ML19290E499
| ML19290E499 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek, Millstone |
| Issue date: | 01/21/1980 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19290E500 | List: |
| References | |
| TASK-08-01.A, TASK-8-1.A, TASK-RR NUDOCS 8003140135 | |
| Download: ML19290E499 (1) | |
Text
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,.,[j NUCLE AR REGULATORY COMMISSION W ASHINGTON. D. C 20555 C
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gv j JAN 21 1983 MEMORANDUM FOR:
D. G. Eisenhut, Acting Director Division of Operating Reactors, NRR FROM:
R. J. Mattson, Director Division of Systems Safety, NRR "SPONSE TO OPERATING EXPERIENCE MEMORANDUM N0. 23 SUBJECT-POTENTIAL OVERVOLTAGE CONDITION - OYSTER CREEK' Follouing the degraded grid conditions which occurred at Millstone in 1976, the Power Systems Branch developed a four part position on this subject.
The first three parts of this posi+. ion paralleled the three part position generated by D0R. These three parts respectively addressed a second level of off-normal voltage protection, load shedding of the emergency buses while powered from onsite sources, and explicit inclusion of the above features in the Technical Specifications. The forth part of the Power Systems Branch position deals with the optimization of voltage at the safety beses by appropriate adjustment of the transformer tap settings. Part 4 reads, in full, as follows:
"4.
The voltage levels at the safety-related buses should be optimized for the full load and minimum load conditions that are expected throughout the anticipated range of voltage variations of the offsite power source by appro-priate adjustment of the voltage tap settings of the interven-ing transformers. We require that the adequacy of the design in this regard be verified by actual measurement cnd by correlation of measured values with analysis results.
Pro-vide a description of the method for making this verification; before initial reactor power operation, provide the documenta-tion required to establish that this verification has been accomplished."
8003140 m5 p
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. E l ISE The above position was coordinated with D0R in 1976 and has been applied to all plants in licensirg review since that time. We feel that this is fully responsive to Operat'.ng Experience Memorandum flo. 23.
[-
my Rog.r J. Mattson, Director Division of Systems Safety, ilRR
Contact:
R. G. Ci tzpatrick x27276 cc:
H. Denton J. Sniezek E. Ca'se L. flichols D. Vassallo G. Lainas D. Muller R. Satterfield R. Mattson F. Rosa F. Schroeder V. Thomas R. Tedesco E. Wenzinger E. Jordan J. E. Knight DSS ads D. Tondi DOR ads R. Kendall 00R BCs PSB flem';ers 00R SLs SDOE31_gy