ML19220C841
| ML19220C841 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/28/1977 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Mattson R Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7905150654 | |
| Download: ML19220C841 (1) | |
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6t FiD Distribution: u NHd xcg, File RSB File JUL 2 8 G77 T. Novak Israel chron Cock =t ':o. 50-320 ME"CRANDUM FOR:
Roger J. !!attson, Director, Division of Systems Safety FRCti:
Thomas M.
lovak, Chief, Reactor Syster.s Eranen SUEJECT:
THREE MILE ISLAND U'iIT 2 STEA11 LIE SREAX A:iALYSIS CAPA5!LITY A meeting with GPU was held on July 21, 1977. The staff was advised by the applicant and h555 supolier (5&W) that they have no analysis capability to detemine fuel da age folicwing a stean line break when the core returns to pcwer. Absence of code capability to address core heat transfer at reducec pressure and ficw cv.ditions and the absence of ability to consicer ceaking factors resulting frco a stue': rod assecbly during th: transier.t cave teen Cited.
The staff believes that there is a potential for fuel damage following this event.
It is required that the extent of fue! damace be identified fcr this platit during such an event as well as other B*iW plants woich also may return to power (<0%) following a steam line break.
It is requested that the apolicant and BMI present their plans and schedule relative to preparing this analysis capability and the apclication of it in support of T'il-2.
This subject was discussed with 31W cn July 28, and it was concluded that B&W does not have near-term analytical cacability and the potential for fuel failure under similar SLB ccnditions could be generic.
S&W was requested to ccmpare their core with similar Westinchouse and C-E designs as a basis for assessing the safety significance in S&W plants.
I proposed two meetings in Bethesda on August 5 to discuss the generic issue and then the TMI-2 issue. These meetings wmid be attended by appropriate levels of canagement frca CSS, CCR, and CPM.
Your concurrence of this plan is mauested.
Original Signed DJr T. M. Novak Themas M. Novak, Chief Reactor Systems Branch cc:
F. Scnreeder D. Ross G. Mazetis
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