ML20059L276

Amend 170 to License DPR-65,revising Pressure/Temp Limits for Rv

ML20059L276
Person / Time
Site:	Millstone
Issue date:	01/27/1994
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co
Shared Package
ML20059L278	List: ML20059L276 ML20059L280
References
DPR-65-A-170 NUDOCS 9402030341
Download: ML20059L276 (5)

Text

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p-4 UNITED STATES j

.j NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20555 4101 J

NORTHEAST NUCLEAR ENERGY _ COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 HILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.170 License No. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated June 11, 1993, supplemented by letter dated November 15, 1993, 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; l

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

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9402030341 940107 DR ADOCK 050003 6 s.

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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 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:

(?) Technical Specifications The Technical. Specifications contained in Appendix A, as revised through Amendment No.170, 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 issuance to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ohn F. Sto), Director

• • ' Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: January 27, 1994 i

1 I

ATTACHMENT TO LICENSE AMENDMENT NO. 170 EACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 i

Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

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INDICATED REACTOR COOLANT TREMPERATURE T ' Y C

M..ILLSTONE - UNIT 2 3/4 4-19 Amendment No.17, J/, JJJ 170

b REACTOR COOLANT SYSTEM BASES The heatup and cooldown limit curves (Figure 3.4-2) are composite curves which were prepared by determining the most conservative case, with either the inside or outside wall controlling, for any heatup or_ cooldown rates of up to the maximums described in Section 3.4.9.1.

The heatup and cooldown curves' were prepared based upon the most limiting value of the predicted adjusted reference temperature at the end of the. service period indicated on Figure 3.4-2.

The reactor vessel materials have been tested to determine their initial RT the results of these tests are shown in Table 4.6-1 of the Final Safety An$hs;isReport.

Reactor operation and resultant fast neutron irradiation will cause an increase in the RT temperature, based upon the flueNSI,. Therefore, an adjusted reference can be predicted using the methods described in Revision 2 to Regulatory Guide 1.99.

The heatup and cooldown limit curves shown on Figure 3.4-2 include predicted adjustments for this shift RT at the end of the applicable serviceperiod,aswellasadjustmentsYOfpossibleerrorsinthepressureand temperature sensing instruments.

The actual shift in RT of the vessel material will be established

. periodically during operatiBRTby removing and evaluating, in accordance with ICCFR50 Appendix H, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area.

Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel. The heatup and cooldown curves must be recalculated when the ART determined from the surveillance capsule is different from the calculatggTART for the NDT equivalent capsule radiation exposure.

The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperatt;re requirements of Appendix G to 10 CFR 50 for reactor criticality and for inservice leak and hydrostatic testing.

The maximum RT for 011 reactor coolant system pressure-retaining materials, with the Olceptico of the reactor pressure vessel, has been N

detemined to be 50*F. The i.owest Service Temperature limit line shown on Figure 3.4-2 is based upon this RT since Article NB-2332 (Sumer Addenda of 1972) of Section III of ge ASME Boiler and Pressure Vessel N

Code requires the Lowest Service Temperature to the RTNDT + 100'F HILLSTONE - UNIT 2 B 3/4 4-6 Amendment No. Jf, JJJ,170 0082

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