ML20069L336
| ML20069L336 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/20/1983 |
| From: | Coffey J TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-50-26-83024, NUDOCS 8304280168 | |
| Download: ML20069L336 (1) | |
Text
N N TRIS, E62 8804 20 830 C
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TELECOPY TO NRC T. G. Campbell, 1760 CST 2-C Apr. 20, 1983 G. L. Paulk, NRC T. L. Chinn, BFN C. W. Crawford, 670 CST 2-C U. S. Nuclear Regulatory Commission A. W. Crevasse, 401'UBB-C G. S. Harrison, Plt Supt Office Region II L. M. Mills, 400 CST 2-C 101 Marietta Street, NW Shift Engineer Suite 3100 F. A. Szczepanski, 417 UBB-C Atlanta, Georgia 30303 W. C. Thomison, BFN D. L. Williams, W10B85C-K BFRO-50-296/83024 Reported under Technical Specification 6.7.2.a.(8)
Telecony : Date: 4/20/83 Time:
1300 ca o
W Telsohone : Date: 4/20/83 Time:
1220 n
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Person Contacted: Ross Butcher and Floyd Cantrell W
Py Date of Occurrence: 4/19/83 Time of Occurrence: 1500 Unit 3 in C
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83 Technical Specification Involved: 2.1
~f Li Conditions Prior to Occurrence C
Unit'1 - Refueling outage Unit 2 - 945 - steady state Unit 3 - 99 5% - steady state Identification and Description of Occurrence Review of licensing documents revealed the Lead Test Assemblies in unit 3 could reach a maximum of 18.8 kw/ft in the event of rod withdrawal errer
-(reference supplemental reload licensing submittal BFNP 3 Reload 4). NEDC 24376 gives the safety limit LHGR for the LTA's as 17.8 kw/ft at 0 exposure and 17.6 kw/ft at 25000 MWD /t exposure.
Potential for violation of LHGR safety limits exists.
Annarent Cause of Occurrence l
Error in the preparation and review of GE licensing documents.
j Other Related Events Corrective Action Taken or Planned MFLPD for LTA's was verified less than.904.
This ensures LHGR is equal to or less than 12.1 and in the event of rod withdrawal error the maximum LHGR for the LTA's will not exceed 17.0 kw/ft.
This will be monitored on a daily basis and administratively controlled. General Electric has been contacted to perform the rod withdrawal error reanalysis using a control cell core rod configuration (which unit 3 has operated in this cycle).
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f{gActingPowerPlantSuperintendent OFFICI A1. COPY ;
J. A. Coffey Browns Ferry Nuclear Plant
- /-- d' 2 M 8304280168 830420 PDR ADOCK 05000296
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