ML20238E114
| ML20238E114 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/29/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-3652C, NUDOCS 8801050006 | |
| Download: ML20238E114 (2) | |
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Georgia Power Cornpany 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-6526 Malhng Address:
Post Office Box 4545 Atlanta Georgia 30302.
Georgia Power
'L.T.Gucwa
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Manager Nuclear Safety.
and Licensing SL-3652c 1827C X7GJ17-H600 December 29, 1987 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Hashington, D. C.
20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 CLARIFICATION OF ADMINISTRATIVE CONTROLS REGARDING SUBMITTAL OF START-UP REPORTS Gentlemen:
Georgia -Power Company is providing this letter in response to a request made during phone conversations with NRC Project Management and Reactor Core Analysis Branch regarding summary reports on plant start-up and power escalation testing.
Specifically, Georgia Power. Company contacted the NRC for guidance relative to when and under what conditions such a start-up test report would be required.
The following information provides our views as discussed with NRC staff relative to those requirements.
Technical Specification 6.9.1.1 (both units) states, in part, that "A summary. report of plant startup and power escalation testing shall be submitted following... (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier...".
He : believe the requirement for submittal of a summary report is intended to address those occasions when a "significant" number of fuel bundles of a different design or manufacture are inserted in the core.
A different design would be one that has not been previously reviewed and accepted by the NRC or not utilized in the industry.'
He do not believe, specifically, that-this requirement is intended to cover those occasions where a small number of bundles, typically 4 or fewer, are inserted into a' reactor as part of either a fuel vendor's developmental process, or the utility's qualification process of an alternate fuel supplier.
This r;hef is further strengthened by the observation that this small number of bundles would not appreciably impact the results of tests included as part of the start-up test program.
The start-up test program normally cor.sists of:
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GeorgiaPower d U. S. Nuclear Regulatory Commission December 29, 1987 Page Two A.
Core Verification B.
Control Rod Drive Friction Testing C.
Control Rod Drive Timing D.
Full Core Shutdown Margin Demonstration E.
Cold Critical Eigenvalue Comparison F.
Whole Core LPRM Calibration G.
APRM Calibration H.
Control Rod Scram Time Testing I.
TIP Reproducibility and Asymmetry Calculations J.
Reactivity Anomaly Calculation Should GPC determine that for some reason the lead test bundles affect test results, or if a reload consists of a significant number of fuel bundles with a different design or from a different manufacturer, we will submit the results of our start-up tests to the NRC.
Please contact this office if you have questions or comments regarding this clarification.
Sincerely, efs;9" L. T. Gucwa GKM/lc c: Georaia Power Comp _any Mr. J. P. O'Reilly, Sr. Vice President - Nuclear Operations Mr. J. T. Beckham, Jr., Vice President - Plant Hatch GO-NORMS U. S. Nuclear Regulatory Commission. Washinoton. D. C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U. S. Nuclear Reaulatory Commission. Reaion II Dr. J. N. Grace, Regional Administrator Mr. P. Holmes-Ray, Senior Resident Inspector - Hatch 1827C
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