ML20135F754
| ML20135F754 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/07/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135F756 | List: |
| References | |
| NUDOCS 9703130424 | |
| Download: ML20135F754 (3) | |
Text
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4 Dave Morey S uthern Nuct:ar Vice President Operating Company Farley Project RO. Box 1295 Birmingham. Alabama 35201 Tel 205.992.5131 3
March 7, 1997 SOUTHERN C.OMPANY Energy to Serve Your World' Docket No.:
50-348 10 CFR 50.90 50-364 I,
U. S. Nuclear Regulatory Commission ATI'N: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Steam Generator Tube Smoort Plate Voltane-Based Renair Criteria a
Ladies and Gentlemen:
By letter dated December 26,1997, Southern Nuclear requested approval of a technical specification amendment concerning steam generator tube support plate voltage-based repair criteria. As part of the request, an increased steam line break leakage limit based on ICRP-30 dose conversion factor was requested. Questions have recently arisen concerning the calculation of the steam line break leakage limit. As a result, the NRC Staff has requested that the calculation documenting the steam line break leakage limit be submitted for review.
Enclosure i provides a copy of the requested calculation based on ICRP-30 dose conversion factors used for the technical specification amendment request. Enclosure 2 provides the results from a similar calculation using ICRP-02 dose conversion factors. A comparison of the results reveals that the doses calculated with the ICRP-30 dose conversion factors are less than those
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calculated using ICRP-02.
The calculation provided in Enclosure 1 uses the same methodology as that provided by Southern Nuclear letter dated June 4,1992. ICRP-30 dose conversion factors are used in the calculation.
This methodology has been the basis for the leakage limits used for all Farley Units 1 and 2 steam generator technical specification amendments since its inclusion in a 1993 safety ev i
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U. S. Nuclear Regulatory Commission Page 2 If you have any questions, please advise.
Respectfully submitted, SOlmIERN NUCLEAR OPERATING COMPANY j
9/ ?Arta Dave Morey Sworn to andsubscribed before me this day of M 6h I997 Yb YR,(0.4 I
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NotaryPublic (
My Commission Expires:
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REM:DOSECAL2. DOC
Enclosures:
- 1. Calculation based on ICRP-30 2.
Results of calculation based on ICRP-02 cc:
Mr. L. A. Reyes, Region II. Administrator Mr. J. I. Zimmerman, 'NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health
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a ENCLOSURE 1 Calculation based on ICRP-30 y
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