ML20011F802
| ML20011F802 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/02/1990 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9003080052 | |
| Download: ML20011F802 (2) | |
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David W. Cockfield Vice President. Nuclear March 2, 1990 Trojan Nuclear Plant Docket 50-344 License NPF-1 I
U.S. Nuclear Regulatory Commission I
Attn.Docuenent Control Desk Washington DC 20555
Dear Sirs:
J Interpretation of License condition 2.C.11 f
l Reference la Letter to B. D. Withers (PCE) from C. M. Tramell, III (NRC) i dated August 10, 1984.
Portland General Electric Company (PCE) wishes to reconcile the statements of License Condition 2.C.11
" Fuel Assemblies", with Technical i
Specification Design Features 5.3.1, " Fuel Assemblies". At issue is whether new (i.e., fresh) fuel assemblies may have stainless steel rods substituted for fuel rods.
License Condition 2.C.11. " Fuel Assemblies", was last changed in 1984 following a modification that eliminated baffle jetting induced fuel damage. Previous to this change, fuel reloads were approved on a cycle specific basis with an evaluation of the number and positioning of stainless steel rods. The NRC Safety Evaluation (Reference 1) concluded that'"the facility can be safely operated with these assemblies during Cycle 7 and any additional cycles of operation necessary to achieve their design discharge burnup." Throughout the safety evaluation, the basis is that the baffle jetting repair eliminates the need for modified fuel assemblies. Based on this, the license condition was written as follows:
(11)
Fuel Assemblies The licensee is permitted to use fuel with stainless steel pins and fuel with stainless steel pins and extra grid straps for Fuel Cycle 7 and subsequent cycles provided:
(a) The fuel with extra grid straps is used only in the 8 corner locations where previously used, and (b) No fresh fuel modified as above is introduced into the core.
9003090Q32 900302 h
PDR AIJUCK 05000344 u
A P
((OO/
121 S.W. Salmon Street, Portland. Oregon 97204,503/464 8897
N W M Cortguriy Document Control Desk March 2, 1990 page 2 It is understood that Item (b) prevents further insertion of modifLed fuel to cope with beffle jetting.
Design Features Section 5.3.1, " Fuel Assemblies", was changed in 1989 to road " limited substitutions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, or by vacancies, may be made as justified by cycle specific reload safety analysis." The intent of this change is to allow fuel repairs to replace leaking fuel rods now that fuel assemblies have removable top nozzles.
The design features section was considered consistent with the license condition because new fuel assemblies are not likely candidates for repair. However, a situation has arisen involving repair of a new assembly where substitution of fuel rods with stainions stool rods is the preferred solution. The reason for the repair is to ensure that fuel leakage will not occur. The stainless rods are Dol being added to combat baffle j e tting.- The nuclear, thermelhydraulic, and physical effects of the stainless steel will be evaluated for each cycle in the Reload Safety Evaluation.
pCE's interpretation of License Condition 2.C.11 is that the restrictions to new fuel with stainless steel applies to assemblies modified for baffle jetting but does not apply to new assemblies modified for other reasons.
Based on this, PGE intends to insert one new assembly with two stainless rods in Cycle 13.
A separate submittal will be prepared to delete License Condition 2.C.11.
Sincerely,
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p ct Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. David Stewart-Smith
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M State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear plant 1
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