ML19263E367
| ML19263E367 | |
| Person / Time | |
|---|---|
| Issue date: | 04/02/1979 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | Gilinsky V Office of Nuclear Reactor Regulation |
| References | |
| FOIA-79-98 NUDOCS 7906130356 | |
| Download: ML19263E367 (1) | |
Text
- c 4
UNITED STATES j
NUCLEAR REGULATORY COMMISSION
= *'l(!X '.j
[014 }/ i WASHINGTON. D. C. 20555 g,.v /
April 2,1979
..+
MEMORANDUM T0: Victor Gilinsky FROM:
Eds V
Per your request, I have attached the chcrter of the Task Group on Generic Implications of Feedwater Transient In B&W Designed Reactors, attachment: Memo to Edson Case dated 4/2/79 on Task Group - Generic Review of Feedwater Transient in B&W Designed Reactors cc: w/ attachment Chairman Hendrie Comissioner Kennedy Comissioner Bradford Comissioner Aherarne HRDenton, TMI Site LV Gossick 2357 052 SECY tog aossG f
e e
M j
UNITED STATES e 's NUCLEAR REGULATORY COMMISslON 3
..I d WASHINGTON, D. C. 20555 a%,b
'U 8
p April 2,1979 e
MEMORANDUM FOR: Edson G. Case, Deputy Director, Office of Nuclear Reactor Regulation FROM:
D. K. Davis, Chief, Systems evaluations Program Branch, DOR, NRR
SUBJECT:
TASK GROUP ON GENERIC REVIEW 0F FEEDWATER TRANSIENT IN B&W DESIGNED REACTORS As we discussed, a task group has been established to evaluate the generic implications of feedwater transients in B&W designed reactors. The members and their charter are set forth in the enclosure. An evaluation of the task group's findings and any reconmendations should be available in about ten days.
LK D. K. Davis, Chief, Systems Evaluations Program Branch
Enclosure:
Task group list and charter cc: NRR Division Directors NRR A/Ds R. Satterfield, ICSB G. Lainas, PSB Z. Rosztoczy, AB A. Oxfurth, IE 2357 053 P. Check, RSB S. Israel 1 *\\ O3\\ \\O l5k cr.
pq DT
.~w
- --mm4
TASK GROUP ON GENERIC REVIEW OF FEEDRATER TRANSIENTS IN B&W REACTORS Members:
S. Israel, Group Leader P. Check, RSB R. Satterfield ICSB G. Lainas, PSB Z. Rosztoczy, AB A. Oxfurth, IE Charter:
Given the operating experience with feedwater transients in operating B&W designed reactors, assess whether reactor and plant systems at these plants provide adequate protection from design basis feedwater transients. This assessment should re-confirm whether these plant designs meet the requirements of NRC regulations, using appropriate staff guidelines for acceptable means of meeting these regulations. This should include an evaluation of the safety margins of these plant designs to assure that specified acceptable fuel design limits are not exceeded as a result of feedwater transients.
2357 054
/
=
D