ML19312E166

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Informs That Interim Procedural Changes for Nonconservative Features Identified in Rod Drop Analysis Will Remain in Effect Until Longer Term Solutions Have Been Developed Via Westinghouse Topical Rept Due mid-1980
ML19312E166
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/28/1980
From: Goodwin C
PORTLAND GENERAL ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
References
TAC-11203, NUDOCS 8006030391
Download: ML19312E166 (2)


Text

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r c-May 28, 1980 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:

Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Sir:

In our letter of December 11, 1979 to Mr. A. Schwencer, we committed to institute interim procedural changes at the Trojan Nuclear Plant to compensate for nonconservative features that had been identified in the rod drcp analysis.

Specifically, operating procedures were modified to require that when the reactor control system is in the automatic mode and power is >90 percent of rated power, the Bank D control rods will be withdrawn >215 steps.

No changes were made for operation at power levels <90 percent of rated or for operation with the reactor control system in the manual mode.

These procedural changes remained in force until our current shutdown for refueling.

As part of the design of the core loading pattern for Cycle 3, we have reviewed the rod drop analyses to ensure that these interim procedural changes provide the same degree of conservatism as was provided during the previous cycle.

It has been determined that it will be required for Cycle 3, in order to ensure this level of conser-vatism, to require the Bank D control rods to be withdrawn >215 steps whenever the reactor control system is in the automatic mode and power is >85 percent of rated power. No changes will be made for operations at power levels <85 percent of rated or for operation with the reactor control system in the manual mode.

800608039l f

4 Mr. Robert A. Clark May 28, 1980 Page two These interim procedural changes will remain in cffect until longer-I term solutions have been developed as part of a topical report on this matter to be submitted to the NRC by Westinghouse in mid-1980.

Sincerely,

.h r/ /

C. Goodwin, Jr.

Assistant Vice President Thermal Plant Operation and Maintenance CG/DIH/CJP/4jedlA22 c:

Mr. Lynn Frank, Director State of Oregon Department of Energy i

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