ML20215K717
| ML20215K717 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/19/1987 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| NUDOCS 8706250424 | |
| Download: ML20215K717 (3) | |
Text
June 19, 1987 Docket No. 50-302 Mr. W. S. Wilgus D_ISTRIBUTION Vice President, Nuclear Operations
<DocketeFileg OGC-Bethesda Florida Power Corporation NRC PORs E. Jordan ATTN: Manager, Nuclear Licensing Local PDRs J. Partlow P.O. Box 219 PD22 Reading ACRS (10)-
Crystal River, Florida 32629 S. Varga Gray File G. Lainas
Dear Mr. Wilgus:
D. Miller H. Silver In order to permit us to complete our review of your Crystal River Unit 3 Technical Specification Change Request No. 152, Cycle 7 Reload, responses to the enclosed Request for Additional Information are required.
Please furnish your responses within 30 days of the date of this letter to assure that the desired schedule can be maintained.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
/s/
Harley Silver, Senior Project Manager Project Directorate Il-2 Division of Reactor Projects-I/II
Enclosure:
As Stated j
cc w/ enc.losure:
See next page Qf LA:PDII-2 PM:PDII-2 PD:PDII-2 0 Miller HSilver:bg LRubenstein 6/ /87 6/g/87 6/jf/87 l
8706250424 870619 PDR ADOCK 050 2
P i
s Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee Mr. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Mr. E. C. Simpson Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Florida Power Corporation Support 1
Suite 220, 7910 Woodmont Avenue P.O. Box 219 Bethesda, Maryland 20814 Crystal River, Florida 32629 Resident Inspector U.S. Nuclear Regulatory Commission 15760 West Powerline Street Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 1
Attorney General Department of Legal Affairs l
The Capitol Tallahassee, Florida 32304
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l ENCLOSURE j
REQUEST F0f< ADDITIONAL INFORMATION CRYSTAL RIVER UNIT 3 CYCLE 7 RELOAD 1.
Justify that the increased bypas's flow of 8.8% used in the thermal-hydraulic design evaluation for a full Mark BZ core provides sufficient margin to offset the core penalty required for the Cycle 7 nixed core of Mark BZ and Mark B fuel assemblies.
2.
The licensee has proposed to eliminate any reference to the DNB correlation used or the limiting DNBR value in the Bases for Tech Spec 2.1.1 and 2.1.2.
Although the staff has previously accepted the removal of the ONBR limiting value, we require that the particular correlation (s) used for the most recent core continue to be referenced in the Bases.
3.
Provide details on the reevaluation of the boron dilution event indicating why a reevaluation was required and justifying that the resulting time available for the operator to take corrective action meets the requirements of SRP 15.4.6.
3.
The Cycle 7 control rods will differ from those used'in previous cycles.
Provide a reference where the use of this type of control rod has been previously approved by the NRC. Since no mention of these new rods is made in the Cycle 7 reload report, verify that the Cycle 7 values of rod worths, shutdown margin, etc., reflect the use of these new control rods?
5.
Provide references for the NRC's previous. acceptance of the revised power imbalance detector correlation to justify the reduction-from 3.5% to 2.5%.
.