NRC-09-0025, 2 - Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report: Difference between revisions

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#REDIRECT [[NRC-09-0025, Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report]]
| number = ML091140127
| issue date = 04/17/2009
| title = 2 - Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report
| author name = Johnson R W
| author affiliation = Detroit Edison
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000341
| license number = NPF-043
| contact person =
| case reference number = NRC-09-0025, VP-86-0154
| document type = Letter type:NRC, Report, Miscellaneous
| page count = 8
}}
 
=Text=
{{#Wiki_filter:Fermi 2 6400 North Dixie Hwy., Newport, MI 48166 Detroit Edison TS 5.6.6 VP-86-0154 1OCFR50.46 April 17, 2009 NRC-09-0025 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington D C 20555
 
==Reference:==
 
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
 
==Subject:==
Submittal of 2008 Safety Relief Valve Challenge Report, Main Steam Bypass Line Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report The Fermi 2 Technical Specifications (TS) contains a requirement for submitting an annual report for safety relief valve challenges (TS 5.6.6). Enclosure 1 provides the Safety Relief Valve Challenge Report for 2008.Enclosure 2 provides the annual Service Life of the Main Steam Bypass Lines Report for 2007. This satisfies the commitment stated in Detroit Edison's letter to the NRC dated November 7, 1986 (VP-86-0154).
Enclosure 3 provides the annual Emergency Core Cooling System (ECCS) Cooling Performance Evaluation Model Changes or Errors Report for 2008. This report is provided in accordance with 10 CFR 50.46(a)(3)(ii).
Should you have any questions or require additional information, please contact me at (734) 586-5076.Sincerely, Rodney W. Johnson Manager, Nuclear Licensing f A DTE Energy Company -.
USNRC NRC-09-0025 Page 2
 
==Enclosures:==
: 1. Safety Relief Valve Challenge Report 2. Service Life of Main Steam Bypass Lines Report 3. ECCS Cooling Performance Evaluation Model Changes or Errors Report cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 4, Region III Regional Administrator,'
Region III Supervisor, Electric Operators, Michigan Public Service Commission ENCLOSURE 1 TO NRC-09-0025 FERMI 2 SAFETY RELIEF VALVE CHALLENGE REPORT JANUARY 1 -DECEMBER 31, 2008 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 Enclosure 1 to NRC-09-0025 Page 1 Safety Relief Valve Challenges There were no instances in 2008 where reactor pressure was high enough to require Safety Relief Valve (SRV) actuation.
There were also no instances in 2008 where an SRV actuation was demanded by an automatic logic system.
ENCLOSURE 2 TO NRC-09-0025 FERMI 2 SERVICE LIFE OF MAIN STEAM BYPASS LINES REPORT JANUARY 1 -DECEMBER 31, 2008 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 Enclosure 2 to NRC-09-0025 Page 1 Service Life of Main Steam Bypass Lines In accordance with Detroit Edison's letter to the NRC dated November 7, 1986 (VP-86-0154), the cumulative time the main steam bypass lines are operated with the bypass valves between 30 and 45 percent open will be reported annually.
A cumulative value of 100 days is not to be exceeded without prior NRC notification.
Evaluations performed by Detroit Edison contractor companies concluded that the bypass lines are acceptable for safe operation when operated within the 100 day constraint.
Based on these evaluations, the main steam bypass piping that was installed in 1985 has a service life that will allow it to function for the life of the plant under anticipated operating conditions.
As of December 31, 2008, the main steam bypass lines cumulative usage was 41.38 days.
ENCLOSURE 3 TO NRC-09-0025 FERMI 2 ECCS COOLING PERFORMANCE EVALUATION MODEL CHANGES OR ERRORS REPORT JANUARY 1 -DECEMBER 31, 2008 DETROIT EDISON COMPANY NRC DOCKET NO. 50-341 FACILITY OPERATING LICENSE NO. NPF-43 Enclosure 3 to NRC-09-0025 Page 1 ECCS Cooling Performance Evaluation Model Changes or Errors One error has been identified since last year's report: General Electric JOCFR50.46 Notification Letter 2008-01, Revision 1, dated November 25, 2008, identified a 5 degree Fahrenheit (5°F) increase in the licensing basis Peak Cladding Temperature (PCT) for the GE14 fuel type small break Loss of Coolant Accident (LOCA)analysis.
The limiting transient for the GE14 fuel is the small break LOCA; therefore, the error resulted in a 5°F increase in the licensing basis PCT for GE14 fuel.The General Electric notification was the result of a Steam Flow Induced Error (SFIE) where water level could reach the bottom of the dryer and allow steam to bypass to the reactor pressure vessel annulus. This bypass affects the Level 3 water level measurement, which relies on pressure taps in the reactor pressure vessel annulus.Scram from the Level 3 level indication is conservatively modeled in small break Emergency Core Cooling Systems (ECCS)-LOCA analyses assuming 1OCFR50, Appendix K requirements.
Since Fermi 2 has a limiting PCT defined by a small break assumption there is an effect on the licensing basis PCT. An assessment made by the fuel vendor of the effect on the Fermi 2 licensing basis PCT found an impact on the GE14 small break LOCA analysis only. Design Basis Accident (DBA) (large break) analyses are confirmed to be unaffected by SFHE as the modeling relies on signals other than Level 3 for scram and ECCS response.The current licensing basis PCT for Fermi 2 is 1830 degrees Fahrenheit for GEl I fuel and 1990 degrees Fahrenheit for GE14 fuel. Fermi 2 currently maintains two LOCA analyses, one for each of 'Global Nuclear Fuel -Americas' GEl I and GE14 fuel types. A 5 degrees Fahrenheit will administratively be added to the GE14 small break LOCA PCT; therefore, the new licensing basis PCT for Fermi 2 becomes 1995 degrees Fahrenheit.}}

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