ML20211M578

Forwards SER of Util 860123 Submittal Re Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events.Matl Properties Acceptable

ML20211M578
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/11/1986
From:	Chan T Office of Nuclear Reactor Regulation
To:	Lindblad W PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20211M582	List: ML20211M578 ML20211M598
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-59991, NUDOCS 8612170359
Download: ML20211M578 (2)

Text

V.

D:cemb:r 11, 1986 DISTRIBUTION '

Docket No. 50-344 , Docket: File e B. Grimes NRC PDR N. Thompson Local PDR J. PArtlow PD#3 Rdg. C. Vogan T. Novak T. Chan Mr. William J. Lindblad OGC ACRS(10)

President E. Jordan Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

SUBJECT:

PROJECTED VALUES OF MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SH0CK EVENTS We have reviewed your letter dated January 23, 1986 which was submitted in response to the Pressurized Thermal Shock (PTS) Rule,10 CFR 50.61, for Trojan Nuclear Plant. We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel for the end of life of the plant and the calculated RT for the end of life of the plant to be acceptable. The calculated RT i$Tbelowthescreening criteria of 270 F at 32 EFPY chisbeyondtheShirationdateofthe license and, therefore, meets e requirements of the PTS Rule.

The PTS Rule requires that the projected assessment of the RT must be updatedwheneverchangesincoreloadings,surveillancemeasubntsorother information (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the accumulated fluence for the limiting beltline materials throughout the life of the plant to verify that their assumptions remain valid. In this regard we request that you submit a re-evaluation of the RT and comparison tothepredictedvaluewithfuturePressure-TemperaturesubbIktalswhichare required by 10 CFR 50, Appendix G.

! Our associated Safety Evaluation is enclosed.

Sincerely, e

)

Terence L. Chan, Project fianager Project Directorate #3 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page J

PD#3 PD#3 -

PD.3 CVogantN TChan.inak SVa a 12/\\/86 12/lj/86 1 86 8612170359 861211 PDR ADOCK 05000344 P PDR

T Mr. William J. Lindblad j . Portland General Eletric Company Trojan Nuclear Plant cc:

Senior Resident Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 William T. Dixon Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 l

Regional Administrator, Region V U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 l

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