance W/Code Would Result in Hardship W/O Compensating Increase in Level of Quality & Safety ML20217H8831998-04-0101 April 1998 Safety Evaluation Supporting Request for Relief for Third ISI Program ML20216F6791998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for DAEC NG-98-0650, Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center ML20217F8841998-03-23023 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Program Plan Requests for Relief for Plant NG-98-0398, Monthly Operating Rept for Feb 1998 for DAEC1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for DAEC ML20199L3481998-01-31031 January 1998 Rev 0 to Duane Arnold Energy Ctr Emergency Action Level (EAL) Technical Basis Document NG-98-0252, Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center ML20249B3391997-12-31031 December 1997 Central Iowa Power Coopertive 1997 Annual Rept ML20249B3351997-12-31031 December 1997 1997 Annual Rept for Corn Belt Power Cooperative ML20249B3331997-12-31031 December 1997 1997 Annual Rept for Alliant Corporation NG-98-0017, Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center1997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center NG-97-2118, Monthly Operating Rept for Nov 1997 for DAEC1997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DAEC ML20199J6841997-11-21021 November 1997 SER Approving Relief Requests to Second 10-year Inservice Inspection Interval for Duane Arnold Energy Center NG-97-1959, Monthly Operating Rept for Oct 1997 for DAEC1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for DAEC 1999-09-30
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',k UNITED STATES 4 [4 g 5j g NUCLEAR REGULATORY ;OMMISSION WASHINGTON, D. C. 20555
\...../ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ECCS LOAD SEQUENCER MODIFICATION IOWA ELECTRIC LIGHT AND POWER COMPANY -
DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331
1.0 INTRODUCTION
On August 22, 1985, with the reactor in normal power operation, the licensee determined that the loss of one of the two transformers that supply vital (emergency) power buses from offsite power, concurrent with a LOCA,-could defeat-the load sequencing logic of the emergency diesel generators. The effect would have been that a core spray and two residual heat removal pumps per diesel would have been on demand simultaneously loaded onto the diesel rather than in intended sequence of five second intervals. The essential bus loads, in this potential situation, could have caused the diesel generator to trip during loading. Following this determination on August 22, 1985, both diesel generators were declared inoperable. In the interim, keylock test switches were placed in the
" test" position in the RHR and the core spray pump start logics to ensure that bus vital loads always sequence upon bus transfer. The licensee was asked by the staff to find a permanent solution to the problem of load sequencing onto the diesel generators during emergency conditions. By letter dated May 9, 1986, the licensee submitted the information for a permanent solution.
2.0 EVALUATION In the original design, a loss of offsite power (LOOP) signal is initiated only if the output voltage of both the standby and startup transformers drops to 65% or less of nominal voltage or if a degraded undervoltage condition exists on the emergency bus. Therefore, if the emergency loads were powered by the standby transformer and a loss of coolant accident (LOCA) occurred at the same time as the standby transformer failed, the output voltage of the startup transformer (which was still in operation) would have prevented from sending the loss of offsite power signal to the pump start circuitry. This would have caused all core spray and RHR pumps to load their respective emergency buses sirhultaneously and, thereby, stalling the diesel generators due to excessive load resulting from simultaneous motor starting currents. In the modified design, the relays used in the automatic start circuitry of core spray pump and RHR pumps on loss of auxiliary power have been disconnected to bypass the automatic instantaneous start feature on the pumps and to direct the pump start signal to the appropriate time delay pickup relay. As a result, the pumps will sequence onto their respective buses in their proper order.
0609170036 060911 PDR ADOCK 03000331 P pga
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3.0 CONCLUSION
Based on the above evaluation, the staff concludes that in the modified design, the core spray and the two RHR pumps will sequence to the emergency buses in the proper order, following a LOCA signal regardless of the status of offsite power and thereby, ensure that the diesel generators are loaded in accordance with plant design basis. Therefore, the licensee's modifications are acceptable.
Principal Contributor:
N. Trehan Dated: September 11, 1986
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