ML19317G542
| ML19317G542 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/30/1972 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003180845 | |
| Download: ML19317G542 (4) | |
Text
-
.s o
e AEC UISTRIBUh0N FOR PART SO DOCKET MATERIAL
-(TE!GORARY FORM)*
CONTROL HO:
9678 FROM:
DATE OF DOC:
DATE REC'D LTR IEMO RET CTHER Florida Power Corporation St. Petersburg Fla.
J. T. Rodgers 6-90-72 7 6-72 X
TO:
SENT LOCAL PDR X
Mr. DeYounn 1
CIAS3:
PROP _ IIif0 INPUT NO CYS REC'D DOCKET NO:
1 50 102
- DESCRIPfION:
ENCLOSURES:
Ltr re our 6-1-72 ltr, trans the following:
Babcock & Wilcox Topical ReI sr Crystal River Unit # 3 IOTE:
- Indicates Ltr Only 10 \\!0.. REMOV_:
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PLANT NA!ES: Crystal River Unit # 3
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FOR ACTIO:i/INFORMATICI; 7-7-72 AB BUfLER(LJ ENIEL(L)
VASSALLO(L)
ZIEMANN(L)
KNIGHT 0H(EINIRO W/ Copies W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)
/SCHWENCER(L)
H. DENTON CHITWOOD(FM)
W/ Copies W/ 2 opies W/ Copies W/ Copiesu W/ Copies C
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./GRDES-L BROWN-L L/A PWR OGC-RM P-506 VPAWLICKI-L
/GAMMILL-L WILSON-L L/A PWR MUNTZIIU & SIAFF "fHOMPSON-L VINIGHTON-ENVIRO
- KARI-L L/A EWR VGIAMBUSSO-L
- M'EDESCO-L
- VDICXER-EINIRO
+ S4ITH-L L/A EWR BOYD-L-BNR VLONG-L
/ PROJ LDR EINIRO:
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- VLAINAS-L Sells DIGGS-L L/A VMULLER-L-E?NIRO
- SHAO-L SALTZMAN-IND.
TEETS-L L/A SKOVHOLT-L-OPER /EENAROYA L
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- WADE-L L/A EINIRO 6
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- DUEE-L SMILEY-FM HARLESS-ENVIRO SCHROEDER-L a/ E. CASE-L
- P. COLLINS-L EXTERNAL DISrRIEUTION y l-LOCAL FDR crvn+n1 Riv,v. pl a _
l-SAN /LA/NY--FDR el-DfIE-(LAUGHLIN) 9-NATIONAL LAB'S 1-CHIEF WATER REACTORS
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Regt(!gtory deCy
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FLOHIDA POWER C O R P O R ATI ON ST. PETERSDt;HG FIDHIDA June 30, 1972 Mr. R. C. DeYoung Assistant Director for Pressurized Water Reactors Directorate of Licensing-
'~
United States Atomic Energy Commission Washington, D. C.
20545 In re:
Florida Power Corporation Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302
Dear Mr. DeYoung:
Attached please find a current compilation of Babcock & Wilcox Company topical reports, which support our application for an operating license for the Crystal River Unit #3 Nuclear Generating Plant, as was requested in your letter of June 1,1972.
We will, in the near future, update the FSAR to properly include these reports by reference.-in the appropriate sections.
Please contact us if further clarification or discussion is required.
Very truly yours, J.
. Rodgers Assistant Vice President &
Nuclear Project Manager JTR/pab Attachment
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DATE
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B&W 'OPICAL REV.
SUBMITTED T
REPORT NO.
TITLE NO.
TO DRL BAW-I0001 Incore Instrumentation Test Program-8/69 BAW-10003-
' Qualification Testing of Protection System
~
Instrumentation-1 6/72 BAW-10006 -
Reactor Vessel Material Surveillance Program 1
2 9/71 BAR-10008 Part 1 - Reactor Internals Stress & Deflection Due to LOCAEand Maximum Hypothetical Earthquake 1
6/70 BAW-10009 ~
-Effect of Fuel Rod Failure on Emergency Core 6/70 Cooling B AW-10010 Part 1 - Stability Margin for Xenon Oscilla-8/69 tions - Modal Analysis BAW-10010 Part 2 - Stability Margin for Xenon Oscilla-3/70 tions - One-Dimensional Digital Analysis BAW-10010-Part 3 - Stability Margin for Xenon Oscilla-tions - Two-and Three-Dimensional Digital 1
6/71 Analysis BAW-10013 Study of:Intergranular Separations in Low
~ Alloy Steel - Heat Affected Zones Under 1
2/72 Austenitic Stainless Steel Weld Cladding BAW-10017 Stability & Compatibility of Sodium Thiosulfate Spray Solution - R&D Report (PROPRIEIARY) 1 5/70
-BAW-10018 Analysis of'the Structural Integrity of a 5/69
~ Reactor Vessel Subjected to Thermal Shock
-BAW-10019 Systematic Failure. Study of Reactor Protective 9/ 70
-Systems.
BAW-10021 TEMP - Thermal Enthalpy Mixing Program-
- 4/70 BAW-10024-Effectiveness of < Sodium Thiosulfate Sprays for 1/71 Iodine Removal _ (Nonproprietary Version of BAW-10022)
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B&W TOPICAL
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DATE REV.
' SUBMITTED REPORT NO.--
TITLE NO.
~TO DRL BAW-10027-Once-Through Steam Generator Research and 4/71-Development Raport (Nonproprietary Version of BAW-10002)
BAW-10029-
-Control Rod' Drive-System Test (Nonproprietary ~
1/72 Version' of BAW-10007, Rev.1)
BAW-10030
.- CRAFT - Description of Model for Equilibrium 10/71 LOCA Analysis Program
.BAW-10031 REFLOOD --Description of Model for Multinode Core Reflood. Analysis 1
5/72 De'ay Heat Peaking BAW-10033 c
10/71 BAW-10034~
Multinode Analysis. of B&W's-2568 Wt Nuclear Plants.During a LOCA 1
2 3
5/72 BAW-10035
. Fuel Assembly Stress & Deflection Analysis.
-1/72
.Due-to LOCA and Seismic. Excitation (Non-proprietarf Version.of BAW-10008, Part 2, Rev.1)
.BAW-10037
- Reactor Vessel-Model Flow Tests (Nonproprietary 2/72
' Version'of BAW-10012-BAW-10043
-Overpressure. Protection for~ B&W's Pressurized 5/72 Water Reactors i
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