ML20133H776
| ML20133H776 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/16/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20133H766 | List: |
| References | |
| NUDOCS 8510180109 | |
| Download: ML20133H776 (8) | |
Text
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~k UNITED STATES 1
[
g NUCLEAR REGULATORY COMMISSION L
- j WASHINGTON, D. C. 20555 Y
J CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 70 License No. DPR-61 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated June 11, 1985 as revised June 27, 1985 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 Commission's regulations and all applicable requirements have been satisfied.
i 8510180109 851016 PDR ADOCK 050 3
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph P.C.(2) of Facility Operating License No. DPR-61 is hereby arended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.70, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ik John A. Zvelinski, Chief Oper ting Reactors Branch #5 Division of Licensino
Attachment:
Changes to the Technical Specifications Date of Issuance: October 16, 1985
l ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 3-5 3-5 i
3-6 3-6 Figure 3.4-1 Figure 3.4-1 Figure 3.4-8 Figure 3.4-9 D
3.4 C0!!31t:ED HEATU?. COOLDOWN AND PRESSURE LihlTATIONS Applicability: Applies to pressure and. temperature conditions during heatup, cooldown, hydrostatic and leak testing of the reactor coolant system.
Objective:
To natntain operational limits within allowable design limits of the reactor coolant system.
Specifications:
A.
REACTOR VESSEL 1.
The reactor coolant system pressure and temperature relationship to be applied for hydrostatic and leak testing shall be maintained within limits as shown in Figure 3.4-1.
2.
The reactor coolant system temperature, pressure and system heatup and cooldown rates shall be maintained within limits as shown in Figures 3.4-2 through 3.4-9 for the spccified service period.
3.
The average rate of reactor coolant temperature change during normal heatup or cooldown shall not exceed 100*F/hr when avera5ed over a one-hour pericd.
4.
Allowable ecmbinations of pressure and temperature for specific temperature cht.nge rates are below and to the right of the limit curves (labelled operating zone) as shown in Figures 3.4-2 through 3.4-9.
B.
Pp.ESSURIZER 1.
Thepressurizershalinotbepressurizedabove500psigunlessthe temperature of the pressurizer is above 70'F.
1 0
2.
The pressurizer heatup rate shall not exceed 100 F/hr.
3.
The pressurizer cooldown rate shall not exceed 200 F/hr.
0 4.
The temperature difference between the pressurizer and the reactor coolant system shall not excced 200'F.
C.
STEAM GENERATORS 1.
The primary side of the steam generators shall not be pressurized above 500 psig unicss the temperature of the reactor coolant system is above 70*F.
2.
The maximum hoatup and cooldown rate for the steam generators shall not excted 100*F/hr.
3.
The temperature difference across the tube sheet shall not exceed 100'F.
4.
The secondary side of the steam gencrators must not be pressurized above 200 psig if the temperature of the vessel is below 70'F.
HADDAM NECK 3-5 Amendment No. 25. 70
Basis:
The allevable. pressure-ta=perature relationships for the i
specified heatup and cooldovn rates of.the reactor coolant systa= vere calculated in accordance with Appendix C in Section III of the AST Soiler and Pressure Vessel Code. The mini =um full pressurization limits to be applied during hydro-static and leak testing of the reactor coolant system were de-i rised in accordance with ' Appendix C to ASME III.
The system leakage test and system by-drostatic test pressure limitations are based on patagraph 15-522 of the Winter 1972 Addenda to ASME Section XI.
The total stress of a co=ponent in the reactor coolant system is the ec=bined stress caused by internal pressure and by therr.a1 gradients. The Appendi.x C approach specifies that the allowable total stress intensity factor (K 1) at any ti:e during heatup and i
cooldown cannot be greater than that shown on the KIR cu m (Reference 1) for the metal ta=perature at that time. The derived operating li=it curves (Tigures 3.4-2 through 3.4-9) contain explicit safety factors of 2.0 and 1.25 (addit-ional conservatism above code requirements) on stress intensity i
f actors induced by pressure and ta=perature gradients, respectively.
A11ovable pressure ta=perature relationships for both steady-state and finite heatup and cooldest rates were generated assu ing the presence of code refe:ence 1/4 7 deep flav at either the ID or CD of the reactc; vessel. Tinally, a ec=posite curve was constructed based on a point-by-p: int co:parison of the steady state and finite heatup and cooldosm data. At any given ta=perature, the allevable pressure is taken to be the lesser of the two values taken fro: the curves under consideration. The co:posite curve vas then adjusted to allev fer pessible errors in the pressure and te:;erature sensing instrtruents.
The criticality limit is defined as the mini =u= full pressurization j
ta=perature plus 40o7 when reactor is critical.
i The heatup, cocideen and hydrostatic and leak testing operating 11=its were based on the adjusted trend curve (Ref erence 2),
j derived fro a surveillance Capsula A and T results. The projected 7.Tgg7 shif t vill be verified periodically by the reactor vessel surveillance progra=.
4
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The heatup and cooldovn rates of 200 T/hr of the pressuriser and l
300*T/hr for heatup and cooldown of the steam generators are specified since they are both design limits to maintain stresses in these vessels within acceptable design li=its.
A temperature difference of 2000T between the pressuriser and reactor coolant systes is specified to maintain therv.a1 stresses within the surge line below design limits.
Teeperature requirements for pressurization of the pressuriser 1'
and stes:n generators correspond with DTT measured for each material of each component.
/cendaent !:o.MM,70, HADDAM NECK 3-6
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