ML19256D752
| ML19256D752 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/03/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19256D751 | List: |
| References | |
| NUDOCS 7910220680 | |
| Download: ML19256D752 (2) | |
Text
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January 3, 1977 DISTRIBUTION:
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l1gra Docket No.: 50-289 0
- y Memo File R. Reid V. Stello K. Galler MEMORANDUM FOR: Karl V. Seyfrit. Chief, Reactor Technical Assistance Branch, Office of Inspection and Enforcement FROM:
Robert W. Reid, Chief, Operatino Reactors Branch f4, Division of Operating Reactors
SUBJECT:
THREE MILE ISLAND UNIT NO.1 - DOCKET NO. 50-289 -
DISCREPANCY BETWEEN REACTOR COOLANT PLHP PONITOR DELAY TIME AND THE VALUE ASSUMED IN THE FSAR This is in reply to your memorandum of December 13, 1976, in which you requested the status of D0R review of the subject issue reported in I
Three Mile Island Unit No.1 occurrence reports 76-18/1P and 76-18/1T l-of May 14 and May 26, 1976.
I We have reviewed the inforsation provided by the licensee in occurrence report 76-18/1T in which he presents the results of his analysis of
~
the effect of the increased monitor delay. As a result of our review we find the assumptions and results of the analysis acceptable. While the analysis shows that the increase in monitor delay time causes a decrease in the minimum DNBR from 1.75 to 1.60 for a four pump i
coastdown from 102% power, this is still well above the safety criterion value of 1.30, and is therefore acceptable. The B&W-2 critical heat flux correlation employed in his analysis is also accep-table as stated in our letter of May 18, 1976, to the licensee transmitting licensee amendment No. 17.
We therefore consider this item closed.
t RobertW. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors 1453 225 s m M s' sde xEx0RB R
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