ML20206J745
| ML20206J745 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/23/1988 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 GL-88-11, NUDOCS 8811290103 | |
| Download: ML20206J745 (2) | |
Text
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Alab m;PowerComparty e
r? North 10th Street Nf,te Dox 2641 m7,yiam, Alabama 35291-0400 4--
'1e 205 250 '837 W. G. rielrste n, lit Senior Vice President Nuclear Operabons lab maPOWCT the Southern elecinc system November 23, 1988 Docket Nos. 50-348 50-364 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Vashington, D.C.
20555 Gentlemen:
NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations (Generic Letter 88-11)
Generic Letter 88-11 requested submittal of the results of a technical analysis of the use of the methodology contained in Revision 2 to Regulator; Guide 1.99 to predict the effect of neutron radiation on reactor vessal materials.
In the event that actions are necessary, such actions are to be completed within two plant outages (approximately three years).
A echnical anelysis was completed for the Parley Nuclear Plant (FNP) Units 1 and 2 reactor vessels in accordance with the request of Generic Letter 88-11 relative to the implementation of Revisic:,2 to Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Mat.eria)"."
This technical analysis shoved that, for Unit 1, the current neatup and cooldovn limits in the Technical Specifications are bounded by the nov methodology of Revision 2 to Regulatory Guide 1.99.
For Unit 2, however, new heatup and cooldown licits vill be required.
To this end, new heatup and cooldovn curves vill be generated afeer analysis of the next surveillance capsule data at approximately 6 EFPY.
This capsule is to be removed during the FNP Unit 2 refueling outage scheduled for the Spring of 1989.
Appropriate changes to the Technical Specifications should be submitted to the NRC by June 1990 and, pending NRC approval, revised heatup and cooldovn curves can be in effect prior to startup following the subsequent refueling outage for FNP Unit 2 scheduled for the Fall of 1990.
Relative to the potential incorporation of the calculational methods of Regulator) Guide 1.99 Revision 2 into the PTS Rule, the reference temperatures for all FNP Units 1 and 2 reactor vessel materials at end-of-life (32 EFPY) are below the current screening criteria.
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.U. S. Nuclear Regulatory Commission Page 2 If you have any questions, please advise.
Respectively Subaitted, ALABAMA POWER COMPANY i
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V. G. Hairston, III VGH,III/JARipr-2.24 cci Mr. L. B. Long i
Mr. M. L. Ernst Mr. E. A. Reeves Mr. G. F. Maxwell 1
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