ML20132G548
| ML20132G548 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/26/1985 |
| From: | Jason White JAMES R. WHITE, CONSULTING |
| To: | Snyder NRC |
| Shared Package | |
| ML20132G516 | List: |
| References | |
| NUDOCS 8508050065 | |
| Download: ML20132G548 (2) | |
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c Fermi Unit 2 1
On N1 arch 20,1985, the Nuclear Regulatory Commission issued a li-cense to Detroit Edison Company and Wolverine Power Supply Corpo-rations, incorporated, for the Fermi 2 nuclear power plant. This license authorizes fuel loading and the con-duct of low power testing up to fiv Since 1972 NPE users have been percent of full power. Fermi Umt ccessing the single most uses a boiling water reactor and at full power will have an electrical out.
comprehensive, constantly put of about 1093 megawatts.
updated compilation of LWR y
y industry operating experience.
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Currently over 23,000 detailed a 9' Waterford Unit 3 entries representing more tnan
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500 cumulative reactoryears of operation are indexed in the On N1 arch 16,1985, the Nuclear publication with plant descriptions and operating histories also Regulatory Commission issued a li-included.
cense to 1.ouisiana Power & l.ight Company for full power operation of the Waterford Steam Electric Sta-INTRODUCING tion Unit 3. Waterford 3 uses a pres-COMPUTERIZED RETRIEVAL SYSTEM--NPEars sunied water reactor and at full power will have an electrical output Now offen.ng a new computerized retrieval capability which com-of about 1104 megawatts. The plant was licensed on December 18,1984, plements existing hard copy keyword indexing and plant cross-for fuel loading and low power test-referencing. Improved search parameters enhance data base's ing up to live percent of full power.
value by providing faster and more efficient referencing of NPE articles.
O Wolf Creek Nuclear see oemonstration at sootn 79 ANs summer Power Conference 3
Plant 8,
On N1 arch 11,1985, the Nuclear Regulatory Commission issued a li-l call or write for a descriptive
- nam, cense to Kansas Gas and Electric l
NPEars brochure, Mall coupon to:
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Company and other owners autho-g company
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rifing them to load fuel into the Nuclear Power Expenence Wolf Creek Generating Station and l
191914th street. suite 501 m en 7
Boulder. CO 80302 UM c ty state. zip conduct low power testing up to tive l
303M49 7220 mme rcie.
percent of full power. The other owners are Kansas City Power &
Circle 106 on Reader Service Form 1.ight Company and Kan'sas Electric b - """ - T"- ~ '"" ~
a Power Cooperative, Inc. The Wolf pressurized in February 1984, the polar crane For further inforniation, contact Creek Station has a water reactor and at full ptmer will test w s successfully conducted. hve Dr. #crnard J. Snyder, Director, months later the reactor pressure Three.1/i/c Island Program Office, have an electrical output of about venel head was removed. In Decem-O]Jice of Nuclear Reactor Regula-1150 megawatts.
ber 1984, the reactor vessel plenum rion. U. S. Nuclear Regulatory was jacked up seven and one-half Conimission, li'ashington, DC
[ TMI-2 Cleanup inches allaying fears that it may be 20555: telephone 1301) 492-7761.
stuck and require cutting to remove.
Gisen below are the accomplish-Removal of the plenum, scheduled in (Continued on next page) ments, future goals, and the views of N1ay 1985, represents the last major the Nuclear Regulatory Commission hurdle prior to fuel removal opera-on the cleanup of Three N1ile Island tions. According to GPU Nuclear's Unit 2 (TN1I-2) of General Public latest estimate, dated July 2,1984 Utilities Nuclear (GPU Nuclear).
the target date for the completion of reactor fuel removal from the prima-rs system is June 19S7.
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41 Nt br Plant Safety. May-June 1985
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c News Flashes, LI.S. Nuclear Regulatory Commission ' ' i continuedfrom page 4/
Engineers get a hold on your future.
Reactor FuelRod Agggygjg HEADOUARTERS POSITIONS REGIONAL OFFICE POSITIONS h
(Office of Nuclear Reactor Regula5on Reg.on I. 631 Park Avenue, g
The latest versions of the Fuel Bethesda. MD)
King of Prussia. PA 19406
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Rod Analysis Package (I: RAP), a
- REACTOR EN9NEER (Matde Postons) i r
The NRC Operator L.cens.ng Prog am has
- HE Al TH PHYSCIST (vA #84 R1033) nuclear safety computer code series vacames for ino<v.ouars *.tn OPERATOR p
for anal 7inE the behavior of reactor u,SR REACTOR OPERATOR UcENSING Regon Il 101 Marera Street I
exper ence as REACTOR ENGINEERS and Sude 2900. Attanta. GA 30303 a_
fuel rods, have been developed at the TRAINING ASSESSMENT SPECIAUST e REACTOR INSPECTOR (MJt one Postons)
Department of Energy's Idaho Na-(SRO) Saiary negaan.e Cano, dates must
- RESIDENT INSPECTOR (Muft se Post.ons) f
" d
EACTOR e REACTOR ENGtNEER tional Engineering Labora tory
[p n47o""n "'&hI *i r c 9, S
(INEL). FRAPCON-2 and FRAP-Cerucat on on a commerc a. nuciea, Reg.on lit 799 Roosevelt Road he[Q,7S T6, developed through funding from po*e' vant SPECTOR 2
the Nuclear Regulatory Comm,s-i e REACTOR ENGINEER (Operator
- REACTOR ENGINEEWS (Nuclear Er.g nee <>
E sion, represent the state of the art in Lcens ng) (VA #R85 0744 7) e RESIDENT INSPECIOR g
light water reactor fuel rod analysis.
