ML19210A108
| ML19210A108 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/14/1978 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19210A109 | List: |
| References | |
| GQL-1197, NUDOCS 7910240827 | |
| Download: ML19210A108 (1) | |
Text
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RCOULATOPY INFCFJ1ATICN DISTRIBUTION SYSTEt1 (RIDS)
DI5'RIBUTION FOR It4CGT1ING MATERI AL 50-2S9
..EC. c.IID R N ORG: HEREEItJ J G DOCDATE: 07/14/76 r.FC T1ETROPOL EDISON DATE RCVD: 07/20/7?
E C Ti F E.
LETTER NOTARIZED. NO COPIES PECEIVEO E U G. lECT :
LTR 1 ENCL if IMI-1 FEACTOR CONTAINNENT EUILDING PERIODIC INTEGRATED LEAK RATE TE:ET PEFORT
'TATING THE NEXT TEST IS SCHUELED FOR THE 1931 REFUELING OUTAGE.
FLANT NAME: THREE MILE ISLAND - UNIT 1 REVIEWER INITIAL:
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DISTRIEUTOR INITIAL: g,-
4 5 4 -* + ->-* + 4 4-6 4 4 4 4 4 DISTRIEUTION OF THIS MATERIAL IS AS FOLLOWS 44+**+++44*+++++4+
CCNTAINMENT LEAK RATE TESTING-APPENDIX J.
- OISTRIDUTIGN CODE A017)
FCR ACTION-ER CHIEF ORB #4 EC**W/7 ENCL hEGFILb4/ ENCL INTERNAL.
NRC PDR**W/ ENCL I u cv, u _ c m., L OELD**W/ ENCL HANAUER**W/ ENCL CONTAINMENT SYSTEMS **W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB4*W/ ENCL M FAIRTILE4*W/ ENCL EFFLLIENT TF; EAT SYS**W/ ENCL EXTERNAL:
LPDR'S HARRISBURG, PA**W/ ENCL TERA **W/ ENCL NSIC+4W/ ENCL ALRT CAT B**W/16 ENCL 1489 274
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DISTRIEUTION.
LTR 40 ENCL 40 CONTROL NER:
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7910240
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METROPOLITAN EDISON COMPANY PCST OFFICE BOX 542 READING. PENNSYLVANI A 19C/)3 TELEPHONE 215 - 929-2001 July 1h, 1978 GQL 1197 Director of :Tuclear Reactor Regulation Attn:
Mr. R. '4. Reid, Chief Operating Reactor Branch :To. k jfg[ l)(? c.,
a df U. S. :Tuclear Regulatory Cer=ission
-N. L.'{ ~'si.d~ C0 v
'4ashingten, D. C.
20555 I
Dear Sir:
1 Three Mile Island Tuclear Station Unit 1 (DfI-1)
Operating License No. DPR-50 Docket :To. 50-239 In accordance with the requirenents of 31!-1 Technical Specification h.h.1,1.8 and 10 CFR 50 Appendix J, Secticn V.3,e.nclosed please find twelve (12) copies of the 1978 DfI-1 Reacter Centainment Building Pe-riodic Integrated Leak Rate Test Report.
This test, as specified in your January 18, 1978 letter, is in addition to these tests already required by DII-1 Technical Specifications, and is censidered a replacement for the 1977 test. Based on the acceptable results of this year's test, the next test is presently scheduled for the 1981 refueling outage.
S'.nc erely,
~
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J. G. Herbein Vice President-Generaticn JGH:DGM:cjg
Enclosure:
BfI-1 Reacter Centainment Euilding Periodic Integrated Leak Rate Test - 1978 (12 copies) 1489 275 782010178 h \\
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