ML20150A725
| ML20150A725 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/01/1988 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| References | |
| TAC-66714, NUDOCS 8807080164 | |
| Download: ML20150A725 (3) | |
Text
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July 1, 1988
,s Docket No.:
50-344 Mr. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204
Dear Mr. Cockfield:
SUBJECT:
LCA 161; UPGRADED FUEL DESIGN (TAC NO. 66714)
By [[letter::05000344/LER-1987-030, :on 871021,discovered That Component Cooling Water (CCW) Flow to RHR a HX Was Only 4,460 Gpm.Caused by Procedure Inadequacy.Rhr a HX CCW Outlet Valve Adjusted to Provide 5,100 Gpm|letter dated November 20, 1987]] as supplemented May 27, 1988, Portland General Electric Company (PGE) requested changes to the Trojan Technical Specifications (TS) regaraing nuclear fuel design and power distribution limits (LCA 161).
The November 20, 1987 application did not include in its accident evaluation, i
the results of analyses regarding departure from nucleate boiling (DNB) based upon a postulated reactor coolant pump (RCP) shaft seizure (locked rotor) event, since the upgraded fuel assemblies were considered to be substantially similar to the Westinghouse standard 17 x 17 fuel assemblies used through Cycle 10.
We have reviewed the application and conclude that although some physical attributes may exhibit similarities, the upgraded fuel assemblies cannot be considered similar to the standard fuel assemblies from the nuclear design standpoint. Therefore, a Trojan specific analysis based upon a postulated locked rotor event which assumes fuel failure for fuel pins that exceed the DNB safety limit criterion must be included in the accident evaluation.
We request that you inferm this office within 30 days of receipt of this letter the anticipated submittal date of the requested analysis.
Sincerely, original signed by wJ8 Terence L. Chan, Project Manager c o a.
Project Directorate V
$8 Division of Reactor Projects - III, gg IV, Y and Special Projects Office of Nuclear Reactor Regulation 40 38 cc: See next page, om R
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July 1, 1988 Docket No.:
50-344 Mr. David W. Cockfield Vice President, Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204
Dear Mr. Cockfield:
SUBJECT:
LCA 161; UPGRADED FUEL DESIGN (TAC NO. 66714)
By [[letter::05000344/LER-1987-030, :on 871021,discovered That Component Cooling Water (CCW) Flow to RHR a HX Was Only 4,460 Gpm.Caused by Procedure Inadequacy.Rhr a HX CCW Outlet Valve Adjusted to Provide 5,100 Gpm|letter dated November 20, 1987]] as supplemented May 27, 1988, Portland General Electric Company (PGE) requested changes to the Trojan Technical Specifications (TS) regarding nuclear fuel design and power distribution limits (LCA 161).
The November 20, 1987 application did not include in its accident evaluation, the results of analyses regarding departure from nucleate boiling (DNS) based upon a postulated reactor coolant pump (RCP) shaft seizure (locked rotor) event, since the upgraded fuel assemblies were considered to be substantially similar to the Westinghouse standard 17 x 17 fuel assemblies used through Cycle 10.
We have reviewed the application and conclude that although some physical attributes may exhibit similarities, the upgraded fuel assemblies cannot be considered similar to the standard fuel assemblies from the nuclear design standpoint.
Therefore, a Trojan specific analysis based upon a postulated locked rotor event which assumes fuel failure for fuel pins that exceed the DNB safety limit criterion must be included in the accident evaluation.
We request that you inform this office within 30 days of receipt of this letter the anticipated submittal date of the requested analysis.
Since erence L. Chan, Project Manager roject Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation cc: See next page.
)
Mr. David W. Cockfield Portland General Electric Company Trojan Nuclear Plant cc:
Senior Resident Inspector U.S. Nuclear Regulatory Comission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Mr. Michael J. Sykes, Chainnan Board of County Comissioners Columbia County St. Helens Oregon 97501 Mr. William T. Dixon Oregon Department of Energy Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Comission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 1
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