ML15264A576
| ML15264A576 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/19/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| Shared Package | |
| ML15264A577 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-68093, TAC-68094, TAC-68095, NUDOCS 8812280020 | |
| Download: ML15264A576 (1) | |
Text
December 19, 1988 Docket Nos.:
50-269, 50-270 DISTRIBUTION and 50-287 Docket-File NRC PDR LOCAL-PDR PD r/f Mr. H. B. Tucker, Vice President SVarga GLainas Nuclear Production Department DMatthews MRood Duke Power Company HPastis OGC 422 South Church Street EJordan ACRS(10)
Charlotte, North Carolina 28242 BGrimes
Dear Mr. Tucker:
SUBJECT:
CONFORMANCE TO REGULATORY GUIDE 1.97 AND COMMITMENT CHANGE ON MAIN STEAM SAFETY/RELIEF VALVE POSITION (TACS 68093/68094/68095)
Re: Oconee Nuclear Station - Units 1, 2, and 3 The staff has reviewed your April 20 and May 15, 1988, letters requesting deviations from Regulatory Guide (RG) 1.97. The deviations relate to pres surizer level, pressurizer heater status, safety relief valve position or main steam flow instrumentation, and accumulator tank level. and pressure.
The staff has concluded that your design for the variables on pressurizer level, pressurizer heater status, and safety relief valve position or main steam flow instrumentation is acceptable with respect to conforming with R.G. 1.97, Revision 2.
The acceptability of instrumentation for accumulator tank level and pressure will remain open pending the outcome of the staff's generic review of the needs for environmentally qualified category 2 instrumentation to monitor this variable. Therefore, when the generic review process has been completed, the staff will report on the acceptability of this issue.
For details related to these issues, refer to the enclosed supplemental safety evaluation with its attachment, EG&G Idaho, Inc., Technical Evaluation Report, EGG-TA-6959, Revision 1.
Sincerely, Original Signed By:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosure:
Supplemental Safety Evaluation w/att cc w/encl:
See next page PD P I p II-3 oM H
is'.s w DMatthews 12/4,/88 12/1/88 12/t /88 SS122O0S S1219 PDR ADOCK 05000269 P
FDC