ML20236A049
| ML20236A049 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/23/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Butterfield L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8707270418 | |
| Download: ML20236A049 (5) | |
Text
-
2 in July 23,1987
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DISTRIBUTION,,q s
i DocketsJ11esin i
Docket Nos. 50-2951 NRC & Local PDRs-and 50-304
.PDIII-2 Rdg. File l
GHolahan CVogan Mr. L. D. Dutterfield JNorrst-Licensing Manager 0GC-Bethesda Commonwealth Edison Company.
EJordan Post Office Box 767 JPartlow Chicago, Illinois 60690 ACRS(10)
PDIII-2 Plant File
Dear Mr. Butterfield:
As a result of the Surry pipe erosion / corrosion incident'in December of 1986,-
the NRC is preparing a report that will reference existing research information available and describe the actions being taken by utilities regarding erosion / corrosion in feedwater pipes in nuclear power plants.
~
Central to an understanding of erosion / corrosion in pipes is an accurate assessment of erosion /corroison experience, piping design, feedwater and condensate chemistry and piping materials.
To ensure that both the NRC and the nuclear industry have available a comprehensive collection of data regarding erosion / corrosion in feedwater pipes, the NRC will assemble a summary of utility infohnation related to ongoing water chemistry actions in pressurized water reactors. To accomplish this task we.ask that you complete-the enclosed questionnaire.
The information being requested'is quite extensive and will require a diligent effort on your part and ours to assure accurate and timely completion. Also, we realize that parts of the information may already be available to the NRC, but not in a convenient format which 'is readily accessible. Therefore, we request that you assist us by returning for each unit a single completed copy of the enclosed questionnaire to the Project Manager, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, within 60 days of receipt of this letter. We believe the questionnaire is self explanatory; however, if questions arise or clarification is required' please contact your NRC Project
- g f
Manager.
i j
8707270418 870723 PDR ADOCK 05000295 P
Mr. L. D. Butterfield Commonwealth Edison Company 2
I This request is covered by Office of Management and Budget Clearance Number 3150-011 which expires December 31, 1989. Comments on burden and duplication may be directed to the Office of Management and Budget, Room 3208, New Executive Office Building, Washington, D.C.
20503.
Sincerely, Original Signed by/
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects' - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
PWR Erosion-Corrosion Questionnaire cc:
See next page
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PDIIIk:PM P W:PD JNorr's:bj Wef 7/ /87 J/87 l
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- Mr. L. - 0. Butterfield, Jr..
Commonwealth Edison Company Zion Station CC:
Robert J. Vollen,-Esquire
. Mr. Michael C. Parker, Chief -
-109 North Dearborn Street Division of Engineering Chicago, Illinois 60602 Illinois Department of Nuclear 4
Safety 1035 Outer Park Drive, 5th Floor Dr. Cecil Lue-Hing Director of Research and Development-
-Springfield, Illinois 62704
, Metropolitan. Sanitary District of Greater Chicago.
i 100 East Erie Street-Chicago, Illinois. 60611-
'Mr. P. Steptoe Isham, Lincoln and Beale Counselors'at Law
~Three First National Plaza r
Sist Floor Chicago', Illinois 60602 j
4
' Mayor:of Zion Zion, Illinois 60099 l
i Illinois Department of Nuclear Safety ATTN: Manager, Nuclear Facility Safety l
1035.0 uter Park Drive; 5th Floor
. Springfield, Illinois 62704 U.S. Nuclear Regulatory Commission Resident Inspectors Office l
105 Shiloh Blvd.
Zion, Illinois 60099 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
)
l J
-- _ = - _ - - - -
r [
l' PWR EROSION-CORROSION QUESTIONNAIRE (Check or Circle All Applicable)
Utility Company:
Unit Name:
MWe-
' filled by:
Date:
Phone No.
In servicea 19....
Water Treatment:
AVT with anmonia, morpholine, hydrazine.
Condensate polisherst 'none, cation, powdex, mixed bed;......% of feedwater flow; installed 15....; operated in: H-OH, NH4-OH form.
Cooling waters fresh, salt, brackish, cooling tower.
Copper alloy condenser tubing: yes, no. Copper alloy FW heater tubes: LP, HP, none.
Boric acid used since 19
...I durings operation, layup. Iow load soaks, other.......
'A.
EROSION-CORROSION EXPE.RIENCE I.
Erosion-Corrosion' identified in wet steam piping: yes, no.
- 2. -Erosion-Corrosion of MSR Chevrons or mesh: yes, no.
Chevron materials stainless steel, carbon steel other.....................
3.
Erosion-Corrosion of feedwater piping: yes, no.
Date.found...................
Feedwater piping materials:.................................................
.4.
Erosion-Corrosion of:..... e l bows,....,. T s,..... - d if fusers,...... : reducers.
.... valves,-.... orifices
.... other components (specify)......'............
5.
Erosion-Corrosfon of J-Tubes: yes, no.
6.: Eroston-Corrosion of.feedwater distribution ring: yes, no.
's.
Erosion-Corrosion of turbine:
8.
Eroston-Corrosion of other cycle components (identify)...................... 6' 9.
Feedwater temperature range where erosion-corrosion founds from
....'to..... F 10.
Inspection frequency for.feedwater piping..... years. Steam-lines..... years.
11.
Inspection methods usedt ultrasonic thickness, radiography, visual, other......
B.
PIPING DESIGN 1.
Maximum feedwater flow velocity............ feet /second.
2.
No. of feed pumps operat ing at 1007, load..... -... second pump On at.....% load.
3.
Maximum flow velocity when only 1 pump is operating............... feet /second.
4.
No..of feedwater piping components:....... elbows,...;.. Ts,....... diffusers,
...... reducers,...... Valves....... oriflCes,
...... other components (specify) 5.
Maximum flow velocity in wet stean. piping............ feet /second.
Feedwater pressures and temperatures (a (preferred) or design):
f_qll load (pressure. psla/ temperature gtual 6.
f):
P:
P:
P:
P P:
T T
T:
T:
T:
p u
a r
ir ir g
Con ensate Pump Cond. Polishers BF Pump Steam Generators
'O low load (typical.. 1 of full load):
P P
P:
P:
P n
T T
T:
Ts.....
T:
U (f
k Q'
U F
g p
7 Cond1!rnsate Pump Cond. Polishers SF Pump Steam Generators Please attach cooles of the heat balance diaorams for your actual full load and typical low load.
C.
FEE 0 WATER AND CONDENSATE CHEMISTRY l
1.
Please complete the attached Table.
2.
feedwater chemistry history (average or typical values, final feedwater):
Year of oper.:
Ist 1974 1976 1978 1900 1982 1983 1985 1986 1987 pH of FW maximum.
minimum.
average.
pH of condensate maximum.
mlnimum.
average.
D0, ppb maximum.
minimum.
SVerage.
Cat. Cond. uS/cm.
Spec. Cond, uS/cm.
NH, ppb Nk, ppb 8$r8n. ppb Air Inleakage.
SCfn Please send any water chemistry sununary reports and data _._
3.
Chemical additions 3.1 Ammonia:-' typical concentration in feedwater.... ppb added at...........
3.2 Hydrazine typical concentration in feedwater.... ppb added at.........
3.3 Boric acid: typical concentration in feedwater.... ppb as B;
. added at..................
D.
MATERIALS 1.
Feedwater piping - list ASTM or other specification numbers....................
2.
Wet steem piping:
3.
Attach results of chemical analysis by you or pipe vendors.
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