ML16299A519
| ML16299A519 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/03/1991 |
| From: | Wiens L Office of Nuclear Reactor Regulation |
| To: | Miraglia F, Murley T, Russell W NRC |
| References | |
| NUDOCS 9112090003 | |
| Download: ML16299A519 (3) | |
Text
j REQ0 UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 December 3, 1991 Docket No. 50-287 MEMORANDUM FOR: T. Murley
- 0. Zwolinski B. Grimes F. Miraglia M. Virgilio Acting DD, DRIS W. Russell D. Crutchfield F. Congel J. Partlow W. Travers E. Butcher F. Gillespie C. Rossi J. Roe S. Varga J. Richardson C. Thomas J. Calvo B. D. Liaw W. Bateman, EDO G. Lainas A. Thadani M. Slosson B. Boger G. Holahan Operations Center E. Merschoff, RH THRU:
David J. Lange, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II FROM:
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/H1
SUBJECT:
DAILY HIGHLIGHT Oconee Unit 3 Oconee Unit 3 continues to be shut down and depressurized as a result of the instrument line leak inside containment which occurred on November 23, 1991.
Duke Power Company (DPC) has removed the mechanical compression fitting that failed on the instrument line and sent it to B&W for a root cause failure analysis.
Initial analysis by DPC indicates that the fitting was not properly assembled during initial installation.
Inspection of the other two applications of this type fitting on Unit 3 indicated that the fittings were installed properly. DPC has completed modifications to the instrument line on both hot legs by attaching a mechanical fitting on 3/8 inch tubing instead of the previous 3/4 inch tubing that had to be reduced to 3/8 inch tubing. Units 1 and 2 will be modified during their next outages.
CONTACT:
L. Wiens, NRR/PDII-3 X21495 9:112090003 911:203 PDR ADOCK 050o00287 P
F'DR
2 December 3, 1991 A total of approximately 87,000 gallons of water was pumped from the reactor building sump and processed through rad waste. This total included some normal leakage from non-nuclear sources. A total of 672 curies of noble gasses and 1.62 E-4 curies of Iodine have been purged from the containment.
Both totals represent less than.008 percent of the allowable annual dose from the respective isotope. The licensee has conducted a comprehensive inspection of electrical, mechanical and instrumentation components. NRR projects in conjunction with Region II inspectors, and NRR plant systems and engineering division staff have reviewed the licensees actions regarding inspection activities associated with equipment qualifications and electrical and mechanical component degradation. No damage, other than the loss of one fire detection sensor and a small amount of water in the oil for one reactor coolant pump, has been found.
The licensee is presently completing these inspections and proceeding to make preparations to restart the plant. The resident inspectors, Region II and NRR participated in a conference call with the licensee on December 2, 1991, to discuss their root cause analysis and corrective actions and are continuing to closely monitor the licensees actions.
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II cc:
All NRR PDs A. Chaffee L. Plisco G. Imbro December 3, 1991 A total of approximately 87,000 gallons of water was pumped from the reactor building sump and processed through rad waste. This total included some normal leakage from non-nuclear sources. A total of 672 curies of noble gasses and 1.62 E-4 curies of Iodine have been purged from the containment.
Both totals represent less than.008 percent of the allowable annual dose from the respective isotope. The licensee has conducted a comprehensive inspection of electrical, mechanical and instrumentation components. NRR projects in conjunction with Region II inspectors, and NRR plant systems and engineering division staff have reviewed the licensees actions regarding inspection activities associated with equipment qualifications and electrical and mechanical component degradation.
No damage, other than the loss of one fire detection sensor and a small amount of water in the oil for one reactor coolant pump, has been found.
The licensee is presently completing these inspections and proceeding to make preparations to restart the plant. The resident inspectors, Region II and NRR participated in a conference call with the licensee on December 2, 1991, to discuss their root cause analysis and corrective actions and are continuing to closely monitor the licensees actions.
/s/
Leonard A. Wiens, Project Manager Project Directorate 11-3 Division of Reactor Projects -
1/II cc:
All NRR PDs A. Chaffee L. Plisco G. Imbro DISTRIBITION:
Docket File NRC & Local PDRs PDII-3 R/F DMatthews LWiens LBerry OFC
- LA:PDII-3
,:F:D:PDII 3
NAME
- LBerry
- LWiens:cw
- DMatt DATE :11/S\\91
- i)-/)/91
/91 OFFICIAL RECRD COPY Document Name:
OCONFEE DAILY HILITE 112/3