ML20212N018
| ML20212N018 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/05/1987 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| Shared Package | |
| ML20212N019 | List: |
| References | |
| NUDOCS 8703120313 | |
| Download: ML20212N018 (2) | |
Text
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MAR 51987
. : Docket No. 50-285:
DISTRIBUTION
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Qocket Fil'e>
JPartlow NRC PDR NThompson
' Mr. ' R. L. Andrews L PDR Gray File Division Manager - Nuclear Production-P8D#8 Rdg PKreutzer Omaha Public Power District
_FMiraglia WPaulson 1623 Harney Street OGC-Beth BGrimes Omaha ~, Nebraska 68102 EJordan ACRS-/0
Dear Mr. Andrews:
SUBJECT:
PROJECTED VA' LUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS _FOR PROTECTION AGAINST PRESSURIZED, THERMAL SH0CK EVENTS The NRC staff has completed the review of your letter dated January 23, 1986, and the supplemental information in your May 7,-1986 letter, which you submitted in response to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for the-Fort Calhoun Station,-Unit No.
1~.
The staff's Safety Evaluation is enclosed.
The staff finds that the material properties of the reactor vessel beltline
. material.are acceptable.
The staff also finds the projected fluence at the
~
inner surface o_f the' reactor vessel at the expiration date of the license (June'7, 2008) and the calculated RT at the expiration date of the license to be acceptable based on an evaluat$M at 32 effective full power years of operation.
The Fort Calhoun reactor is projected to have less than-32 effective full power years of operation at the expiration date of the license.
The calculated RT is below the screening criterion of 270 F
~
of 10 CFR 50.61.
Thismeet$TkherequirementsofthePTSRule.
The PTS Rule requires that the projected assessment of the RT be updated wheneverchangesincoreloadings,surveillancemeasurements,pNother information (including changes _in capacity factor) indicate a significant change in the projection values.
This ensures that the licensees will track the fluence at the limiting beltline materials throughout the life of the plant to verify their assumptions.
In this regard, we request that you submit are-evaluationoftheRT[kalswhicharerequiredby10CFRPart50,AppendixG.
and comparison of the predicted value with future Pressure-Temperaturesubm$
This request for information was approved by OM8 under clearance number 3150-0011 which expires September 30, 1989.
Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C.
20503.
Sincerely, 8703120313 870305 PDR ADOCK 05000285 6ngDW dgnedy P
PDR Walter A. Paulson, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosure:
Safety Evaluation cc w/ enclosure:
See next pa P80#9 PBD#E PBD#8 P6Mdtker WPap/87 1
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.Mr. R. L. Andrews Fort Calhoun Station Omaha Public Power District Unit No. 1-cc:
Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission
-P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Harold Borchert, Director Division of Radiological Health Department of Health-301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509
.