ML17244A191
| ML17244A191 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/08/1978 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-02, REF-GTECI-RV, TASK-03-05.A, TASK-03-05.B, TASK-3-5.A, TASK-3-5.B, TASK-RR NUDOCS 7811140241 | |
| Download: ML17244A191 (3) | |
Text
4 Es REGULATORY'INFORMATXON DISTRIBUTION
~STEM DOCKET NBR:
50-244 RE GINNA 1 RECXPXENT:
ZXEMANN, D.L.
ORXGINATOR: WHITE, L.D.
COMPANY ROCHESTER'GAS'6'ELEC
SUBJECT:
Furnishes addi info re 781004 meetin DOC DATE:
781108 ACCESSXON NBR-7811140241 COPIES RECEIVED:
LTR 1
ENCL 0
SIZE:
2 to discuss SEP To ic 3-5.A Hi h Energy Line Breaks Inside Containment.
Discus'ses i e stress calculations, high energy line break outside containment, eneric task A-2 6 As mmetric LOCA loads.
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~
N AllE ElvCL2 BR CH F
NRC Pnp ILE OELD HANAUER CORE PERFORSANCE BR AD FOR SYS 5
PROJ FNGIl fERI NG BR REACTns SAFFTY BR PLANT SYSTEMS BR EER EFFLUFlvT TREAT SYS J
'lCGOUGH LPDR TERA NSIC ACRS TOTAL NUMBER OF CUP W/7 EhlCL W/ENCL W/ENCL W/P.
ENCL I TR ONLY lV/ENCL
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<</E~'CL W/ENCL LV/ElVCL w/ENCL iV/ENCL tV/ENCL W/ENCL 4'/ENCL w/ENCL 4'/ElvCL W/lb ENCL IES REQUIREDI LTR ENCl FOR ACTION ORB52 BC 00-39 NOTES:
ROCHESTER GAS AHD ELECTRlC CORPORATIOiV g ~
~ JAIL~ 4 89 EAST A",I='!4UE, ROCHESTER, H.Y. t4649 I-EON D, WHITE, JR.
VICC PRCSIDCNT
'I C L. C>H0 N E A i A ~OQC
'tlat 546-2700 November 8,
1978 Director of Nuclear Reactor Regulation Attention:
Dennis L. Ziemann, Chief Operating Reactors Branch No.
2 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
High Energy Line Breaks Inside Containment R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Ziemann:
On October 4,
- 1978, members of our Staff and representatives of other utilities involved in the Systematic Evaluation Program (SEP) met with members of your Staff to discuss SEP Topic III-S.A, High Energy Line Breaks Inside Containment,.
The purpose was to clarify the actions that we and the NRC Staff would be taking to resolve this topic and to discuss tentative schedules.
We have reviewed the minutes of the meeting, dated October 20, 1978, which were prepared by your Staff and wish to add additional information regarding the meeting.
The Staff indicated that, submittal of the original pipe stress calculations for Ginna was voluntary and not necessary for resolution.
Some utilities within the SEP Owners'roup preferred the Mechanistic Approach.
We however, encouraged the Staff to continue to develop other technical approaches which could be used to resolve the topic.
With respect to the Ginna high energy line break outside con-tainment evaluation, modifications performed did follow from the calculations.
An augmented inservice inspection provided a valuable technique for addressing that issue.
pt'oo
ROCHESTER GAS ANO ELECTRIC CORP.
November 8,
1978 Director of Nuclear Reactor Regulation SHEET NO.
The Staff indicated that the phenomenon being evaluated in generic task A-2, Asymmetric LOCA Loads, are not considered to be part of thia SEP topic.
The work on generic task A-2 includes detailed definitions of the loads due to pipe breaks at critical locations and evaluation of the effect of these loads on major reactor coolant system components, their supports, and reactor internals including fuel.
For SEP Topic III-5.A, the NRC staff expected that utilities will evaluate the effects of pipe whip, jet impingement and environmental effects on other systems and components important to safety.
Very truly yours,