ML20040D460
| ML20040D460 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/25/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 82-020, 82-20, IEB-79-01B, IEB-79-1B, NUDOCS 8202010317 | |
| Download: ML20040D460 (3) | |
Text
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P.O. Box 480 Middletown. Pennsylvan,a 17057 i
717-944-7621 Writer's Direct Dial Num' er:
o January 25, 1982 82-020
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.Y,Y b0 Office of Nuclear Reactor Regulation Attn: John F. Stolz, Chief 2
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Division of Licensing 3'
E Ope rating Reactors Branch No. 4
[ Ehyi.l$f'3[ j U. 3. Nuclear Regulatory Commission TIO
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Washington, D.C.
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Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 l
Docket No. 50-289 Environmental Qualification of Safety-Related Electrical Equipment As oiscussed between Mr. R. Jacobs (NRC) and E. Wallace (CPU) on January 11, 1982, enclosed please find a copy of the criteria for Class IE radiation qualification for harsh environments at TMI-1.
All Class IE equipment evaluated to date in connection with IE Bulletin 79-OlB and the TMI-l environmental qualification SER date March 24, 1981 are in or are currently being modified to be in compliance with the enclosed radiation criteria.
Sincerely, v-I Hokill r ctor, TMI-l HDH: CWS : vj f Attachment cc:
R. Jacobs R. C. Haynes Cyril J. Crane 8202010317 820125 L
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05000289
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3eneral Public Utilities System
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' Criteria for Class IE Equipment - Radiation Qualification For Harsh Environments at IMI-l Source Terms and Dose Rates
- The gamma and beta dose used for a LOCA inside containment was 2 x 10 Rads in general areas. The DOR Guidelines (Section 4.12) permit the use of a dose of 2 x 107 Rads integrated dose for gamma radiation in lieu of a detailed plant specific calculation. tha have not included the integ-rated dose associated with beta radiation since safety related equipment in the IMI Containment is in metal enclosures or conduit. The enclosures and conduit, while not necessarily gas tight, do shield the sencitive materials from essentially all of the beta source terms which is external to the enclosures / conduit. The beta dose from gases potentially within the enclosures / conduit was considered so insignificant as to not affect environmental qualification (i.e. several orders of magnitude lower than 2 x 107 Rads).
- The gamma dose used for High Energy Line Break (HELB) inside containment was 2 x 106 Rads in general areas. This is in accordance with Appendix B of the DOR Guidelines.
The-accident gamma and beta dose rates outside cf containm.nt were obtained in accordance with the guidelines of NUREG 0578 and NUREG 0737 for plant specific areas. No letdown was assumed to the makeup and purification system.
Normal plant operating radiation levels were obtained from plant operating records and health physics data.
When necessary detailed localized radiation analyses were made.
Examples of this are the shielding review outside of containment and the analysis for Rosemount transmitters inside of containment.
i The exposure 'ime used is that which is required for the component to' function after the initiation of the accident plus one hour.
Equipment Qualification The' radiation threshholds from Table C-1, Appendix C, of the DOR Guidelines were used.
Radiation effects were evaluated as non synergistic.
The components qualified were: those required for hot shutdown and i
those required for the one identified path the cold shutdown. Additionally, the display instrumentation not qualified for harsh environments and i
required by the emergency procedures were evaluated to ensure that failure of this instrumentation would not mislead the operators.
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- The, preferred method of qualific.ation used was to obtain sequential type test-data.
Other methods used were separate function test data, engineering analysis, and a combination of the methods.
- The qualification data was detailed on individual System Component Evaluation Worksheets. When an engineering analysis was performed, a Materials Evaluation Worksheet was generated. When necessary, Engin-eering Calculation Sheets were prepared.
All of the. required reference information to support the evaluation is in the central file.
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