ML20072U411

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Forwards BAW-2125, Analysis of Capsule TE1-D,Toledo Edison Co,Davis Besse Nuclear Power Station Unit 1,Reactor Vessel Matl Surveillance Program. Results Indicate That Pressure Temp Operating Limits Conservative
ML20072U411
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/11/1991
From: Shelton D
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20072U414 List:
References
1906, NUDOCS 9104190130
Download: ML20072U411 (2)


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V N RGY Donald C. Shelton 300 Madson Avenue Vce President Nuclear Toledo, Ott 43652 0001 Davis Besse (419)2 4 2300 Decket Number 50-346 License Number NPF-3 Serial Number 1906 April 11, 1991 United. States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.

20555 Subj ect :

10 CFR 50, Appendix H Report of Reactor Vessel Material Surveillance Program Test Result for Davis-Besse Nuclear Pover Station, Unit 1 Gentlemen:

10 CFR 50, Appendix H, requires licensees to have a reactor vessel

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materials surveillance program. The purpose of the program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor _ vessel beltline region resultIng from exposure of these materials to neutron irradiation and the thermal environment associated with reactor operation.

Under the program, fracture toughness test dt.ta are obtained from surialliance capsule material specimens which are periodically vithdrawn from the reactor vessel.

The schedule for. withdrawal of Davis-Besse Nuclear Power Station

.-(DBNPS),, Unit 1 surveillance capsules is contained in Babcock and V11cox (B&V) Topical Report, DAV-1543A, "Haster Integrated Reactor Vessel Surveillance Program," which was_ approved by the Nuclear Regulatory Commission (NRC) staff in 1985. The test data ate obtained from examination of the material specimens used in accordance with 10 CFR 50, Appendix G, " Fracture Toughness Requirements," to update Technical Specifications pressure / temperature operating limits.

The fourth surveillance capsule (TEl-D) for DBNPS_vas withdrawn from the-reactor vessel during the clxth refueling outage.

The sixth

' refueling outage ended in July 1990.

The enclosed B&V Nuclear Service Company report, BAV-2125, " Analysis of Capsule TEl-D - The Toledo Edison Company DBNPS, Unit 1 Reactor Vessel Material Surveillance Program," describes the results of the examinntions performed on surveillance capsule, TEl-D.

The report is submitted for NRC information in accordance with 10 CFR 50, Appendix H.

The test results

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confirm that'the existing Technical Specifications pressure /

temperature operating limits are conservative and remain valid through ten effective full power years of operation.

9104190130 910411 FDR ADOCK 05000346 P

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Operenng Compomes Clevetand Oectnc IHumanonng i

Toledo Ed: son

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Docket Numbar 50-346

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' License Number NPF-3 Serial Number 1906 Page 2 Should you have any questions regarding the information provided by this letter, please contact Mr. R. V. Schrauder, Manager - Nuclear Licensing, at_(419) 249 2366.

Very truly yours,

- h b[k

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PVS m attachments cc P. H. Byrt,n, DB-1 NRC Senior Resident Inspector A. B. Davis, Regional Administrator, NRC Region III J. R. Hall, NRC Senior Project Manager H. D. Lynch, NRC Senior Project Manager Utility Radiological Safety Board L

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