ML20214R537
| ML20214R537 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/26/1986 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20214R539 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8612080012 | |
| Download: ML20214R537 (2) | |
Text
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.i November 26, 1986
. Docket No. STN-50-454.
d B. Grimes NRC PDR-N. Thompson Local PDR J.-Partlow PD#3 Rdg.
C. Vogan
-Mr. D. L. Farrar-
.T. Novak L. Olshan Director of Nuclear Licensing OGC ACRS(10)
Comonwealth Edison Company E. Jordan Post Office Eox 767
- Chicago,' Illinois 60690
Dear Mr. Farrar:
SUBJECT:
PROJECr VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIVMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS
'We have reviewed your letter dated January 17, 1986 which was submitted in response to the Pressurized Themal Shock (PTS) Rule,10 CFR 50.61, for Byron Station, Unit 1.
We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor for the end vessel for the end of life of the plant and'.the calculated RT ~ bN below the The calculated RT of life of the plant to be acceptable.
screeningcriteriaof270 Fat 32EFPY,whichisbeyondtN3 expiration date of the license and, therefore, meets the requirements of the PTS Rule.
must be-The PTS Rule requires that the projected assessment of the RT updatedwheneverchangesincoreloadings,surveillancemeasuMentsorother infonnation (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensee will track the accumulated fluence for the limting beltline materials throughout the life of the plant to verify that their assumptions remain valid.
In this regard we and comparison of the request that you submit a re-evaluation of the RT predictedvalueinanyfuturePressure-Temperatur$Tkubmittalswhichare submitted as required by 10 CFR 50, Appendix G.
Our associated Safety Evaluation is enclosed.
Sincerely, Leonard N. Olshan, Project Manager Project Directorate #3 Division of PWR Licensing-A
Enclosure:
As stated cc: See next page PDf3
,3 PD#3 b
- Olshan
- mak ra CVoo n 11/
86 11/2h/86
/86 8612080012 861126 DR ADOCK 0500 4
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's Mr. Dennis L. Farrar Pyron Station Commonwealth Edison Company Units 1 and 2 l
cc:
Mr. William Kortier Ms. Diane Chavez Atomic Power Distribution 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III U. S. Nuclear Regulatory Commission Michael Miller 799 Roosevelt Road Isham, Lincoln & Beale Glen Ellyn, Illinois 60137 One First National Plaza 42nd Floor Joseph Gallo, Esq.
Chicago, Illinois 60603 Isham, Lincoln & Beale Suite 1100 Mrs. Phillip B. Johnson 1150 Connecticut Avenue, N.W.
1907 Stratford Lane Washington, D. C.
20036 Rockford, Illinois 61107 Douglass Cassel, Esq.
Dr. Bruce von Zellen 109 N. Dearborn Street Department of Biological Sciences Suite 1300 Northern Illinois University Chicago, Illinois 60602 DeKalb, Illinois 61107 Ms. Pat Morrison Mr. Edward R. Crass 5568 Thunderidge Drive Nuclear Safeguards & Licensing Rockford, Illinois 61107 Sargent & Lundy Engineers 55 East Monroe Street Ms. Lorraine Creek Chicago, Illinois 60603 Rt. 1, Box 182 Manteno, Illinois 60950 Pr. Julian Hinds U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Offices 4448 German Church Road Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive Springfield, Illinois 62704
,