ML18092B578
| ML18092B578 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/11/1987 |
| From: | Mcneil C Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8705180494 | |
| Download: ML18092B578 (8) | |
Text
- .
e Public Service Electric and Gas Company e
Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box 236, Han cocks Bridge, NJ 08038 609 339-4800 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
May 11, 1987 CHANGES TO INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA) DESIGN INFORMATION QUESTIONNAIRE SALEM UNIT 1 DOCKET NO. 50-272 In accordance with Code 2.2 of the proposed IAEA facility attachment for Salem Unit 1 (LCR 87-04, Facility Attachment No.
13, April 20, 1987), attached is a list of changes to the information in the IAEA Design Informatio~ Questionnaire.
These changes *are associated with the core reload for Salem 1, Cycle 8.
The scheduled shipment date and the all fuel on site date for Cycle 8 fresh fuel are currently set for August 12, 1987.
A Cycle 7 shutdown date of October 31 1987 and a Cycle 8 startup date of December 17, 1987 are currently anticipated.
If you have any questions, please contact E. s. Rosenfeld at (609) 339-4723.
Sincerely,
~&~~
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e.4-~~r-.
c D. c. Fisher - Licensing Project Manager T. J. Kenny - Senior Resident Inspector E. Sparks Safeguards Material Licensing and International Activities Branch Off ice of Material Safety and Safeguards 7:f>°'°
- j 1 Dr. T. E. Murley USNRC Region 1 Administrator i--~6~ 5-1~g~~:-3~88A17;-
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SALEM NUCLEAR GENERATING STATION, UNIT 1 CHANGES TO IAEA DESIGN INFORMATION QUESTIONNAIRE (DIQ)
DIQ Paragraph Number 13 23 24 26 27 28 36 Revised Data Replace old Attachment 13.4 with attached new 3.4.
Change number of fuel types from 9 to 7 and cycle from 7 to 8.
Replace old Attachment 23 (applicable to Cycle 7) with attached new Attachment 23 (applicable to Cycle 8).
Replace old Attachment 24.1 (applicable to Cycle 7) with attached new Attachment 24.1 (applicable to Cycle 8).
Change Cycle from 7 to 8 (two places).
Replace old Attachments 26.1 and 26.3 (applicable to Cycle 7) with attached new Attachments 26.1 and 26.3 (applicable to Cycle 8).
Replace old Attachment 27.1 (applicable to Cycle 7) with attached new Attachment 27.1 (applicable to Cycle 8).
Change first information item to:
"The new fuel assemblies to be inserted into Cycle 8 are designed to be nondestructively disassembled and rebuilt.
All fuel assemblies onsite prior to the Cycle 8 fresh fuel delivery are not designed to be nondestructively disassembled and rebuilt."
Change Cycle from 7 to 8 and number of poison rods from 1,616 to 1,712.
ATTACHMENT 13.4 DISASSEMBLY AND REPAIR Although Salem Nuclear Generating Station 1 fuel assemblies received prior to the new fuel for cycle 8 are not designed to be nondestructively disassembled and repaired, techniques are available to achieve such an operation.
Disassembly and repair can be performed in special ad hoc work stations located underwater in the spent fuel storage/transfer areas.
Special tools operated from the water surface are used for disassembly.
The types of operations that can be performed are drilling, (un)screwing/(un)bolting, cutting and fitting.
These operations can be performed to achieve either a skeletal rebuild utilizing the same fuel rods or a removal of a few defective rods which are to be replaced with durcuny rods, i.e., zircaloy rods.
Salem Nuclear Generating Station 1 new fuel assemblies for cycle 8 are designed to be nondestructively disassembled and rebuilt.
The cycle 8 fuel assembly design allows disassembly and rebuild utilizing work stations, tooling and operations as described in the preceding paragraph but with no damage to the fuel assembly.
Disassembly and repair should be scheduled well in advance.
