ML20213G539

Amend 87 to License DPR-61,modifying Tech Spec Section 4.10.C to Increase Frequency of Each Pump Flywheel Insp to Include Ultrasonic Volumetric Exam of Bore & Keyway Areas at 3-yr Intervals & Surface Exam at 10-yr Intervals

ML20213G539
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/12/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20213G533	List: ML20213G532 ML20213G539 ML20213G542
References
NUDOCS 8611180189
Download: ML20213G539 (4)

Text

. _ -_-__--______ -

pn r* %

8 'o . UNITED STATES 8 I NUCLEAR REGULATORY COMMISSION 5 E WASHINGTON, D. C. 20555 4.,

/

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 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 September 4,1986, complies with the standards and re as amended (the Act)quirements , and the Commission's of the Atomic rulesEnergy Act of 1954, and regulations as 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.

8611180189 861112 gDR ADOCK 05000213 PDR

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. 87, 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 TQ W 1. M Christopher I. Grimes, Dir ctor Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specifications Date of Issuance: November 12, 1986 O

I l

l l

ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE N0. DPR-61 DOCKET N0. 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 4

captioned amendment number and contains a vertical line indicating the area of change. -

REMOVE INSERT 4-19 4-19 f

.5

_ _ _ _ . . . . - - - . - _ - - .-- ---c , - - - - - - - -- - --

-w- - -

~

4.10 INSERVICE INSPECTION AND REACTOR VESSEL SURVE!!.1,ANCE App!!cability:

Applies to the periodic Inservice inspection and testing of ASME components. Boller and Pressure Vessel Code Class 1, 2 and 3 equivalent Objective:

components defined To verify above.the structural Integrity of the applicable 5pecification:

A. Inservice Inspection of ASME Code Class 1, Class 2 and Class 3 equivalent components shall be performed in accordance with Section XI of the ASME Boller and Pressure Vessel code and app!! cable Addenda as required by 10CFR50, Section 50.55a(g), with the exemptions and alternate Inspection that have been approved by the .NRC pursuant to 10CFR50, Section 50.55a(g)(6)(1). These exemptions and alternate Inspections are included in the Inservice Inspection Program.

B.

Inservice testing of A5ME Code Class I, Class 2 and Class 3 equivalent pumps and valves sha!! be performec in accordance with Section XI of the A5ME Boller and Pressure Vessel code and applicable addenda as required by 10CFR50, Section 50.55a(g), with the exemptions and alternate testing that have been approved by the NRC pursuant to 10CFR50, Section 50.55a(g)(6XI). These exemptions and alternate testing are included in the Inservice Inspection Program.

C.

Inservice inspection should be performed for each flywheel as follows: l Each reactor coolant pump flywheel shall be Inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision I, August 1975.

D. The removal plan for the remaining reactor vessel surveillance capsules is scheduled as follows:

Capsule Capsule Remova! Time Predicted Exposure (E IMEV)N/cm2 Type Indent. Years' Capsule Reactor Vessel ID I H 10 1.3 x 1019 1.0 x 1019 II D 15 2.0 x 1019 1 x 1019 11 E 25 3.3 x 1019 i

2.6 x 1019

! B 5tandby I C Standby I G 5tandby

• Removal time is in approximate calendar years from the date of initla! criticality (July 24, 1967) and Intended to coincide with the nearest refueling outage to that time.

4-19 Amendment No. , 87 ,

- . _- - _ - .__- --_ _ _ _