ML20054J538
| ML20054J538 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/22/1982 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TAC-43461, NUDOCS 8206290203 | |
| Download: ML20054J538 (3) | |
Text
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- Elll PortlandGeneralElectricCompany DonaldJ BrctN Assistant Vce Presdent June 22, 1982 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 IAEA Safeguards Program Attached is a revision to the Trojan Design Information Questionnaires (DIQ) regarding the fuel pin exchange process conducted at Trojan. This revision was previously discussed with your staff and is submitted to you in accordance with 10 CFR 75.6 and 75.11.
PGE's letter of March 10, 1982 to the NRC provided an advance notification of a possible onsite fuel pin exchange operation and application of stain-less steel rods. This advance notification for the installation change was provided in accordance with 10 CFR 75.11. col.
The attached revision officially documents the changes in the DIQ resulting from the fuel pin exchange. This completes necessary actions by the licensee for the installation change as required in 10 CFR 75.
Sincerely, l
Attachment c:
Mr. Lynn Frank, Director State of Oregon 3
Department of Energy Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing Nuclear Regulatory Commission 8206290203 820622 PDR ADOCK 05000344 P
PDR T C:
i cn uw Pc ' m C eyn 9Gs:
t ATTACHMENT 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 264 264 264 264 264 264 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 i
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 were replaced with dummy stainless steel rods in 1981 due to baffle jetting problems in the reactor core. Due to continuous baffle jetting problems, a various number of fuel assemblies in the peripheral region of the core will have fuel pins replaced with solid stainless steel rods.
t CESEA2CH AND POWER REACT 3%S Date:
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- b. NUCL' EAR IA1YE RI AL DESCRIPTION -d" E O
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2s.PRoVISICN Fom ELEMENT EXCHANGE IN AssEueuts o, E ACN TveE
- The facility was not permanently designed W***"an***""""'""**
to accommodate fuel rod exchange.
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NOTE: Due to baffle jetting problem, fuel pin exchange tools were obtained from Westinghouse for a temporary use during the 1982 refueling outage.
- Fuel rod exchange is not routine.
- One assembly has been built so that 88 fuel rods may be removed for examina-tion.
29.SASIC OPERATIONAL ACCOUNTING UNITLS)
(fust elements /emmentWes, etcJ Basic Operational Accounting Unit:
One Fuel Assembly Means of Identifying Accounting Unit:
1D Numbers Any Seals:
No Accounting Procedures for Changed Elements:
Item Count Element Identification: None 30.OTHE R TYPES oF UNIT 5 None st.wE ANs pr NUCLEAR uaTERiaveuf L Method for Reading Identification Markiogs:
loENTIFICATioN Area Method Fresh Fuel Storage Direct Visual Core Underwater Camera or Visual Position Verification Spent Fuel Storage Visual Position Verification CONFIDENTIAL 5
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