However, if fuel failures occur, the consequences of operating with the fuel failures could warrant a disassembly/rebuild project on a short term notice.
No firm commitments to a disassembly and repair operation are established at the present time.
TYPE 1
2 3
4 5
6 7
ATTACHMENT 23 SALEM 1 CYCLE 8 OPERATIONAL FUEL ASSEMBLY INITIAL ENRICHMENTS ENRICHMENT 3.40 3.80 3.80 3.80 3.80 3.80 3.80
ATTACHMENT 24.1 NOMINAL WEIGHT OF FUEL IN ASSEMBLIES OPERATIONAL ASSEMBLIES (i.e., PRIMARY FUEL)
DESIGN TYPE TYPE TYPE TYPE TYPE TYPE TYPE MATERIAL TOLERANCES 1
2 3
4 5
6 7
TYPE (ALL TYPES)
WEIGHT WEIGHT WEIGHT WEIGHT WEIGHT WEIGHT WEIGHT COMPOUNDS I CONTAININGj uo2
+1.0%
I 524 kg I
524 kg 524 kg 524 kg 524 kg 524 kg 524 kg THE FISSILE MATERIAL I I
I I
I FISSILE u235
+.05 w/o 17.82 kg 19.91 kg 19.91 kg 19.91 kg 19.91 kg 19.91 kg 19.91 kg MATERIAL I
I TOTAL ASSEMBLY
+1.0%
665.4 kg 665.4 kg 665.4 kg 665.4 kg 665.4 kg 665.4 kg 665.4 kg WEIGHT
ATTACHMENT 26.1 SALEM 1 CYCLE 8 REACTOR ASSEMBLIES CHARACTERISTICS OPERATIONAL (CYCLE 8)
TYPE 1 TYPE 2 TYPE 3 TYPE 4 TYPE 5 TYPE Number of Assemblies 25 80 8
4 12 8
I Number of Poison Rods 0
0 I
4 8
12 20 I
I Average Enrichment 3.40 3.80 I 3.80 3.80 3.80 3.80 i
Characteristics Common to All Fuel Types:
- General Structure:
- Geometric Form:
- Dimensions:
Cladding Material:
L 264 fuel rods, 24 rod cluster control guide thimbles, one instrumentation thimble, 8 fuel rod spacer grids, 8 grid sleeves, and top and bottom assembly nozzles.
17 x 17 array 8.426 inch x 8.426 inch Outer Dimensions Zircaloy -
4 6
TYPE 7._
56 24 3.80
ATTACHMENT 26.3 SALEM 1 CYCLE 8 FUEL ROD AND POISON ROD PATTERN FOR EACH ASSEMBLY TYPE y
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'IO TYPE 1 AND 2 TYP.E 3 llf
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TYPE 4 TYPE 5
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TYPE 6 TYPE *.7 D FUEL ROD
~WATER HOLE POISON ROD
ATTACHMENT 27.1 FRESH FUEL RODS CHARACTERISTICS Physical Form Chemical Form Nuclear Material Quantity Design Tolerance Fissionable Material Quantity Design Tolerance Enrichment and/or Pu Content Geometric Form Dimensions Pellets per Rod Composition of Alloy Cladding Material Thickness Composition Bonding OPERATIONAL TYPE 1 Sintered Pellets uo2 u235 + u238
- 1. 98 kg
+.05 w.o.
u235 67.32 gm
+1.0%
3.40 wt%
-Rods
-Cylindrical Ceramic Pellets 385.0 cm length 0.95 cm diam 272 Not applicable 0.0572 cm Zircaloy-4 None TYPE 2 Sintered Pellets uo2 u235 + u238 1.98 kg
+.05 w.o.
u235 75.24 gm
+1.0%
3.80 wt%
-Rods
-Cylindrical Ceramic Pellets 385.0 cm length 0.95 cm diam 272 Not applicable 0.0572 cm Zircaloy-4 None i
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