ML19259C496
| ML19259C496 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/15/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906220204 | |
| Download: ML19259C496 (3) | |
Text
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( O 6s P s J H A f f O g June 15, 1979 Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operatiag Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
In response to the request of the NRC Review Team assigned to CR#3, Florida Power Corporation hereby submits the attached table which lists a comparison between the key parameters used in the B&W Small Breaks Analyses and the actual equipment parameters at Crystal River Unit 3.
The parameters identified in the table for the B&W analysis were taken from the B&W report entitled " Evaluation of Transient Behavior and Small Reactor Coolant Systems Breaks in the 177-Fuel Assembly Plant", dated May 7,1979.
This table demonstrates that the generic B&W Small Breaks Analysis conservatively envelopes the Crystal River Unit 3 design parameters and is therefore applicable to Crystal River Ur.it 3.
Very truly yours, FLORIDA POWER CORPORATION U ~QL6
]gj j]7 W. P. Stewart Manager Nuclear Operations RMBekcF05(D3)
Attachment File:
3-0-3-a-3 General Office 320i Tniny.founn street soutn. P O Box 14042 St Petersbu g F!onda 33733 813 e66 5151 r
79062202o9
s Attached is a table which l'sts a omparison b2 tween juranetern omd in the IOCA analyses presented in i he retort, " Evaluation of Transient Behavior and small Reactor Coolant Systems Breaks in the 177-Fuel Asseably Plant",
May 7,1979, and the actual equipnent at Crystal River 111.
TAB 1,E - CtX.iPAlt1StVJ OF PAlWil?l'EliS Analys i_s Cid Power level, Mit 2827 6152 Reactor trip pressure, psig 1885 1900(b)
ESPAS trip pressure, psig 1350 1500 HPI punp infonwition No. of puq m '
1( )
2 1-lw at 600 psig RCS pressure, gpa/punp 500 500 Shutoff head, psig 2800 2"00 D21ay tien, see 35 25 Auxiliary feedwater punp int onnation No. of punps 1
2 Plow at 1050 psig SG pressure, gpnV'punp 550 720 Rod worth, ?..tk/k 2.26 H.8 Electronutic Relief Valve 2
Cross Sectional Are'a, ft 0.0073 0.0041 (a)
In Sections 6.2.1 and 0.2.2, two IIPI punpc were utilized in the analysis.
(b) Based on RCS pressure - variable laa trip.
2281 128 Mright(smlBktronp)lu7
r STATE OF FLORIDA COUNTY OF PINELLAS W. P. Stewart states that he is the Moridger, Nuclear OperdLions, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attac.ned hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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W. P. Stewart Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 15th day of June, 1979.
Notary Public Notary Public, State of Florida at Large, My Commission Expires:
July 25, 1980 2281 129 (CRPNotary 1 D12)