ML19351D978
| ML19351D978 | |
| Person / Time | |
|---|---|
| Site: | Fermi |
| Issue date: | 11/04/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Jens W DETROIT EDISON CO. |
| References | |
| NUDOCS 8011200499 | |
| Download: ML19351D978 (1) | |
Text
t,
- g
- 1. :..,.
.t alSTMBURON:
[ ' id<C PD RDocket File D R. Tedesco F. Whitt L. Kintner Local PDR M. Service LB #2 File I&E (3)
D. Eisenhut R. Purple BCC: ACRS (16)
A. Schwencer TERA Docket No. 50-341 November 4, 1980 TIC NSIC
~
Dr. '.fayne H. Jens Assistant Vice President Engineering a Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 4225 i
Dear Dr. Jens:
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION IN FER!iI 2 FSAR As a result of our continuing review of the Final Safety Analysis Report (FSAR) for the Enrico Fermi Atomic Power Plant Unit 2, we have develooed the enclosed requests for additional information.
Please ame'.d your FSAR to comply with the enclosed requests. Our review schedule is based on the assumption that the additional information will be available for our review by Decembee 30, 1980.
If you cannot meet this date, please inform us within 7 days after receipt of this letter so that we may revise our scheduling.
Sincerely, Oriz!nn! shm.. ! by Robert L. Ted.wo 4
Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
i Requests for Additional Information cc w/ enclosure:
See next page fh M,.
s
. LB #2/DL' hlb #2/DLfk L:DL orr.cc )
sva-c ). LK.i nt,ner/LLM ASchwen,cer esco p
1 [/80 og. 11/c..3/80 11/ o'7 /80.'~
p.
tu.s. =2cveawcyr namrmo orrics5 tin.n,-us
.j.y sec Foru ne : m.uc e mo
i j
J 1
i l
ll Dr. Wayne H. Jens Assistant Vice President Engineering & Construction l'
Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 j!
cc: Eugene B. Thomas, Jr., Esq.
David E. Howell, Esq.
- t LeBoeuf, Lamb Leiby & MacRae 21916 John R 1333 New Ha rshire Avenue, N. W.
Hazel Park, Michigan 43030 Washington, D. C.
20036 3:
l Peter A. Marquardt, Esq.
i Co-Counsel The Detroit Edison Co-any I
i 2000 Se:end Avenue
{
Detroit, Michigan 48226 f
Mr. William J. Fahrner Project Manager - Fermi'2 i
The Detroit Edison Company 2000 Second Avenue i-Detroit, Micnigan 45:26 l
i Mr. Larry E. Schuerman Licensing Engineer - Fermi 2
}
Det# cit Ed'so9 Com?a9y 2000 Se:ond Avenue Detroit, Michigan 48226 Charles Be:hhoefer, Esc., Chairman Atomic Safety & Licensing Coard i
Panel j
U. 5. Nu: lear Regulatory Commission Washington, D. C.
20555 Dr. David R. Schink Department of Oceanography Texas A & M University College Station, Texas 77840 Mr. Frederick J. Shon Atomic Safety & Licensing Board Panel i
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 D""]D *I[)df
. es es Ju esJuu du.\\
as l'
l i
i
. -, +. - - - - - - -
- - - - ~
~ ' ~ ' '"' ~
~ ~ " ' ' " ~ '
ENCLOSURE REQUESTS FOR ADDITIONAL INFORW, TION ENRICO FERMI AT0!!IC POWER PLANT UNIT 2 DOCKET NO. 50-341 Requests by tne followir.g branch in NRC are included in tnis enciosare.
ReqJosts and pages are numbered sequer.tially with respect to cres:casly transmitted requests.
E ra r.c h F 3 c + "..
Chemical Engineering Brar.h 281-1 3
f
i 281-1 i
281.0 CHEMICAL ENSINEERING BRANCH - CHEMICAL TECHNOLOGY 281.1 Section 9.1.3., Amendment 2 and Appendix 9C, Amendment 13 of the FSAR do not iridicate any proposed modi'ication to the Spent Fuel Pool Cooling and Cleanup System (SFPCCS) in conjunction with the proposed modifications for high-density spent fuel storage.
Cescribe what changes, if any, will be made to the SFPCCS to maintain tne level of pool water purity with respect to visual clarity and activated corrosion and fission product buildup the same as for the original spent fuel storage c?pacity. Assume that the number of defective fuel asse-blies increase in proportion to the increased spent fuel storage capacity.
If no changes to tne 5FPCCS are to be made, indicate how the same level of pool water purity will be maintained.
2S1.2 Describe the samples and instrument readings and their frecuency of measurement that will be performed to monitor the water purity and need for demineralizer resin replacement. State the chemical and radiochemical limits to be used in monitoring the soert fuel nool water and initiating corrective action.
Provice the basis for establishing these limits.
Your response should consider variables such as: conductivity, gross gamma and iodine activity, demineralizer, differential pressure, pH and crud level.
.