ML20037D309
| ML20037D309 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 06/23/1981 |
| From: | Barrett L Office of Nuclear Reactor Regulation |
| To: | Hovey G METROPOLITAN EDISON CO. |
| References | |
| CON-NRC-TMI-81-036, CON-NRC-TMI-81-36 NUDOCS 8107090383 | |
| Download: ML20037D309 (3) | |
Text
DISTRIBUTION W J-50-320 NRC PDR Local PDR TERA TMI:PO HQ r/f TMI Site r/f June 23, 1981 L. Barrett NRC/THI-81-036 (. [ga n e
Attorney, ELD IE (3) kR Docket No. 50-320 m
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2-to Mr. Gale K. Hovey R. Weller py gp Vice President and jJ NOjg 7
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Director of THI-2 h
Metropolitan Edison Company ffj P.O. Box 460 "U I? D 198% Q Middletown, PA 17057 Q v.s.u g p ;
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.y On lia 7 1981, you submitted for our review and approval the design 9
criteria for the installation of a Temporary OTSG Layup Recirculation System.
We understand this system will be utilized both to fill 0TSG 2A and 28 and to establish and maintain the.necessary secondary side water chemistry conditions for long-term wet storage of the OTSGs.
We are withholding final approval on :.he proposed design criteria pending resolution of the items discussed in Attachment I.
Since the subject system will be used to cleanup the radioactivity in OTSG '2B", we suggest that considerable attentfon be given to control and isolate any potential con-tamination in the M-20 and turbine building areas. Additionally we recommend that our staffs continue discussions to resolve any open items in a timely fashion so as to not impact on the construction and operation of this system.
Sincerely, original signed by L.H. Barrett Lake H. Barrett Acting Deputy Program Director TMI Program Office
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4 ATTACHMENT I OPEN ITEMS ON DESIGN CRITERIA FOR TEMPORARY OTSG LAYUP RECIRCULATION SYSTEM 1.
10 CFR 50 Appendix A, General Design Criteria for closed system isolation (GDC-57) requires that piping which penetrate primary reactor containment and are neither part of the reactor coolant pressure boundry nor connected directly to the ontainment atmosphere shall have at least one containment isolation valve which shall be'either automatic,-locked close or capable of remote manual operation.
State how your current system design meets this requirement and/or the intent of GDC-57, 2.
10 CFR 50.55a, Codes and Standards, and Reg Guide 1.26 establishes criteria for Quality Group Classifications and Standards for Water, Steam and Radioactive Waste Containing Components of Nuclear Power Plaits.
These criteria require ASME III, Seismic I, Class 2 up to and including the first isolation valve for PWR steam and feedwater systems extending from and including the secondary side of steam generators up to and including the outermost containment isolation ulves.
Provide justification for not designing the system to meet these requirements. m,a ~
3.
Although 'the reactoris' shut down, RCS pressure is approximately.
0E 100 psig and no ~a) parent _ primary to secondary leakage exists, we are concerned wit 1 primary system integrity on the "B" OTSG based on the events of March 29, 1979.
A description of the system overpressure protection and basis for no installed relief protection must be addressed.
Since the potiiiitial for primary to secondary leakage exists, it is our position that adequate safety protection must be provided considering the worst case RCS overpressure transient.
4.
Based on p.evious discussions with your staff we understand that the Technical Evaluation Report will address the impact of-the proposed recirculation system on the core / core cooling and visa versa.
We believe however, these findings are necessary to bound the range of conditions and controls necessary in developing acceptable design criteria for this 0TSG wet layup system.
If not already completed we suggest the timely revic of these effects-to insure no significant parametric changes are necessary.
i 5.
Provide your basis for not including isolation valves for either pumps.
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