ML17037C549
| ML17037C549 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/14/1973 |
| From: | Schneider R Niagara Mohawk Power Corp |
| To: | Ziemann D US Atomic Energy Commission (AEC) |
| References | |
| Download: ML17037C549 (6) | |
Text
AEC DI BUTION 'FOR PART 50 DOCKET MA L
(TEMPORARY FORM)
CONTROL NO:
6238 FILE:
FROM&:
Niagare Mohawk Power Corp.
- Syracuse, N. Y.
13202 R. R. Schneider TO: Dennis L. Ziemann DATE OF DOC 8-14-73 ORIG 1 signed DATE REC'D 8-15-73 CC OTHER OTHER SENT AEC PDR x
SENT'LOCAL PDR CLASS UNCLASS DESCRIPTXON:
PROP INFO INPUT NO C S REC'D 40 ENCLOSURES:
DOCKET NO:
50-220 Ltr re our 7-16-73 ltr....furnishing info regarding NEDM-10735, Supplement 6, "Fuel Densification Effects in General Electric BWR Fuel," dtd August 1973.
PLANT NAK: Nine Mile Point 1
ACKNOWLEDGED DONQT REMOVE FOR ACTION/INFORMATION 8"16-73 LB V BUTLER(L)
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MOHAWK 300 ERIK BOULEVARD WEST SYRACUSE, N.Y, ISROR August 14, 1973
,Mr. Dennis L. Ziemann, Chief Operating Reactors Branch 82 Directorate of Licensing U.
S. Atomic Energy Commission'ashington, D. C.
20545
Dear Mr. Ziemann:
Re:
Nine Mile-Point Unit 1 Docket No. 50-220 Your letter of July 16, 1973, requested analyses and other relevant data for determining the consequences of densification using the guidance provided in the enclosure to your letter.
This includes the effects on normal 'operation, anticipated transients and accidents, including the postulated loss-of-coolant accident.
This letter also requested that changes to design or operating conditions be submitted if the analyses indicate'that changes are necessary to maintain required margins.
The requested analyses and other relevant data for determining the consequences of densification have been submitted to the Commission in a comprehensive generic report NEDM-10735, Supplement 6, "Fuel Densification Effects in General Electric BWR Fuel," dated August, 1973.
In this report, Nine Mile Point Unit 1 is identified as reactor B.
This General Electric report also defines operating limitations 'I which result from application of the modifications to the models as specified in the enclosure to your letter of July 16, 1973.
Analyses show the most limiting case to be the postulated loss-of-coolant accident.
Limitations on the maximum average lineal heat generation rate at any axial cross section of each fuel bundle will assure compliance with the interim acceptance criteria for emergency core cooling systems.
Specific limits on fuel segment powers are set forth in Section 4 of NEDM-10735, Supplement 6.
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Mr. Dennis L. Ziemann August 14, 1973 The Nine Mile Point Unit 1 can continue to operate in accordance with the Interim Acceptance Criteria without any specific changes in design or operating conditions.
However, until such time as the differences between the densification models of General Electric and the AEC Staff are resolved, Niagara Mohawk proposes to implement operating restrictions on maximum average planar lineal heat generation rate."
This proposed restriction will consist of maintaining the average lineal heat generation rate at any axial cross section of any fuel bundle in the core at a level which is at least limited to values prescribed by the curve labeled beta (g) on Figures 4.9.B of the General Electric report, NEDM-10735, Supplement 6.
Very truly yours, chneider Vice President - Electric Operations
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