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Category:GENERAL EXTERNAL TECHNICAL REPORTS
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[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power 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Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20197A9921997-12-15015 December 1997 Rev 0 to Efp,Unit 1 Fermi 1 Sar NRC-97-0131, Monthly Operating Rept for Nov 1997 for Fermi 21997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Fermi 2 ML20248H1151997-10-31031 October 1997 Rev 1 to Colr,Cycle 6 for Fermi 2 1999-09-30
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~ VP-86-0146-Page 17 of 23 HOPPER AND ASSOCIATES HA-10/86-532 ENGINEERS PRELIMINARY STEAM BYPASS LINE STRUCTURAL EVALUATION Prepared for: Detroit Edison Company Enrico Fermi 2 Job Site 6400 North Dixie Highway Newport, MI 48166 Prepared by: Hopper and Associates
- Suite E , 210 Avenue I I Redondo Beach, CA 90277 October 3, 1986 8610220191 861016 1 PDR ADOCK 0500 P
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.. k'ttachment VPs86-0146 Page'18 of 23 HOPPER AND ASSOCIATES HA-10/86-532 l
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A catastrophic respnnse to flow generated noise was observed in i the Fermi facility main ~ steam relief _ valve dumplines during operation in 1985. As a result, this 30" diameter piping was redesigned to en- ,
hence its operational response characteristics. The material thick- 1 ness was increased from 3/8" t o .1 " , and support lugs were removed from !
the piping to reduce wall stresses and stress concentrations. In ad-dition, flow orifice plates were installed downstream to mitigate the noise levels at high mass flow rates. The newly configured piping was thoroughly instrumented to provide immediate feedback on the opera-tional response of the system. .
I as predicted, the I Evaluation of the resulting data shows that, most severe structural response in the form of wall flutter occurred in the west line just downotream from the valve. Significant random vibration was observed at mass flow rates between 30 to 40 percent of the design limit. A fatigue life evaluation using a correlated frac-ture mechanics approach indicates that the system is not susceptible to structural degradation even in the most critical mode of operation.
The wall flutter observed in the dumplines was noted to have ran-dom vibration characteristics. The fatigue life evaluation was based upon a' detailed fracture mechanics analysis in which a maximal permis-cible weld flaw was assumed at the location of critical stress.
Crack growth was evaluated in accordance with the relationship presented in Exhibit A.
As anticipated, data from the instrumentation revealed critical atrains in the west line just downstream from the valve. Exhibit B indicates maximal half amplitude (0-P) microstrain recorded at this location as a function of mass flow rate. For the postulated weld flaws to grow, the strain . (0-P) must exceed a 100 microstrain threshold level. These strains were noted only at 30 to 40 percent design mass flow rate levels. At other mass flow rates, crack growth is improbable.
Statistical analysis of maximal and minimal peak strain values measured from expanded scale strain traces yielded a normal distribu-tion for number of occurrences as a function of peak strains. The i; number of occurrences for alternating stresses is determined by the difference (maximal minus minimal distributions) as a Rayleigh dis-tribution. The Rayleigh distribution of occurrences for' alternating i.
atress ranges at 36% mass flow rate determined for a one-second time interval is shown in Exhibit C. A minimal occurrence of detrimental stresses (i.e. A S>5. 85 KSI) is observed from the Rayleigh distribu-tion. These stress-occurrence value sets are then used to predict fatigue crack growth.
Attachment VF-86-014&
Page 19 of 23 HOPPER AND AssocirrES HA-10/86-532 ENGINEERS The life of the west dumpline in the most critical operating mode at 36% mass flow is estimated to be in excess of 130 days as shown in Exhibit D. This represents the total accumulated time in the critical mode, therefore, brief transitory periods through~the critical operat-ing mode range are not detrimental to the overall life of the pipe (this phenomenon is akin to the transition of a turbine through its critical speed during synchronization). Furthermore, radiography of the welds in .the critical regions has indicated that flaws with the postulated size are not present. This means that the critical fatigue life prediction is extremely conservative and that structural degrada-tion is improbable even in the worst-case operating situation.
However, avoiding operation of the west dumpline between the 30 and 40 percent flow rates can do no harm.
Larger peak stress intensity ranges are probable at other loca-tions in the line as a result of three-dimensional stress combination end stress concentration effects. Such stresses do not appear to be detrimental since significant material flaws are not observed in the parent material.
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