ML19343B829
| ML19343B829 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/23/1980 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | Barrett L Office of Nuclear Reactor Regulation |
| References | |
| TLL-684, NUDOCS 8012300645 | |
| Download: ML19343B829 (3) | |
Text
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Metropolitan Edison Company Post Office Box 480 ll-L Middletown, Pansylvania 17t. '
Writer's Direct Dial Nurnber December 23, 1980 TLL 684 TMI Program Office Attn:
Mr. Lake H. Barrett, Deputy Director U. S. Nuclear Regulatory Commission a
c/o Three Mile Island Nuclear Station
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Middletown, Pennsylvania 17057
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
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-j Operating License No. DPR-73 Docket No. 50-320 a
Design Criteria for the Modification for Closure of Reactor Building Penetration 401 Attached is our design criteria for the modification of reactor building penetration 401 (P401).
The purpose of this modification is to provide a more permanent closure for P401 due to the potential for flooding through this penetration as a result of an increase in reactor building water level. This modification is not intended to return P401 to its pre-accident condition, however, as it will still be used to pro-vide provisions for monitoring reactor building water level. Our intention is to perform this modification prior to March 31, 1981.
Sincerely,
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G. I. HOVEY G. K. Hovey Vice-President and Director, TMI-2 GKH:JJB: dad cc:
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i 8 012300 OE Metropolitan Edison Company is a Member of the Genera! Puchc Utti.es System
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THREE MILE ISLAND UNIT 2 DESIGN CRITERIA MODIFICATION FOR CLOSURE OF REACTOR BUILDING PENETRATION 401 1.
SCOPE This document provides criteria for design modifications to Reactor Building penetration ntsnber 401 to provide a more permanent closure of the penetration, in consideration of future potential increase of building water level to the extent of flooding the penetration.
2.
INTRODUCTION Penetration 401 was modified in late Summer 1979 to allow access to obtain samples of the building sump water. Following successful completion of the sampling program, further design changes were made to use the penetration for building water level measurement, by addition of a manometer system to the sampling tubing. The penetration has remained in this basic configuration to date, to allow daily water level measure-ments. The present configuration is described by Reference 1 and Refer-once 2.
The intended modification will remove the 12-inch gate valve and the special cover assembly outboard of the valve. A welded closure assembly will then be added. Provisions for building wa'ter level measurement will remain. This modification is not intended to return the penetration design i
to the pre-accident condition nor to qualify the penetration for plant restart.
3.
DESIGN REQUIREMENTS 3.1 Codes and Standards 3.1.1 Design and fabrication shall be in accordance with' applicable portions of ANSI B 31.1 and ASME Section VIII.
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3.1. 2 Welding shall be in accordance with ASME Section IX.
3.2 Design Pressure and Temperature:
10 psig (positive) and 2.5 psi (vacuum) at 50 F to 100 F.
3.3 Design Loads:
Design shall consider deadweight and pressure loads, and accelerations applicable to the plant operating basis earthquake, without loss of function.
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TESTING All welds shall receive visual plus liquid penetrant inspections.
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QUALITY -ASS,URANCE Design, procurement, fabrication, and testing are within quality assurance scope.
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REFERENCES 6.1 Drawing JS061780, Revision 0 Thrte Mile Island Unit #2, Containment Penetration No. 401, M20 area.
6.2 Three Mile Island Unit #2 procedure 2104-4.47, Instrument Hookup, Measurement and Removal for Reactor Building Sump Level Deteminations.
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