ML20042A059
| ML20042A059 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1982 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| 4400-82-L-0039, 4400-82-L-39, NUDOCS 8203230034 | |
| Download: ML20042A059 (2) | |
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P.O. Box 480 Middletown, Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:
March 17, 1982 4400-82-L-0039
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TMI Program Office t'g Attn:
Dr. B. J. Snyder, Program Director
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U. S. Nuclear Regulatory Commission Ic Washington, D.C.
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Dear Sir:
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J Three Mile Island Nuclear Station, Unit 2 (TMI-2)
_,e Operating License No. DPR-73 Docket No. 50-320 LWR Primary Coolant System Pressure Isolation Valves
Reference:
Letter from Darrell G. Eisenhut (NRC) to all LWR Licensees dated February 23, 1980 This letter responds to the NRC Generic Letter dated February 23, 1980 relating to LWR primary coolant system pressure isolation valves.
Due to the reasons discussed below, GPUN concludes that testing of the subject valves is not appropriate at this time. However, this item will be reevaluated if TMI-2 is refurbished.
A review of the TMI-2 piping and instrumentation drawings and the reference letter reveals that the subject valve configuration is used in two different systems at Three Mile Island Unit #2.
The systems are the Core Flood System and the Decay Heat Removal System.
Both of these systems utilize two check valves in series with a motor operated valve as the boundary between the high pressure piping connected to the Reactor Coolant System and the Low Pressure System Piping.
Since the concern expressed in the reference letter is limited to component integrity and functionality as a pressure isolation barrier, it does not apply to Three Mile Island Unit #2 at this time. With the current plant status, these valves do not serve as the boundary between high and low pressure systems.
Reactor Coolant System pressure is being maintained at
/['00 j approximately 100 psi,and this is well within the design pressure of both the Core Flood and Decay Heat Removal Systems. The Reactor Coolant System will remain at low pressure and temperature conditions for the next several j g years.
A second factor which must also be considered in this instance is accessi-bility to the valves. The majority of the time needed to be perform any 8203230034 820317 PDRADOCKOSOOOg is a part of the General Public Utilities System P
Dr. B. J. Snyder 4400-82-L-0039 type test or inspection of these valves would be spent inside the Reactor Building, as this is where all the valves are located.
Present radiation levels inside the Reactor Building and the lack of need for such testing would make this activity not ALARA.
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L. 11. Ba rret t, Deputy Program Director, Dil Program Director J