ML17209A888
| ML17209A888 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/27/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8104020022 | |
| Download: ML17209A888 (6) | |
Text
Cr MAR 2 P lggt Docket No.:
50-389 DISTRIBUTION:
Docket File bcc:
LBk'1 Rdg TERA DEisenhut NRC/PDR JYoungblood L/PDR VNerses NSIC MRushbrook TIC RTedesco ACRS (16)
SHanauer RYollmer Florida Power 8 Light Company,.....,...
... /hler]eyr ATTN:
Dr. Robert E. Uhrig. Yice PIesident,,,Dposp...,
Advanced Systems 8 Tec)nology...., +artfield, HPA P. 0.
Box 529100 OELD hliami, Florida 33152
.,......0,1E (3)
FWitt
Dear Dr. Uhrig:
Sub)ect:
St. Lucie Plant, Unist2 pSgR, -gequept.fqr, Addjtiona1 IIiformation,.
From the review of your application for ag ypepatjng,. license. by, the, Chemigp,'l...
s Technology Section of the ChemicalEngjpeeerjpg.Branch,,
wefind that, pie peed additional information regarding the
.$t,. gucje Plant,, Uykt,2 PSAR, The specific information required,is 1$ stedfj; the gnc1osure.
Responses to the enclosed request shou]d Pesubmjtteds by,,hIay10, 1981.,If you cannot meet this date, p1ease inform usjrjthij seyqJi.days after t'ecejpt, of this letter of the date you jl.ay fo. submit your responses...s Please contact hIr, Nerses, (301-492-7468),St.
Lucie,,2 Prospect,JIaJiygep,, if...
you desire any discussion or,c1ajifjcatiop of,the enclysed reppyt.
Sincerely, Encl osur e:
As stated Robert L. Tedesco, Assistant Director for Licensing Division of Licensing s3/
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Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology Florida Power
& Light Company P. 0.
Box 529100 Ni ami, Florida 33152 CC:
Harold F. Reis, Esq.
Lowenstein, Newman, Reis, Axelr'ad
& Toll 1025 Connecticut Avenue,.N.
W..
Washington, D.
C.
20036-Norman A. Coll, Esq.'cCarthy,
- Steel, Hectory
& Davis
, 14th Floor, First National Bank Building Miami, Flori da 33131 Hr. Hartin H'. Hodder 1131 N.
E.
86 Street Miami, Flor ida 33138 Dr. David L. Hetrick Professor of Nuclear Engineering The University of Arizona, Tucson, Arizona 85721 Dr. Frank F.
Mooper School of Natural Resources Universi ty of Nichi gan Ann Arbor, Michigan 48104 Resident Inspector
't. Lucie Nuclear Power Station c/o U, S. Nuclear Regulatory Commission P. 0.
Box 400 Jensen, Beach, Florida 33457 Edward Luton, Esq.,
Chariman Atomic Safety
& Licensing
'US Nuclear Regulatory Commission
.: Washingtpn, DC 20555
~
~
ADDITIONAL INFORMATION RE(U I RED BY.
CHEMICAL ENGINEERING BRANCH FROM ST.
LUCIE PLANT -.UNIT NO.
2
" CHEMICAL TECHNOLOGY SECTION/CHEMICAL ENGINEERING BRANCH (CMEB) 281.1 (9.1.3) 281. 2 (6.1.2)
Regarding the Spent Fuel Pool Cleanup
- System, provide the followiqg information:
Describe the samples and instrumentation and their frequency of measurement that will"be performed to monitor the Sp~-nt Fuel Pool water purity and need for ion exchanger resin and filter'eplacement.
State the chemical and radiochemical limits to be used in monitoring the. spent fuel pool water and for initiating corrective action.
Provide the basis for establishing these limits.
Your response should consider variables such as:
boron concentration, gross ganma and iodine activity, demineralizer and/or filter differential pressure, demineralizer decontamination
- factor, pH and crud level.
Indicate the total amount of protective coatings and organic materials (including conduit covered and uncovered cable insulation)'sed inside the containment that do not meet the requirements of,ANSI N101.2( 1972) and Regulatory Guide 1.54.
Evaluate the generation Fates and total quantity of combustible gases that can be formed fror. these unqualified organic materials under DBA conditions.
Also evalua1e the amount (volume) of solid debris that can be formed from the.e unqualified organic materials under DBA conditions that can reacl<, the containment sump.
Provide the technical basis and assumptions
- u. ed for this evalu-ation.
281. 3 (6.5.2)
(6.1.1 BTP MTEB 6-1) 281.4 (9.3.2) 281.5 (9.3.2) 281. 6 (9.3.2 and Action Plan II.B.3)
. Describe the containment sump design features to promote mixing of ECCS and spray solutions to maintain proper sump cher~istry.
Allowance should be made, for "dead" volumes, sumps, etc., in the determinati'on of sump pH andthe'uantities of trisodium phosphate dodecahydrate (TSP) used to verify that no areas accumulate pH solutions
<7.0 and that the assumptions regarding pH in the modeling of containment spray fission product removal are valid.
Verify that sample line purge flows and duration time s are sufficient to flush out stagnant lines to assure that a represer tative sample is obtained (The NSSS vendor'ecommends a flush of 6-10 sample line volumes, at a purge flush rate of about 2-3 times the sample iIlow rates).
In paragraph 9.3.2;2 you indicate that all secondaryI'~sample lines are sized for 0.5 gpm flow and in paragraph 9.3.2.2.1 yo<'f mention that steam. generator blowdown sampling lines are sized for' gpm flow.
Resolve this discrepancy.
Describe the provisions to meet the requirements of I>>os'.-accident sampling of the primary coolant and containment atmoe'~here.
Th.
description should address all the requirements outliII~ed in Section II.B.3 of Enclosure 3 in NUREG-0737 (Clarifi('ation of TMI Action Plan Requirements) and should include the appropriate P
8 ID's.
In addition, if gas chromatography is useo for reactor coolant analysis, special provisions (e.g.,
pressure relief and purging) should be provided to prevent high-pressure carrier gas
\\
281.7 (9.3.4) 281.8 (9.3,4) from entering the reactor coolant.
With respect to clarification (4) in Section II.B.3 of NUREG-0737', if the chloride ccncentratjoq in the reactor coolant samples exceeds the limit in the Technic'j Specification, oxygen analysis will be mandatory.
Provide alamo either (a) a summary description of procedures for sample col'lection, sample transfer or transport, and 'sample analysis, or (b) copies of procedures for sample collection, sample transfer or transport, and sample analysis.
le In the FSAR you state that the Failure t1odes and Effects Analysis will be submitted later.
We require this analysis to complete our evaluation of the CYCS.
E The FSAR describes how the plant can be brought to cold shutdown without using non-seismic Category I letdown portion of the CVCS by running the charging pump with suction directly from the boric acid makeup tank, thereby, delivering 8X by weight boric arid to the Reactor Coolant System.
Since this flow path is not finally heat traced (Figures 9.3-5b and 5c), this conc'entrated boric acid may percipitate in the charging line due to cooling.
Desrribe the measures or design modifications to be taken to preve
>t possible blockage of the charging line due to precipitated boric acid.
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