ML20041F244
| ML20041F244 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/10/1982 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TAC-43461, NUDOCS 8203160325 | |
| Download: ML20041F244 (8) | |
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March 10. 198 h XN N,. g ; *'/
Trojan Nuclear Plant--
Docket 50-344 License NPF-1 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
TROJAN NUCLEAR PLANT The IAEA Safeguards Program Enclosed is a revision to the Design Information Questionnaire (DIQ),
originally submitted to the NRC on April 10, 1981. This revision was previously discussed with your staff and is submitted to the NRC in accordance with 10 CFR 75.6.
The enclosed revision contains the following changes to the DIQ:
- 1. 3.1 - A clarifying statement was added for the maximum allowable enrichment of 3.5 percent for fresh fuel.
- 2. 6.1 - Two footnotes were added to describe possible changes to part-length control rods and fuel assemblies.
3.
Paragraph 31 - The method of fuel assembly identification in the Spent Fuel Pool was corrected to specify a visual position verification rather than underwater camera, since no underwater camera is used for routine inventory check in the Spent Fuel Pool.
4.
Paragraph 36 - The number of fuel rods in the core was clari-fled by adding " nominally or by design".
5.
Attachments 52.1 and 52.2 - These attachments were combined and redrawn as Attachment 52.1 to provide more concise information on the reactor flow diagram: Attachment 52.2 should be deleted from the DIQ accordingly.
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6.
Paragraph 52 - The flow diagram was corrected in accordance with the change in Attachments 52.1 and 52.2.
82O3160325 820310 PDR ADOCK 05000344 P
PDR 121 Ssw SaWon Street Portkvx1 Cregon 97204
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W M BedricC0f143EN1y Mr. Darrell G. Eisenhut, Director March 10,1982 Page two Due to the current radioactivity level in the reactor coolant, some degree of fuel failure is assumed to have occurred in the fuel assemblies at the Trojan Nuclear Plant. Although a decision has not been made, we have received the necessary equipment for exchanging new fuel pins with stainless steel rods. This information is provided to you in accordance with 10 CFR 75.11 as an advance notification of a possible installation change. Should we decide to conduct a fuel pin-exchange during the 1982 refueling outage, we will notify you accordingly.
Sincerely,
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Bart D. Withers Vice President Nuclear Attachment c:
Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. Robert A. Clark, Chief Operating Reactors 3 ranch No. 3 Division of Licensing i
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ATTACHMENT 23.1 Sheet 1 of 1 OPERATIONAL FRESH FUEL ENRICHMENT Six regions of fuel have been delivered to Trojan thus far. The enrichments of these regions are:
Region Enrichment 1
2.12%
2 2.61%
3 3.09%
4 3.10%
5 3.10%
6 3.20%
Note: The Trojan Technical Specifications (Appendix A to FOL NPF-1)
Section 5.3.1 allows the fuel enrichment to be as high as 3.5 weight percent. Therefore 3.5 percent should be considered as the maximum allowable enrichment.
ATTACllMENT 26.1 Sheet 1 of 1 REACTOR ASSEMBLIES CHARACTERISTICS Fuel Region 1
2 3
4 5
6 Number of Assemblies 65 64 64 64 64 56 Number of Fuel Rods 264 26A 264 264 264 264 Number of Poison Rods 0
0 0
0 0
0 Average Enrichment 2.12 2.61 3.09 3.10 3.10 3.20 General Structure 264 rod positions, 25 guide tube posi-tions, 8 rod spacer grids, upper and lower end fittings, and hold-down springs.
Geometric Form 17 x 17 square array Dimensions 8.426 in. x 8.426 in.
Cladding Material Zircaloy-4 The reactor contains a total of 193 fuel assemblies, 53 full-length control rods, and 8 part-length control rods. There are by design a total of 50,952 fuel rods in the reactor.
Note 1.
Eight part-length control rods are scheduled to be removed in 1982, which will leave only 53 full-length control rods.
Note 2.
Three fuel rods in two fuel assemblies are replaced with dummy stainless steel rods due to baffle jetting problem in the reactor core. Up to about 12 more fuel assemblies may be modified in 1982.
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RESE ARCH AND POWER REACTG7.3 Jat;:
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NUCtE AR M'A'TE RI AL DESCRIPTION 28.PRovist0N FOR ELEMENT EXCH ANGE IN ASSEMBLIES OF E ACH TYPE i.ao.cc.
in in.i w oor a o t= ora. *
- Fuel assemblies are not designed to be
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- nondestructively disassembled and rebuilt.
- The facility was not designed to accommo-date fuel rod exchange.
- Fuel rod exchange is not routine.
- One assembly has been built so that 88 fuel rods may be removed for examina-tion.
29.8ASIC OPER ATION AL ACCOUNTING UNitts) te es.i.m.atil.a.mu
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Basic Operational Accounting Unit:
One Fuel Assembly Means of Identifying Accounting Unit:
ID Numbers Any Seals:
No Accounting Procedures for Changed Elements:
Item Count Element Identification:
None 30.OTHER TYPES OF UNITS None 31.ME ANS OF NUCLE AR MATE RI AL/ FUEL Method for Reading Identification Markings:
Area Method Fresh Fuel Storage Direct Visual Core Underwater Camera or Visual Position Verification Spent Fuel Storage Visual Position Veritication CON FIDE NTI AL 5
APR 101981 RESEARCH AND POCER REACTORS Dato:
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NUCt. EAR MATERIAL FLOW 1.
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34.lNVENTORY
$ TATE QUANTITY R ANCE. NUM8ER OF ITEMS, AND APPROxlM ATE UR ANIUM ENRICHMENT AND PLUTONIUM CONTENT tender normal ooersting condinens):
34.1 Table of Inventory 4 ReactorCore El Spent Fust Storage kl Other Locanons
- 35. LOAD F ACTOR foo ee coactor only) 1979 (actual)
- 0.56 1980 (actual)
- 0.64 1981 (estimated) - 0.70 l
1982 (estimated) - 0.70 t
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36.RE ACTOR CORE LOADtNO (numtwr of eventalauemotied 50,952 fuel rods (Nominally or by design) 193 fuel assemblies l
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52.1 100 Percent Power Reactor Flow Diagram y
- PROTECTION AND SAFETY MEASURES 1^' Y
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- 53. BASIC MEASURES FOR PHYSICAL FROTECTION OF NUCLEAR MATERI AL
- The inspector will be given an entrance briefing on physical security.
- Trojan complies with 10 CFR 73, which specifies requirements for physical protection.
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