ML19339C952
| ML19339C952 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/14/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339C953 | List: |
| References | |
| NUDOCS 8102120545 | |
| Download: ML19339C952 (5) | |
Text
{{#Wiki_filter:~ 8 UNITED STATES f g NUCLEAR REGULATORY COMMISSION L j WASPINGTON. D. C. 20666 / ....+ VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR-28 l l 1. The Nuclear Regulatory Comission (the Csmmission) has found that: A. The application for amendment by Vermont Yankee Nuclear Power Corporation (.the licensee) dated September 5,1980, complies with as amended (the Act)quirements of the Atomic Energy Act of.1954, the standards and re , and the Commission's rules and regulations set forth in 10 CFR Chacter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conduct?d without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows: B. Technical Specifications The Technical Specifications contained in ^ppendices A and B, as revised through Amendment No. 62, are hereby incorporated in the license. The licensee shall. operate the facility in accordance l with the Technical Specifications. 4 8102120 64$ t
1 - 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMISSION Thomas. Ippolito, Chief Operating Reactors Branch #2 . Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 14, 1981 e l l l I l 9 e S e
ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-331 1. Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Remove Insert 111 111 117 117 118 118 8 P I i l l l i f
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Bases: 3 6 & 4.6 REACTOR COOLANT SYSTEM A. Pressure and Temperature Limitations All components in the Reactor Coolant System are' designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads ar.s introduced by normal load transients, The various categories of load cycles used for design reactor trips, and startup and shutdown operations.During startup and shutdown, the rates of temperature pur poses are provided in Section 4.2 of the FSAR. and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumpt. ions and satisfy the stress limits for cyclic operation. During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from These thermal induced compressive stresses compressive at the inner wall to tensile at the outer wall. Therefore, a pressure-temperature tend to alleviate the tensile stresses induced by the internal pressure. 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 thermal gradients established during the outer wall of the vessel becomes the controlling location. These stresses are additive to the heatup produce tensile stresses at the outer wall of the vessel.The thermal induced stresses at the outer pressure induced tensile stresses which are already present. wall of the vessel are tensile and are dependent on both the rate of heatup and the time along the heatup ramp;.therefore, a lower bound curve similar to that described for the heatup of the inner wall cannot be Subsequently, for the cases in which the outer wall of the vessel becomes the stress controlling defined. location, each heatup rate of interest must be analyzed on an individual basis. In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures should be within 50 F of each other prior to startup of an idle loop. 0 The reactor. vessel materials have been tested to determine their initial nil-ductility transition An additional margin of 20 F has been added in order to estimate temperature (NDTT) of 40 F maximum. Reactor operation and resultant fast neutron (E ) 1 Mev) irradiation will reference temperature, RTNDT. Therefore, an adjusted reference temperature can be predicted using cause an increase in the RJNDT. The current industry practices (GE SIL No.14, Supplement No.1) based on recent GE surveillance data.NDT for pressure / temperature limit curve Figure 3 6.1 includes predicted adjustments for this shift in RT MWH(t), as well as adjustments for possible errors in the pressure and 8 operat' ion through 1.15x10 temperature sensing instruments. 117 Amendment No. 62
The actual shift in NDTT of the vessel material will be entnblished periodically during operation by removing and evaluating, in accordance with ASTM E185-73, reactor vessel material irradiation surveillance Since the neutron spectra specimens installed near the inside wall of the reactor vessel in the core area. at the irradiation samples and vessel inside radius are essentially identical, the measured transition In order shift for a sample can be applied with confidence to the adjacent section of the reactor vessel. to estimate. the material properties at the 1,'4 and 3/4 positions in the vessel plate, the shift in NDTT The heatup and cooldown l is assumed to be 625 and 22%, respectively ol' the irradiation samples properties. determined from the surveillance capsule is different from curves must be recalculated when the thRTNDT for the equivalent er.psule radiation exposure. the calculated 4kRTNDT The pressure-temperature limit lines shown on Figure 3 6.1 for reactor criticality and for inservice leak and hydrostatic testing have been provid0d to assure compliance with the minimum temperature requirements of Appendix G to 10 CFR 50 for reactor e. iticality and for inservice leak and hydrost'atic testing. The number of reactor vessel irradiation surveillance specimens and the frequencies for removing and testing these specimens are provided to assure compliance with the requirements of Appendix H to 10 CFR Part 50. B. Coolant Chemistry A steady state'radiciodine concentration limit of 1.1 j4Ci of I-131 dose equivalent per gram of water in the reactor coolant system can be reached if the gross radioactivity in the gaseous effluents are near the limit as set forth in Specification 3 8.C.l.a or there is a failure or prolonged shutdown of the cleanup In the event of a steam line rupture outside the drywell, the NRC staff calculations show demineralizer. This dose was the resultint radiological dose at the site boundary to be less than 30 Rem to the thyroid. 118 Am:ndment No. 62}}