ML19323B444
| ML19323B444 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/05/1980 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0667, RTR-NUREG-667 NUDOCS 8005120379 | |
| Download: ML19323B444 (5) | |
Text
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8 0051go 37 0 Docket No. 50-346 TOLEDO License No. NPF-3 EEllEiC2rd Serial No. 613 May 5, 1980 R ". 2 P C ' 2 3 a
-t a
v u sc Director of Nuclear Reactor Regulation At t ent ion :
Mr. Robe rt N.
Reid, Chie f Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washin gton, D.
C.
20535 Dea r Mr. Reid:
On April 23, 1980 re p re sen ta tive s f rom your organization, Babcock and Wilcox (B&W) and all operating licensees owning B&W nuclear steam supply systems met in your of fices to discuss Section 7 of NUREG 0667 " Transient Respense of Babcock and Wilcox Designed Reactors".
Your staf f also solicited comments on several of the NUREG 0667 recommendations.
Toledo Edison considers the NUREG 0667 as one input document to the prioritiza-tion of several ongoing activities. We are extremely concerned that the original intention of integrating these activities into the TMI-2 Task Action Plan has been abandoned.
This results in some level of independent treatment of the document's recommendations that almost by necessity will yield inconsistency in evaluations of any required implementation, and will no doubt require compromises of both licensee and NRC resources to initiate non-coordinate requirements.
Toledo Edison 's st c,ngest comment recommends the reconsideration of this segre-gation action.
Ihree additional general comments include:
(1) The qualitative consensus assessment of Section 7 is, to our under-standing, generically based.
This certainly would be appropriate in looking at implementation of recommendations in a plant that has not previously implemented any specific or alternative approaches.
How-ever, many recommendations are inter-related with other recommendations in this document, as well as with other activities that conld affect the overall " comparative value" for a specific plant.
Additionally the generic " comparative value" results are not reflected adequately in the re commen dat ion s.
It appears that even on the qualitative con-sensus assessment level several of the recommendations could be modified or de leted. This has not been done and therefore removes some of the optimism that was held for the objective probablistic evaluation approach.
N
\\
THE TCLECC EC:3CN CCMPANY ECISCN PtAZA 3CC MACISCN AVENUE TCLECO, CMC a3552
Docket No. 50-346 License No. NPF-3 Serial No. 613 May 5, 19 80 Page Two (2) Several of the recommendations are overly prescriptive. - In some cases detailed fixes are enumerated.
These do not take into account dif f icul-ties of installation or operation of that one item as compared to alter-natives, or even the real need of the modiff : tion as determined by analy-sis or operational restrictions. Although discussions with task force members showed flexibility in this area, since TMI-2, obvious oral interpretations of published recommendations have been increasingly difficult to attain f rom an implementation audit group after a task force has disbanded. The basis of the technical concern needs to be the recommendation. How that is resolved should be in a manner such that the basis is addressed adequately by analysis, hardware, and/or operational commitmen ts.
(3) Recommendations need to be integrated with other ongoing approaches for continuity and priority - In discussions with the task force members some recommendations appeared to rely on fault fixing, and event-oriented responses made by station personnel during an event.
These activities do not appear consistent with our major post IMI-2 thrust. An extremely large effort, in design, operation, and analysis, by the industry is trying to attain symptom-related responses to assure that safe, stable, shutdown can be reached and maintained relying as little as possible on the operator or maintenance personnel to correct the initiating problem.
We believe this is the more effective prioritization of industry resources.
Several recommendations are based on items that have been previously addressed by utilities, but the Task Force may not have had time or information to review or evaluate in detail.
In some cases generic industry activities are ongoing now to address, in more detail, require-ments that need to be provided to cope with plant status evaluation.
Some specific comments to selected recommendations are attached as they relate to Davis-Besse Nuclear Power Station, Unit 1.
It is Toledo Edison's intention to evaluate the recommendations of NUREG 0667 in light of already ongoing activities.
No independent implementation is considered necessary.
Very truly yours, Yf W
RPC:TJM: cts Attachment
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