ML093421076
| ML093421076 | |
| Person / Time | |
|---|---|
| Site: | Indian Point |
| Issue date: | 10/29/1979 |
| From: | Early P Power Authority of the State of New York |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML093421077 | List: |
| References | |
| IPN-79-76, NUDOCS 7911020337 | |
| Download: ML093421076 (3) | |
Text
POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRCLE NEW YORiK, N. Y. 10019 (212) 397-6200 TRUSTEES GEORGE T. BERRY PRESIDENT & CHIEF OHAS.D N
OPERATING OFFICER JOHN W. BOSTON GEORGE L. INGALLS EXECUTIVE VICE PRESIDENT & DIRECTOR OF POWER OPERATIONS RICHARD M. FLYNN JOSEPH R. SCHMIEDER EXECUTIVE VICE ROBERT I. MILLONZI October 29, 1979 PRESIDENT & CHIEF ENGINEER FREDERICK R. CLARK IPN-79-76 LEROYW. SINCLAIR SENIOR VICE PRESIDENT
& CHIEF FINANCIAL OFFICER THOMAS R. FREY SENIOR VICE PRESIDENT
& GENERAL COUNSEL Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 Division of Operating Reactors
Subject:
Indian Point 3 Nuclear Power Plant Docket No. 50-286 Inservice Inspection Program for Second Forty Month Interval
Dear Sir:
As required by 10CFR 50.55a (g), the Power Authority of the State of New York has performed a review of the Inservice Inspection Program requirements for the Indian Point Unit 3 '
Nuclear Power Plant. This letter forwards the results of this review.
Under the provisions of 10CFR 50.55a, inservice inspection and pump and valve surveillance testing will be performed in accordance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda which will be referenced simply as the "Code". As further specified in 10CFR 50.55a (b), the effective edition of the Code with regard to this submittal is the 1974 Edition through the Summer 1975 addenda. Based on the date of commencement of commercial operation, the starting date for the second forty month interval for the Indian Point 3 Power Plant is November 28, 1979.
Enclosed Attachment I is the Inservice Inspection Program report for the Indian Point Unit 3.
Five copies are submitted for your review. This has been prepared to comply with Code requirements to the extent practicable.
It consists of the Weld Inspection and Pump Valve surveillance testing Program.
Specific requests for relief from Code requirements are included in Attachment I as provided by 10CFR 50.55a (g) (iii).
Additional 7911o020 37 ofl"
U.S. Nuclear Regulatory Comnmi ssion
-2 exemptions to Code requirements may be requested of the Nuclear Regulatory Commission as the program is fully implemented.
Additions and changes to the test programs which comply with Code testing requirements will be implemented as needed with out prior Nuclear Regulatory Commission notification.
Attachment II is a complete set of system flow diagrams denoting the Inservice Inspection boundaries color coded pink for Class I, yellow for Class 2, and green for Class 3.
a listing of these flow diagrams, and other flow diagrams which are not marked but submitted for pump and valve testing is attached to this letter.
The Technical Specifications for the Indian Point Unit 3 are currently being reviewed with the objective of identifying conflicts with Section XI Code requirements in the weld and the pump and valve programs.
Relief from any inconsistencies between the Technical Specification and the Inservice Inspection Program will be submitted at a future date, as a request for change to the Techni'cal Specification.
Very truly5 ours, Paui J. Early Assistant Chief Engineer-Projects cc:
Hon. George V. Begany White Plains Library
LIST OF INSERVICE INSPECTION PROGRAM DRAWINGS 9321-F-20173-15 "1
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-20193-16 if
-27203-11
-27223-13
-27243-11
-27273-9 "t
-27303-8
-27353-12
-27363-11
-27373-12
-27383-12
-27453-7
-27473-14
-27503-10
-27513-15
.-20353-13 "I
-20363-18
-26533-1
-27233-12 "I
-2'7263-9
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-27533-4 If
-40573-9 i
-40793-7 Main Stream Condensate Boiler & Feed Pump Suction Boiler Feedwater Auxiliary Coolant Service Water Primary Make-up Water Auxiliary Steam & Condensate Waste Disposal Sheet #2 Safety Injection Sheet #1 Chemical & Volume Control Sheet #1 Chemical & Volume Control Sheet #2 Reactor Coolant Sheet #1 Sampling Reactor Coolant Sheet #2 Safety Injection Sheet #2 Auxiliary Coolant Sheet #2 Station Air Instrument Air Post Accident Containment Sampling Nitrogen to Nuclear Equipment Penetrations & Liner Weld Joint Channel Pressurization Hydrogen Recombiner Auxiliary Steam Supply and Condensate Return Post Accident Containment Venting