ML19259B146
| ML19259B146 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/05/1979 |
| From: | Nelson C Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Eisenhut D, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901160361 | |
| Download: ML19259B146 (4) | |
Text
MEETING
SUMMARY
DISTRIBUTI0fl
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lir. W. P. Stewart Director, Power Production Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Docke: File NRC PDR V. Noonan L PDR P. Check ORB #4 Rdg G. Lainas NRR Rdc G. Kniohton F. Denton Project Manager - C. Nelson E. G. Case OELD V. Stello 0I&E(3)
B. Grimes R. Ingram T. Carter R. Fraley, ACRS(16)
D. Eisenhut TERA A. Schwencer J. Buchanan D. Ziemann Meeting Sum. mary File T. Ic;olito Program Support Branch R. Reid NRC Participants J. Burdoin S. Diab J. Rosenthal E. G. Adensam S. H. Weiss 7 9 0116 0 3 M
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NUCLEAR REGULATORY COMMisslON WASHING TON, 0. C. 20555
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Docket No. 50-302 LICENSEE:
FLORIDA POWER CORPORATION (FPC)
FACILITY:
CRYSTAL RIVER UNIT NO. 3 (CR-3)
SUEJECT:
SUMMARY
OF MEETING HELD ON DECEMBER 19, 1978 REGARDING FORTHCOMING APPLICATION FOR POWER IN REASE A list of attendees is enclosed.
FPC stated that they intend to apply for authorization to increase the licensed ccre power level at CR-3 from 2452 to 2544 MWt. They cesire to effect this increase at the start of Cycle 2 operations, currently scheduled for mid June 1979.
Significant points discussed are summarized below.
1.
FPC and Babcock & Wilcox (B&W) briefed us on the content of their forthcoming power increase / reload submittal.
They ptinted out that since the increased power level was used, in most cases, in the FSAR their submittal was not significantly more complex than a normal reload submittal.
2.
FPC stated that the loss of coolant flow and locked RCP rotor accidents would be reanalyzed. The loss of flow accident analysis would ccasider the RCP power monitor currently being reviewed by the staff.
3.
The schedule for submittal and review was discussed.
Due to the likelihood of ACRS review we stated that SER completion must be scheduled for May 1, 1979 and therefore the complete application must be available to the staff no later than February 1,1979. We also stated that this 3 month review period assumed their submittal would be comparable to a reload submittal.
FPC indicated possible difficulties with this schedule.
They did indicate that meteorological data would be submitted in the near future.
4 FPC was infcrmed that they must either support previously determined radiological consequences as applicable or describe and support any
Olorida Power Corporation changes. We stated that control room habitability would be reviewed and that ECCS leakage outside containment must be considered in dose determinations for LCCA analysis. We also asked if DBA's analyzed for CR-3 were all inclusive when compared with the current Standard Review Plan.
B&W stated that "instru-ment lines or other small line breaks outside contaiament" was not analyzed. We stated that we would inform CR-3 if that was necessary.
5.
Startup testing was discussed.
We informed FPC and 8&W that acceptance criteria as well as more stringent " review" criteria snould be established for the evaluation of startup test results.
Inese criteria should be provided with their power increase relcad subnittal.
FPC and B&W will review this issue further.
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Christian C. Nelson,' Project Manager Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
List of Attendees
Enclosure CR-3 MEETING 12-19-78 POWER INCREASE Name Organization C. Nelson NRC/0RB#4/ DOR J. Burdoin NRC/PDB/ DOR S. Diab NRC/PSB/ DOR J. Rosenthal NRC/RSB/ DOR E. G. Adensam NRC/EEB/ DOR
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