ML20198F284
| ML20198F284 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 01/07/1974 |
| From: | Stello V US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| CON-WNP-0939, CON-WNP-939 NUDOCS 8605280460 | |
| Download: ML20198F284 (5) | |
Text
JAt: 7 WI Docket lo.: 50-460 R. C. DeYoung, Assistant Dimetor, for L1Qht Water Reactors, Group 1 IfiPUT TO WPPSS-1 SER Plant tiame:
WPPSS-i Licensing Stage:
CP Docket !io.:
50-460 Responsible Branch LWR Project Branch 1-1 and Project !!anager:
Tom Cox Technical Review Branch Involved:
Core Perfortance Branch Requested Completion Date:
12/28/73 Description of Review:
Input to SER, Section 4.2.1 The attacbrant is subaitted as input to secticr. 4.2.1, Fuel flechanical Design, for the WPPSS-1 SER.
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Victor Stello, Jr., Assistant Director for Reactor Safety Directorate of Licensing cc:w/Attachnent:
S. Hanauer J. liendrie A. Gla!;1Dusso W. IkDonald A. Sdmencer T. Cox
- 0. Ross D. liouston L. Rubenstein L Reading CPB Reading L:RS A6ainistrative Assistant Docket File Victor Stello, Jr., AD/RS 860528046o 740107 PDR ADOCK 05000460 E
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I WASHINGTON, D.C. 20545 JAfl 7 1374 Docket flo.: 50-460 R. C, DeYoung, Assistant Director, For Light Water Reactors, Group 1 WASHIflGT0il PUBLIC POWER SUPPLY SYSTEM fl0. 1 Plant flame:
WPPSS-1 Licensing Stage:
CP Docket tio.:
50-460 Responsible Branch LWR Project Branch 1-1 and Project Manager:
Tom Cox Technical Review Branch Involved:
Core Performance Branch Requested Completion Date:
12/28/73-Description of Review:
Round One Questions The attachment contains the round one questions to section 4.2.1, Fuel Mechanical Design, for the WPPSS-1 SER.
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- f[ictor Stello, Jr!, Assistant Director gf; ~ W2 '-
for Reactor Safety Directorate of Licensing cc w/
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S. Hanauer J. Hendrie A. Giambusso W. I'400nald A. Schwencer T. Cox D. Ross D. Houston L. Rubenstein L. Reading CPB Reading L:RS Administrative Assistant S. Varga 1
ATTACHMEtiT QUESTIONS ON WPPSS 4.2.1 Fuel Mechanical Desian
- 4.2.1.1 - The tiark C fuel assembly is a new fuel design. We understand that the conservative design philosophy employed in the Mark B design is used for the Mark C.
In addition, lower fuel temperatures are expected in the new design due to lower linear heat rates.
Provide a table of comparison between the Mark 8 and C designs verifying that the structural adequacy and margins of safety are conservative.
4.2.1. 2 - Provide additional information in regard to fuel rod design as follows:
a.
A drawing of the fuel rod, similar to Figure 4.2-2, with dimensions. A drawing of the fuel pellet with dimensions should also be provided.
b.
The nominal helium fill gas pressure in the fuel roa, and include the upper and lower tolerance limits.
In addition, describe the prepressurization process and the inspection procedures for verification.
c.
Deflection design specifications and experimental observations for the lower plenum spring.
Is there evidence of permanent deflection due to_ fuel rod and fuel assembly handling? Would gradual deflection of this spring as a function of irradiation be expected and what is the maximum deflection, both expected and possible?
4.2.1.3 - Provide the following information in regard to fuel rod performance:
a.
The design analyses for Zr-4 irradiation growth and supply supporting data or references.
b.
The power history used to calculate fission gas released.
c.
Justify use of 425"F as the limit at which "all significant hydrides have had a chance to precipitate
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4.2.1.3(cont'd)- under a favorable stress field." Define what is meant by "all significant hydrides."
d.
Limits on specifications of absorbed gases and moisture in fuel rods.
e.
The cleaning procedure applied to internal and external surfaces of cladding just prior to pellet loading.
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$ 4.4 Thermal and Hydraulic Design 4.4.2.10 - Provide fuel centerline temperature, volumetric average fuel temperature, and gap conductance as a function of Kw/ft for beginning of life, end of cycle 1, and 55,000 mwd /mtU burnup.
Provide information as a function of burnup for 100%
ower and nominal dimensions for a) gap conductance, b) hot gap size, (c) clad I.D.,
d) gas pressure and thermal conductivity, (e) volumetric average temperature, and (f) centerline temperature. State whether the effects of densification are included in these calculations.
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Y g%1 Docket No.: 50-460
- 9. C. DeYoung, Assistant Director, For Light Water Reactors, Group 1 14AS!!INGTO:1 PUBLIC POWER SUPPLY SYSTGI 110.1 Plant ifare:
WPPSS-1 Licensing Stage:
CP Docket flo.:
50-460 Responsible Granch LWR Project Branch 1-1 and Project :ianager:
Tom Cox
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Technic:ll P.eview Cranch Involved:
Cora Perfortunce Branch ReqJestad Ccupletion Cate:
12/28/73 Descri? tion of P.eview:
Round One Questicns The attachmnt contains the round one questions to section 4.2.],
Fual Mechanical Destgr., for the WPPSS-1 SER.
Odginal signed by '
Victor Shl!o Victor Stello, Jr.. Assistant Director for Reactor Safety Directorate 6f Licensing cc w/Attacrr.cnt:
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S. junacer J. itencric A. Gla:nbusso U. 7:cDonald A. Schwencer T. Cox D. Ross D. Housten L. Rubcostain L. Reading CP5 Pm ding L:RS Administrative Assistant S. Earga See previous yellow for other concurrence.
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