ML20101J583
| ML20101J583 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/27/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20101J586 | List: |
| References | |
| NUDOCS 9604020053 | |
| Download: ML20101J583 (2) | |
Text
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Duquesne @ Company 8 v;vy v eo si aea Shippingport. PA 15077-0004 i
March 27,1996 susan. c..uun g,,33,33si, Divt Vice President Fax (412) 643-8069 Nuclear Power Division U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Reactor Vessel Capsule V Test Report Attached is a copy of WCAP-14484 " Analysis of Capsule V from the Duquesne Light Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program."
This report provides a technical summary of the results of the mechanical property tests conducted on the second capsule to be withdrawn and is provided in accordance with 10 CFR 50 Appendix H, Section III.
This report includes the data required by ASTM E185 as specified in 10 CFR 50 Appendix H paragraph II.B.1. The analysis results support that no change in tecimical specifications is currently required, either in the pressure-temperature limits or in the operating procedures required to meet the limits. The capsule analysis results will be used to determine the appropriate technical specification changes for operation beyond the 10 effective full power years currently approved for the heatup and cooldown curves.
Section 5.1 of WCAP-14484 provides notification that the capsule V dosimeter block numbers previously identified in WCAP-9615 were in error and should be 414 through 419 instead of 354 through 359. In addition, Section 7.0 of WCAP-14484 provides updated capsule lead factors, withdrawal schedules and fluence values from those currently provided in Unit 2 UFSAR Table 5.3-6. The update is based on state-of-the-art methodology and nuclear data including recently released neutron transport and dosimetry cross-section libraries derived from the ENDF/B-VI data base. 10 CFR 50 Appendix H, Section II.B.3 requires prior NRC approval before these changes can be implemented; therefore, NRC approval of the changes identified in WCAP-14484 Table 7-1 is requested by January 31,1997.
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Beaver Valley Power StEtion, Unit No. 2 Reactor Vessel Capsule V Test Report Page 2 If you have any questions regarding this submittal, please contact Mr. G. S. Sovick at (412) 393-5211.
Sincerely, Sushil C. Jain c:
Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager I
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