ML20002A511

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Amend 32 to License DPR-3,changing Tech Specs Values for Core 12 Allowable Peak Linear Heat Generation Rate Versus Exposure
ML20002A511
Person / Time
Site: Yankee Rowe
Issue date: 11/23/1976
From: Schwencer A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20002A509 List:
References
NUDOCS 8011170425
Download: ML20002A511 (7)
v • d • e


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4 UNITED STATES J'-

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1 YANKEE ATOMIC ELECTRIC COMPANY

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r-DOCKET N0. 50-29 YANKEE NUCLEAR POWER STATION (YANVsEE-ROWE) b AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.32 License No. DPR-3 1.

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

I A.

The application for amendment by Yankee Atomic Electric Company (thelicensee)datedOctober 12, 1976, 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; 4

B.

The facility will operate in conformity with the application, Y

the provisions of the Act, and the rules and regulations of p[

the Comission, C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health ki (p

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; hg x

D.

The issuance of this amendment will not be inimical to the comon M.

defense and security or to the health and safety of the public;

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The issuance of this amendment is in accordance with 10 CFR Part M

51 of the Conmission's regulations and all applicable requirements i^

have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license M

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This license amendment is effective as of the date of its issuance.

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[E FOR THE NUCLE 'PEGULATORY COMMISSION y

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A.c'chwencer. Chief S

Operating Reactors Branch #1 Division of Operating Reactors P

Attachment:

2 Changes to the Technical Specifications 0

Date of Issuance:

November 23, 1976 3,

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ATTACHMENT TO LICENSE AMENDMENT NO. 32 g

E FACILITY LICENSE N0. DPR-3

!W DOCK,ET NO. 50-29 E

is Revise Appendix A of current Technical Specifications as follows:

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1.

Replace page 2 with attached revised page 2.

j 2.

Replace Figure 8-1(page 56) with attached revised Figure 8-1 kh (page 56)

Q Revise Appendix A of Standard Technical Specifications issued with gf Amendment No. 27 (effective January 1977)

g we Replace pages 3/4 2-3 and 3/4 2-4 with revised pages 3/4 2-3 and 3/4 2-4 (no changes on page 3/4 2-4).

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214. Nuclear Instrumentation System 215 7 Radiation Monitoring System 218 Fuel Handling System 224 Compressed Air Systems 231 Vapor Containment 232 Radiation Shiciding 235 Architectural Features Physical arrangemente of structures end equipment vill be as described in Section 200 of the license application.

Mechanical equipment and systems will be intenenacted aa shavn in the Fundamental Flow Diagram included in that section.

Electrical equipment and systems which provide station auxiliary power supply vill be as described in Section 226 of the license application and vill be interconnected as shown in the 2400 volt one-line diagram and the 480 volt one-line diagram, sheets 1, 2 and 3, included in that section.

The ventilation system for the control room area, radiochemical laboratory, decontamination cubicle, fuel transfer pit house, and other potentially contaminated portions of the Turbine Generator Service, Primary Auxiliary, and Waste Disposal Buildings shall be in accordance with the description contained in Section 228 of Part B of the license application.

3.

The Perfor=ance Analysis for the current reload core, " Yankee Nuclear Power Station Core NII Perfor=ance Analysis, July 9, 1975" (as s'upple-cented October 10,~ 197S, February 19, 1976, August 17, 1976, and October 12, 1976, and the " Additional LOCA Analysis - Appendix B" dated February 20, 1976, are incorporated as part of these technical specifications. The analysis presented in the FSAR for Core XI forms the basis for the reference core performance analysis.

C.

pep.70?MSCE SPECIFICATIONS Calculated values of operating variables such as pressures, temperatures, flows, heat fluxes, reactivity coefficients and on-site radiation levels under steady state and transient conditions which are stated in the sections of the license application listed in Paragraph B, above, are considered to be performance specifications of the reactor and are incorporated by reference herein.

Yankee shall not operate the facility under circunstances-where there is a substantial variance between the foregoing performance specifications and the corresponding values determined by operation of the facility.

The perforcance and function of the sys.te: 2 described in the following sections of the license application shall be substantially as described; however..the details of individual components and their arrangecent as described in each of these sections may be altered by Yankee at its own discretion previded that such an alteration vould not violate so=e other provisica g gheg yT cbn gal Snecifications:

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