NL-04-0372, Reactor Material Surveillance Program Specimen Withdrawal Schedule Revisions, Additional Information

Reactor Material Surveillance Program Specimen Withdrawal Schedule Revisions, Additional Information

ML040690698
Person / Time
Site:	Farley
Issue date:	03/05/2004
From:	Stinson L Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-04-0372
Download: ML040690698 (4)

Text

L M. Stirison (Mike) Southern Nuclear Vice President Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SOUTHERN A March 5, 2004 COMPANY Energy to Serve YourrWorld' Docket Nos.: 50-348 NL-04-0372 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Reactor Material Surveillance Program Specimen Capsule Withdrawal Schedule Revisions - Additional Information Ladies and Gentlemen:

By letter dated February 23, 2004, Southern Nuclear Operating Company (SNC) provided notice of SNC's plans for withdrawal and analysis of those reactor material surveillance program specimen capsules installed in Farley Nuclear Plant (FNP) Units I and 2 which had been previously designated as "standby" (i.e., with no fixed withdrawal date). This information was provided to NRC for review and concurrence as appropriate.

In a teleconference on March 3, 2004, the NRC staff requested that withdrawal schedules for the standby capsules be provided in a tabular format similar to that used for the capsule withdrawal schedules in the Pressure Temperature Limits Report (PTLR) for each FNP unit, including fluence values for previously withdrawn capsules and projected fluences for the planned capsule withdrawals. The requested information is provided in the enclosed tables.

This letter contains no new NRC commitments. If you have any questions, please advise.

Sincerely, L. M. Stinson LMS/DWD/sdl

Enclosures:

1. FNP Unit I Surveillance Capsule Withdrawal Schedule

2. FNP Unit 2 Surveillance Capsule Withdrawal Schedule P'DOs

U. S. Nuclear Regulatory Commission NL-04-0372 Page 2 cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr., Executive Vice President Mr. D. E. Grissette, General Manager- Plant Farley RTYPE: CFA04.054; LC# 13976 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. S. E. Peters, NRR Project Manager- Farley Ms. T. Liu, NRR License Renewal Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector- Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer

Enclosure 1 FNP Unit 1 Surveillance Capsule Withdrawal Schedule (a)

Capsule Capsule Location Lead Removal Fluence (Degree) Factor EFPY (b) (n/cm2) y(C) 343 3.24 1.15 6.12 x l10' u(c) 107 3.34 3.08 1.73 x 1019 X(c) 287 3.35 6.11 3.06 x 1O' 9 C)110 3.01 12.43 4.75 x 10 19(d)

V(c) 290 3.04 20.16 7.14x 109(c)

Z 340 3.04 -24 8.44 x 1 I9(I(g) 0 Notes:

a) Based on the draft WCAP- 16221 analysis of Capsule V, which updates lead factors and fluence values. Issuance of the final WCAP is expected in March 2004.

b) Effective Full Power Years (EFPY) from plant startup c) Plant-specific evaluation d) This fluence is not less than once or greater than twice the peak EOL fluence for the initial 40-year license term.

e) This fluence is not less than once or greater than twice the peak EOL fluence for a 20-year license renewal term to 60 years.

f) This projected fluence is not less than once or greater than twice the peak EOL fluence for an additional 20-year license renewal term to 80 years.

g) This projected fluence was obtained using draft WCAP-16221, Page 6-16, Table 6-2, "Calculated Azimuthal Variation of Maximum Exposure Rates and Integrated Exposures at the Reactor Vessel Clad/Base Metal Interface." This table projects neutron fluences at various EFPY. The tabulated fluence values for neutrons with E>1.0 MeV were found at 00 azimuth (the peak fluence position) for EFPY values above and below the desired withdrawal EFPY. The fluence value corresponding to the desired withdrawal EFPY was then determined by interpolation from the tabulated values and multiplied by the capsule lead factor to yield the projected capsule fluence value listed above.

Enclosure 2 FNP Unit 2 Surveillance Capsule Withdrawal Schedule (a)

Capsule Capsule Location Lead Removal Fluence (Degree) Factor EFPY (b) (n/cm2)

U(c) 3430 3.31 1.10 6.44x 1018 V(c) 1100 2.86 3.97 1.85 x 10i 9 X(c) 2870 3.41 6.41 3.19 x IO'9 z(c) 3400 3.03 13.24 5.28 x 1 0 9(d)

Y 2900 3.03 -19 7.24 x 10 9(CX)

V 1070 3.47 -22 9.45 x 1019(r)g)

Notes:

a) Based on WCAP-15171 Rev. 1 analysis of Capsule Z, issued in February 2000.

b) Effective Full Power Years (EFPY) from plant startup c) Plant-specific evaluation d) This fluence is not less than once or greater than twice the peak EOL fluence for the initial 40-year license term.

e) This projected fluence is not less than once or greater than twice the peak EOL fluence for a 20-year license renewal term to 60 years.

f) This projected fluence is not less than once or greater than twice the peak EOL fluence for an additional 20-year license renewal term to 80 years.

g) This projected fluence was obtained using WCAP-15171 Rev. 1, Page 6-35, Table 6-13, "Azimuthal Variation of Neutron Exposure Projections on the Reactor Vessel Clad/Base Metal Interface at the Core Midplane - Calculated." This table projects neutron fluences at various EFPY. The tabulated fluence values for neutrons with E>1.0 MeV were found at 00 azimuth (the peak fluence position) for EFPY values above and below the desired withdrawal EFPY. The fluence value corresponding to the desired withdrawal EFPY was then determined by interpolation from the tabulated values and multiplied by the capsule lead factor to yield the projected capsule fluence value listed above.