ML20209D718

Amend 82 to License DPR-61,revising Tech Spec Page 4-21g to Permit Plant Operation W/Four Steam Generator Tubes in Steam Generator 4 Not Inspected Per Tech Spec Table 4.10-2

ML20209D718
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/03/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209D696	List: ML20209D692 ML20209D718 ML20209D739
References
NUDOCS 8609090414
Download: ML20209D718 (4)

Text

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1. ko UNITED STATES 8 NUCLEAR REGULATORY COMMISSION 3 WASHINGTON, D. C 20555

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 License No. DPR-61

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated April 15, 1986, as modified 4

June 4,- 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations as set forth in 10 CFR Chapter I; j 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 conducted 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. .

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8609090414 860903 PDR ADOCK 05000213 PDR P

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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-61 is hereby amended to read as follows:

(2) Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 82, 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 its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION hqwIb' Christopher I. Grimes, Directo Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specifications Date of Issuance: September 3,1986

ATTACHMENT TO LICENSE AMENDMENT N0. 82 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following page of the Appendix A technical specifications with the enclosed page as indicated. The revised page is identified by the captioned amendment number and contains a vertical line indicating the area of change.

REMOVE INSERT 4-219 4-21g

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4 5

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l TABLE 4.10.1-2 '

STEAM GENERATOR TUDE INSPECTION .

ist SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required .

Result Action Required Result

Action Required A minimum of '

C-1 None N/A S Tubes per N/A N/A N/A.

5.G. -

C-2 Repair defective tubes C-1 None N/A N/A and Inspect additional Repair

, C-1 None l

25 tubes in this S.G.* C-2 defective tubes C-2 Repair and inspect defective tubes

• additional 45 tubes -

C-3 Perform-action for l In this S.G.* C-3 result of first sample C-3 Perform action for N/A N/A C-3 result of first l

sample C-3 Inspect all All other ~

tubesin S.G.sare None this S. G., repilr C-I N/A N/A defective tubes and Some S.G.s Perform action for Inspect 25 tubes in C-2 but no N/A N/A C-2 result of second each other S.G.* additional sample ,

S.G.are Prompt notilication C-3 to NRC pursuant to10.CFR50.72(b) Additional Inspect all -

1 (2) . S.G. Is C-3 tubesin each S.G. and re defective tubes.'pair Prompt not!!! cation N/A .N/A '

l to NRC pursuant to10CFR50.72(b)

I (2) *

! S*12 %

i n Where n is the number of steam generators inspected during an inspection.

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sleeves shall be plugged.* Repair of defective tubes shall be limited to plugging with the.. exception of The cycle testing 13 4Steam of the Row #1 Generator tubes (Rowtube 1,eddy current testing of steam cenerator #4 shall not require Columns they are not degraded tubes. 51, 52, 53, and 54) having historical data indicating 4-21g Amendnient No. 2dJd M 82