- PROJECT MANAGER (VA #84 2685)
+ HEALTH PHYSICIST The codes are able to analyze ' fuel
- I A$NG & ASSESSMENT SPECIALIST Regon V 14E0 Mana Lane Suae 210.
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'SR temperatures, fuel cladding stress,
' NON DESTRUCTNE EXAMINATION Wa nu reek 45 %
and fuel chemistry so that fuel rod SPECIAUST (VA #85 0350 7)
- RESIDENT INSPECTOR E
integrity and fission product invento-(O'fice of Inspect;on and Enforcement.
ACRS Graduate and Poq Dnrea4 Fw ps
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ry can be prcJicted. FRAPCON-2 is Bethesda. MD)
Opponun.t es ed for GG 12 0 nd v.dua+s to F-uc-d for analy7ing fuel behavior un-e Ar' ACTOR ENGINEER (Systems) wrk.n reactor safety research the study at
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Generc.ssues eiatea to nuc. ear po er paa der steady-statc (normal operating)
(Otf.ce of Nuclear Matenal Sa'ety and savy and the reve* of spec.fc rwear poe conditions, and FRAP-T6 is used for Sa'eguards. S.iver Spring. MD) vaecense apocarons Sena aoocatons to transient (ot!-riormal or accident) e PROJECT M ANAGER (Operat:on
"*dd4"d'fe's O#ce Am AI Newsom (ACRS)
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Resea,ch) (vA.851077 ')
FOR REGtONAL OFFICE POSITIONS ans, to conditions. The accuracI and reli-o't cets) of cho ce c rectly Use Fecera; ability of the FRAP codes have been NRC H res a rect No Crv4 Serwce Sta'us Employmed Apo!caron Fom (SF 171) n en e
verified by experiments at the reged NRC is an Equal Oppo< tun.tv andy.ng for ait postons its ava.latye ar most Employer M DHocp All appbcants must be INEL,s Loss-of-Flu d Test Fac. lit),
uS c>tzens ano are suo,ect to a en rougn i
i ottces A resume how may be subm t'ed'or o
p,ern nary cons.oe,3non nete, to,0c s
and Power Burst Facility. The background 'nauey saca,cy numbers n e <nacarea e
FRAP codes are now used extensive-FOR sEAoOUARTERS POSITIONS aody to f.
o,S.. U.S. Nuclear wasn.ngem oC aoa,ess oeo. Seemi o
ly by the Nuclear Regulatory Com-f mission and the nuclear industry.
- Regulatory "9'**'*"
For details contact Terry A. Smith, m// C.ommisSion ATTN: FLE (NPSJ)
Public Information d Communica-Division of Personnel sh on 2055 tions, EG& G Idaho, P. O. Box I625,
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idaho Falls, Idaho 83415; telephone (20s) 526-1320.
Whem excellence is standard operating procedure.
Donation Entry level pos:tions also erst for indvdua s who are graduat.ng wt*i eng neering EG&G Services, Inc., Idaho de9'eeS in decxat mechanical nuclear and heafth/ radiation phys Apply to Falls, has donated fifteen software w shington. DC addmss packages valued at $65,000 to Vir-k
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ginia Tech, Industrial Engineering Circle 105 on Reader Service Form and Operations Research Depart-ment's Safety Option Program. The plant systems and components.
Chairman, INPO donation included CMORTe, which The LOMI (Iow oxidation state is the computeri7ed management metal ions) solvent dissolves James J. O'Connor, chairman, oversight and risk tree software. radioactive metal oxide deposits, president and chief executive ollicer CMORTC has been acquired by sev.
which accumulate on primary (CEO) of Commonwealth Edison eral nuclear power utilities.
circuit piping surfaces in nuclear Company, was elected chairman of reactors, thereby reducing radiation the Board of Directors of the Insti-Decon Technology doses to reactor personnel during tute or Nuclear Power Operations inspections and maintenance work.
(INPO) at the board's March 20 IT Corporation, a subsidiary of The solvent was developed by meeting. Ile succeeds Lelan F. Sil-International Technology researchers at the Central lin, Jr., chairman of the board of Corporation, has obtained a Electricity Generating Board of trustees of the executive committee nonexclusive U. S. license from the Great Britain under EPRI funding.
of Northeast Utilities, who he
.tir-Electric Power Research Institute The process has been successfully ed after holding the post of NPO (EPRI) for use of its patented applied in Britain at the Winfrith board chairman since 1981 Sillin LOMI solvent technology in the test reactor and on a Surry steam was one of the charter members of decontamination of nuclear power generator channel head, the INPO Board of Directors.
E 42 Nuclear Plant Safety. May-June 1985 a