ML19319D191
| ML19319D191 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/11/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130782 | |
| Download: ML19319D191 (3) | |
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NRC DISTHIBUTION on PART 50 DOCKET fAATERIAL rida Power & Light Company 10/11/76
!!r. John Stolz S t.
Petersburg, Flc.
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oCGCSIPTION ENCLOSURE 4
Ltr. trans the following:
" Evaluation and Comparison of Calculated System Head Loses and Reactor Building Sump Test System liead Loses Relative to Crystal River Unit No. 3."
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October 11, 1976 l v.s. nnan u,,u
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Mr. John Stolz j
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p' Light Water Reactors Branch 1 Division of Project Management Rl
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U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit No. 3 Docket No. 50-302
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I. car Mr. Stolz:
Attached are three (3) copies of the report entitled " Evaluation and Com-parison of Calculated System Head Losses and Reactor Building Sump Test System Head Losses Relative to Crystal River Unit No.
3."
This report presents the results of a design review and evaluation performed to compare the calculated fluid frictional losses with the Reactor Building Sump flow test data, relative to Decay Heat Removal and Reactor Building Spray Pumps suction systems from the Reactor Building Sump, for CR#3.
This submittal should complete Florida Power Corporation's documentation of all informr. tion used in our discussions and responses concerning our Test Program for compliance with Reg. Cuide 1.79.
Please contact this office if additional discussion is required.
Very truly yours,
/s/
J. T. Rodgers J. T. Rodgers Asst. Vice President JTR/jw Attachments E. $.ltj General Office 3201 Thiny.tounn street soutn. P.O. Box 14042, st. Petersburg. Fionca 33733 e 813-866-5151
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- %26et NINNI Fh04ANBf october 11, 1976
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Mr. John Stol:
Branch Chief Light Water Reactors Branch I
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Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit No. 3 Docket No. 50-302
Dear Mr. Stolz:
We are forwarding to you under separate cover three (3) copies of the report entitled " Evaluation of Calcilated System Head Losses and Reactor Building Sump Test System Head Losses Re-lative to Crystal River Unit No.
3."
This report presents the results of a design review and evaluation performed to compare the calculated fluid frictional losses with the Reactor Building Sump flow test data, relative to Decay Heat Removal and Reactor Building Spray Pumps suction systems from the Reactor Building sump, for CR# 3.
This submittal completes Florida Power Corporation's documenta-tion of all information used in our discussions and responses concerning our Test Program for compliance with Reg. Guide 1.79.
Please contact this office if additional discussion is required.
Very truly yours, J.
T. Rodg s
Asst. Vice President
'JTR/iw F.,,...
General Office 32ci Tnirty-fourtn street soutn. P O Box 14042. St Petersburg, Rorida 33733 e 813--866-5151