ML18044A572
| ML18044A572 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/05/1980 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-15-20, TASK-RR NUDOCS 8002280258 | |
| Download: ML18044A572 (6) | |
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. LREGULATORY oocr<ET FllE COPY Docket No~ 50-255 Mr. David P. Hoffman
- Nuclear licensing Administrator Cons*umers Power Company*
212 West Michigan Avenue Jackson,. Michigan 49201
Dear Mr.* Hoffman:
-~.
. DISTRIBUTION Docket NRC PDR Local PDR ORB Reading NRR Reading.
DEisenhut RVo l lmer O[LD OI&E (3) *
- DLZi emanri.
PO 1 Conn.or HSmith
. NSIC TERA..
- ACRS (16}
DCrutclifield (2~
RE:
SEP TOPIC XV *Rad{oJog1ca1 *con.sequen.ces :of Fuel Damaging Acciden~$* (r~side* and Outside C_onta1nment)~
- Enclosed is a copy.of our evaluation of Systematic Evaluation Program
- FEB, Topic XV-20 Radiological Consequences of Fuel Damagi_ng Accidents. (Inside:
and Outside Conta1nm~nt). *.This assessmen.t comp.ares your_.faci li.ty., as de.;.
- scriped in Docket No. 50.. 255 with the criteria currently'µsedbythe regulatory staff for li~ensing n~w facilities~
- Please inform* us if your...
as-built.. facilii-ty di*ff ers" from the licensing basis. assumed in our assessment.
'~
...We. hav~ discussed* th1 s a!?Se$_sment with. your staff and believe the facts: -:
- . concerning yqur-plant are ~Qrrect. Therefore, our review of this topic. _.
- . is. complete and this* evaluation w.i.U,be a basfc input :to the i!ltegrated *...
safety assessment for your fac1'11ty. unless you:.1dent1fy changes* needed***.. **
to reflect the as~built conditions a_t your facility. This topic: assess-,
me.nt.may be revised *1n,the ft.iture if your facility design is changed or:
.*.if.NRG cr1teria'relat1rlg to this.topic are mod1fi.ed before the integrat~d *,.
assessment 1s.complet_e(i...
Enclosure:
Completed SEP*
Topic XV-20 cc w/enclpsure:
- s' nee rely,..
Original Slgned by:_.
. D.ennis L. ~iemann
~ -
.Pennis L. Ziemann,- Chief
.. Operating Reactors Branch #2
.Qiv1sfon of Operat1ng Rea'ctors
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5 1980 See next page
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>uRNAME ~;:(;iiiQf.: ~~ ~~.. *.. i~?~i6"~................. *.....
..l 'g 0022 80 :Q8*.
DATE~ *.* t... *.*................,._........ :....... *........ **:........................ *....... *.......................,....... *..........................
- NRC FORM'318 (9*76) NRC.M 0240.. : **
-~
Mr. David P. Hoffman
".'.C t-;
- I. M i 11 er, Esq u i re Isham, Lincoln & Beale*
Suite 4200 One First National Plaza Chicago, Illinois 60670 Mr. Paul A. Perry, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Cons:.::r:ers Power Company 212 West Michigan Avenue Jackson, Michi;:~ 492Cl Myron M. Cherry, Esquire Suite 4501 One IBM Plaza Chicago, Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Summerset Drive Midl~nd, Michigan 48640 Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route 1, Box 10 Van Buren County, Michigan 49043 Office of the Governor (2)
Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment Di vision Office of Radiation Programs
. (AW-459)
U. S. Environmental Protection*
Agency Crysta 1 Ma 11 #2 Arlington, Virginia 20460 February 5, 1980 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATIN:
.EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Charles Bechhoefer; Esq., Chai nnan Atomic Safety and Licensing Board Pane.1 U. S. Nu cl ear Regu 1 atory Cammi ssi on Washintjton, D. C.
20555 Dr. George C. Anderson*
Department. of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Li vi ngston
- 1 00 5 Ca 11 e Largo Santa Fe, New Mexico 87501 Resident Inspector c/o U. S.
- NRC P. d. Box 87 South Haven, Michigan 49090 Palisades Plant A TIN:
Mr. J
- G. Lewi s Plant Manager Covert, Michigan 49043
PALISADES XV-20 RADIOLOGICAL CONSEQUENCES OF FUEL DAMAGING ACCIDENTS (I NS IDE Arm ours I DE CONTAINMENT).
The safety objective of this topic is to assure that the offsit~ doses resulting from fuel damaging accidents resulting.from fuel handling are
.well within the guideline value of 10 CFR Part 100.
The design basis fuel handling accident is postulated to damage one fuel assembly during fuel handling oper.ations either inside the Spent Fuel Building or inside containment.
The postulated consequences are giveM in Table XV-3.
The assumptions and input parameters used in calculating the potential consequences are given 1n Table XV-4.
The analysis was performed following the assumptions and procedures indicate:
in SRP 15.7.4 and Regulatory Guide 1.25. The acceptance criteria of SRP specify that the doses should be "appropriately within the guidelines" of 10 CFR Part 100.
"Appropriately within the guidelines" *has been defined bv the staff as a thyroid dose less than 100 rem.
This is based on the probability of these accidents relative to the probability of other accidents which are evaluated against.the Part 100 exposure guidelines *. Whole body doses were considered but th~y are not controlling due to t~e decay of the short-lived.
radioisotopes prior to fuel handling.
On th~ basis of the resulis as given in Table XV-3, we conclude that the rad~o logical consequences *are appropriately within the guidelines of 10 CFR P~rt 100.
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REFERENCES
- 1. Letter, D. L. Ziemann to D. Bixel, June 21, 1979, Transmitting the Safety Evaluation for Fuel Handling Accident Inside Containment.
- 2.
Safety Evaluation Report for Palisades, dated 3/6/70.
TABLE XV-3 CALCULATED DOSES FOR.~UEL HANDLING ACCIDENTS Doses, Rem Thyrof d Whole Bod~
Exclusion Area Boundary ( EAB) 2-Hour Doses:
Accident in Fuel Handling Building 9
. 0. 4 Accident Inside Containment 91 0.4
w TABLE XV-4 ASSUMPTIONS USED FOR THE FUEL HANDLING ACCIDENT Power Level Operating Time Peaking Factor Number of Fuel Assemblies Damaged Number of Fuel Assemblies in Core Shutdown Time Before Start of Refueling Activity Relea~e From Pool Containment Isolation (for Inside Containment Case)
Filter Efficiency for Filter on Spent Fuel Pool Building Ventilating System 0-2 hr, X/Q Value, Exclusion Area Boundary (ground level release) 2650 Mwt 3 years 1.65 l
204 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Regulatory Guide l.25 Puff release assumed with no isolation or eff-luent filtration 903 3.4 x 10-4 sec/ml