ML20149J128
| ML20149J128 | |
| Person / Time | |
|---|---|
| Issue date: | 06/30/1997 |
| From: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| To: | Callan L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-10CFR9.7 COMSECY-97-013, COMSECY-97-13, NUDOCS 9707280061 | |
| Download: ML20149J128 (2) | |
Text
\\,
k aaaa..
oa..............
- p% $
UNITED STATES y
NUCLEAR REGULATORY COMMISShN RELEASED TO THE P WASHINGTON, D C. 20555-0001 e
g'
,of e
date initia!6 June 30, 1997 I
- eses >esee....
om, OFFICE OF THE f
SECRETARY i
MEMORANDUM TO:
L. Joseph Callan ExectLQive Director for Operations FROM:
Johry Ho ec tary
SUBJECT:
STA F REQUIREMENTS - COMSEC F9 NES D-STEAM GENERATOR RULEMAKING The Commission has approved the proposed approach which concludes that a revised approach utilizing a compliance-based generic letter and a risk-informed Regulatory Guide is an appropriate means to ensure steam generator tube integrity.
Should the staff conclude that the current technical specifications do not adequately assure steam generator tube integrity absent any action or requirement by the licensee beyond those specified by the technical specification, then the staff should explore a more definitive means of ensuring the technical specifications are appropriately amended, including issuance of an order.
The staff should seek industry input, as appropriate, in developing the technical basis for the proposed technical specification changes and to ensure that the proposed changes are consistent with the current steam generator tube degradation modes.
The staff should provide additional information in the proposed regulatory package (currently scheduled to be forwarded to the Commission in the September 1997 time. frame) on how the IPE follow-up program will be utilized to evaluate PWRs which have a high potential for core damage sequences that can challenge steam generator tube integrity.
This information should include 1) an assessment of the level of detail in plant-specific probabilistic risk analysis necessary to support the aforementioned evaluation,
- 2) how the staff proposes to obtain the necessary plant-specific information, and 3) a plan showing scheduled milestones.
The staff should account for the fact that the final Commission position on DG-1061, the use of PRA, and severe accidents have not yet been established, and the new Regulatory Guide may require revision in accord with future Commission decisions on these matters.
In addition to the risk-informed degradation-specific management approach, the staff should also review any deterministic alternate repair criteria proposed by licensees.
(EDO)
(SECY Suspense:
9/26/97)
O)
DqA1-bsM!
j llllllklll!}lk!h!
9707280061 970630 i.**
, cc:
Chairman Jackson Commissioner Rogers Commissioner Dicus Commissioner Diaz Commissioner McGaffigan OGC CIO CFO OCA OIG l