ML20087P126

Amend 81 to License DPR-28,revising Tech Specs to Accommodate Shifts in Transition Temp for Reactor Pressure Vessel Matl Induced by Radiation Damage

ML20087P126
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/13/1984
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Vermont Yankee
Shared Package
ML20087P127	List: ML20087P126 ML20087P130
References
DPR-28-A-081 NUDOCS 8404060081
Download: ML20087P126 (5)

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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET N0. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. DPR-28 1.

The Nuclear Regulatory Comission (the Commission) has fcund that:

A.

The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated May 26, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reauirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-28 is hereby amended to read as follows:

8404060081 840313 PDR ADOCK 05000271 P

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1 2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the i

Technical Specifications.

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This license amendment is effective as of the ' ate of its issuance.

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FOR THE NUCLEAR REGULATORY COMMISSION i

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Domenic B. Vassallo, Chief r

i Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical 1

Specifications l

Date of Issuance:

March 13,1984 i

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4-ATTACHMENT TO LICENSE AMEN 0 MENT NO. 81 l

FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Revise the Technical Specifications as follows:

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VYNPS i Eises 3.6 & 4.6 REACTOR COOLANT SYSTEM A. Pressure and Temperature Limitations All components in the Reactor Coolant System are designed to withstand the ef fects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.2 of the FSAR. During startup and shutdown, the rates of temperature and pressure changes are limited the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the i so that stress limits for cyclic operation. During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. These thermal induced compressive stresses tend to ~ I alleviate the tensile stresses induced by the internal pressure. Therafore, a pressure-temperature curve based on steady state conditions (i.e., no thermal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel is treated as the governing locations. The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the outer wall of the vessel becomes the controlling location. The thermal gradients established during heatup produce tensile stresses at the outer wall of the vessel. These stresses are additive to the pressure induced tensile st resses which are slready present. The thermal induced stresses at the outer wall of the vessel are tensile and are dependtat on both the rate of heatup and the time along the heatup ramp; therefore, a lower bound I curve similar to that described for the heatup of the inner wall cannot be defined. Subsequently, for the cases in which the outer wall of the vessel becomes the stress controlling location, each heatup rate of interest must be analyzed on an individual basis. undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures jf In order to prevent should be within 50"F of each other prior to startup of an idle loop. 1he reactor vessel materials have been tested to determine their initial nil-ductility transition temperature (NDTT) of 400F maximum. An additional margin of 200F has been added in order to estimate reference Reactor operation and resultant fast neutron (E ?>l Hev) irradiation will cause an increase y temperature, RThbT. in the RTNLT. The re f o re, an adjusted ref erence temperature can be predicted using current industry practices O' (GE SIL No. 14, Supplement No. 1) based on recent GE surveillance data. The pressure / temperature limit curve, 8 l Figure 3.6.1, includes predicted adjustments for this shif t in RTNDT for operation through 1.330x10 HWH(t), as well as adjustments f or possible errors in the pressure and temperature sensing instruments. 117 -}}