ML17331A611
| ML17331A611 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/21/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A610 | List: |
| References | |
| NUDOCS 8102060554 | |
| Download: ML17331A611 (2) | |
Text
Enclosure 1
t t
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0
SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATIONI DONALD C.
COOK UNITS 1
AND 2 FRACTURE TOUGHNESS OF STEAti GENERATOR ND RE TOR COOLANT P I~IP SUPPORTS DOCKETS NOS.
50-315 5 316 1.0 Introduction 2.0 In a letter dated November 23,
- 1977, Indiana and Michigan Power Company responded to the NRC's request for information concerning the fracture toughness design of the steam generator and reactor coolant pump supports at D.C.
Cook Units 1 and 2.
This information was initially reviewed by Sandia Laboratories as part of generic technical activity A-12'andia's evaluation concluded that the steam generator and reactor coolant pump supports at D.C.
Cook Units 1
and 2 were considered to be as good as careful, reasonable engineering practice can produce.
This evaluation is contained in NUREG-0577.
The information contained in the licensee's response was subsequently transmitted to Franklin Research Center for an independent evaluation.
This evaluation was based on the criteria presented in the draft version of NUREG-0577.
Evaluation 3.0 The enclosed Technical Evaluation Report was prepared by the Franklin Research Center as part of NRC Contract No, NRC-03-79-118.
The scope of Franklin's review was limited to those supports originally reviewed by Sandia which included the steam generator and reactor coolant pump supports.
Subsequent to the initial review by Sandia Laboratories, the scooe of Generic Technical Activity A-12 has been expanded to include other supports.
For those supports identified by the final version of NUREG-0577 that are not included in this review, the licensee should follow the implementation plan specified in NUREG-0577.
Conclusion Based on our review of Franklin's Technical Evaluation Report, we agree with their conclusion that the steam generator and reactor coolant pump supports at D.C.
Cook Units 1
and 2 possess adequate fracture toughness to merit a group III rating per. NUREG-0577.
Therefore, we consider the fracture toughness of the steam generator and reactor coolant pump supports acceptable.
h