ML20080E551
| ML20080E551 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Hatch |
| Issue date: | 05/13/1975 |
| From: | Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079D981 | List: |
| References | |
| FOIA-83-728 NUDOCS 8402090560 | |
| Download: ML20080E551 (2) | |
Text
y.
's UNITED STATES NUCLEAR nEGULATORY COMMisslON WASH!NGTON, D.
C.
20555 MAY 131975 J. F. Stolz, Chief, LWR Branch 2-1, RL GEORGIA POWER COMPANY - HATCH 1 - DOCKET N0. 50-321 A recent inspection of the subject facility by our IE:II office identified a specific section of the Hatch 1 Technical Specifications (TS) which requires clarification. Section 6.0.G.3.p. of the TS requires the licensee to maintain
" records of transient or operational cyclir.g for those plant components that have been designed to operate safely for a limited number of transients or operational cycles."
In addition,- the TS require the licensee to correlate his evaluation of cycling data to the Reactor Vessel Summary Stre. s T n.t (""), "clua ", S n U.n I'ur um TSA?..
Section 2.200, " Operating Parameters," of the SR (copy enclosed) provides a listing of transient conditions and related operational cycles.
In order for our inspector and licensee personnel to make proper use of this information, it appears that some clarification is warranted.
For example, Section 2.2 identifies turbine generator trip and all other scrams as events requiring correlation; however, it is not evident whether trips or scrams from 50% or lower reactor power should be included. The same question can be asked regarding the other transients.
It is requested that the TS be clarified to identify the i
specific threshold values of power level, temperature, pressure, etc., which apply to the transients and operational cycles referred to by TS 6.0.G.3.p.
Likewise, the specific transients and operational cycles identified in the SR should be identified as to their applicability to the components listed in the TS; namely, the feedwater nozzles, flange studs, and reactor vessel shell.
~
e4agi? *0
, (,mo,['g hhDEN83-72
'/ '..
mwp
?'
Nn
%,;. -Rf
- '/3.t916
J. F. Stolz MAY l 3 Wif, We note the standard TS for BWR and PWR facilities require licensees to maintain " records of transient or operational cycles for those facility componants designated as designed for a limited number of transients or cycles." By copy of this memorandum it is recom-mended that the Assistant Director for Operating Reactors, RL revise the standard.TS format to require licensees to identify the specific components to be covered and the related threshold value criteria.
If you require additional information or wish to discuss this matter further, please contact F. J. flolan or me on extension 7451.
In any event, we would appreciate r.otification as to the RL position regarding this matter.
h i
etuuep L.-
/. H. Sniezek,6 Chief Facility Inspection Branch Office of Inspection & Enforcement
Enclosure:
Pg 4, SR cc w/ enc 1:
FJNolan, IE cc w/o enc 1:
KRGoller, RL
(__.dE4cCough, RL REHall, IE WCSeidle, IE:II (F20064H1) isii is