ML20031F160
| ML20031F160 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/12/1977 |
| From: | Diianni D, Fairtile M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13319A640 | List:
|
| References | |
| FOIA-81-313 NUDOCS 8110190284 | |
| Download: ML20031F160 (6) | |
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NUCLE An REGULATORY cOMMIStlON
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,k S W ASHING T oN. D. C. 20550
.k ' ? p '?j #C n. 3 fiE Sep' ten 6er 12,1977 iD
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50-3 50-247 N
Licensee: ConsolidatedEdison(Con. Edison)
P - / / 2 $-
i Facilities:
Indian Pt.1 & 2 j
Subject:
MEETING MINUTES TO DISCUSS CilEMICAL CLEANING 0F PWR STEAM GENERATORS j
i On August 18, 1977, represer.tatives of Con Edison and ERDA met with regulatory sta'ff to discuss :.ethods for cheinical cleanin'g PWR steam I
l generators at Indian Point 1 and 2.
A list of attendees is attached.
I Corrosion products have been accuralating in the annuli between support I
plates and tubes of PWR steam generators. ' Corrosion product accumulation j
in a few steam generators, has been so extensive that tube denting occurred and in some cases tube l'eakage ensued. Furthermore, support
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plates have been cracked due to this corrosion product build-up.
High
,1 concentrations of Cl and/or PO 4 in the secondary side of the liquid l
phase of steam generators, attacking,Ni base alloys and carbon steels, appear to be major contributors in the build-up of these corrosion f
products.
This problem appears generic in nature, and those plants using brackish or sea water for condenser coolant are most susceptib1'e to to accelerated attack. The purpose of this, meeting was to, discuss ERDA's
!l sponsored programs addressing a possible solution for this problem.
The objective of these EP.2A programs is to develop methods for periodic removal of these corrosion products during plant shutdowns.
The fina?
Con
. deve, loped method would thar. be used as an industry-wide process.
Edison, responsible for i..plementin'g these pro' rams, described the g
ERDA covered chemical proposed cleaning methods for Indian Point 1 & 2.
cleaning in nuclear plants.
Carolina Power and Light presented demineralized water flushing experience of steam generators at H. B. Robinsen Unit 2.
Con Edir.on issued two subc:r.tr: cts (ihiliteurtoniand United Nuclear
(
Industries) to evaluate sr.eral candidate chemical cleaning solvents ar.d develop procedures for cleaning one steam generator at Indian Point 1.
Indian Point 2 uill be used to demonstrate the developed c1 caning process Cb10190es4310827 rara Au
? UDELL81-313 PDR
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C' in a commercial opera' ting reac,tcr. Typical solvents that will be t
evaluated are as follows:
10% EDTA, 1% N H, PH-7 to NH 0H, 1.
22 4
.1% 051-1 (Inhibitor) 2.
4.5% EDTA, PH7 to NH 0H, 4
.1% OSI-1 (Inhibitor) 10% Citric Acid,.1% OSI-1 (Inhibitor),PH-4 to NH 0H followed by increase in 4
3.
PH-7.5 to NH 0H,100 PPM N H22 4
4.
Proprietary solvents (DOW NS-4)
A schedule for implementing this program ij attached.
The safety significance of this program which has been startec', addresses the potenttil of plant material degradation that may result from che6ical Forthermore, a cleaning and handling potential radioactive wastes.
i safety study is in progress on the effect of tube vibration that may Such occur during steam generator operation after chemical cleaning.
concerns exist because the removal of corrosion products may result in
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'significantly enlargingthe annulus between the support plate and the
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outside diameter of the tube (.014 to.044 inches s).
Preliminary j
I calculations indicate that no destructive vibration is anticipated due l
toincreasedclearance(reportedbyF.GriffithandE.'Rabinowicz).
However, this preliminary conclusion is being confirmed by model testing.
l A six-tube array containing two support plates mocking up a typical section of the steam generator will be used in the model testing.
Vibration tests of straight and U-bend tube models in high velocity water and two-phase flow will be investigated for fatigue failure and fretting These vibration studies are being performed by Combustion corrosion.
' Engineering and are expected to be completed '.be' fore. starting ~ commercial demonstration in Indian Point 2.
Carolina Power, and 1.ight Comhany discussed the flushing of II. B. Robinson Unit 2 steam generators during plant shutdown to reduce water solubles During flushing, the water was brought to a slight and phosphates.
boil to improve solubility and tgiu tion. Sanp1Ing the bic.down after a,
[
twelve-hour flush indicated a threefold reduction in phosphates.
- However, i
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a It is not flushing did not appear to reduce the chloride concentration.
known how effective this flushing is in reducing 5.G. tube wastage.
l ERDA discussed the organic acid cleaning of fossil boilers and nuclear Some.. the plants that have been decontaminated in the past.
nuclear plants are as follows:
SENA SGHWR Shippingport N-Reactors NPD, Gentilly-1, Douglas Point Naval Reactors P was stated by the NRC' that the proposed test program involves Oh unreviewed safety question, and therefore,such a test program cannot be conducted without prior NRC approval. This position taken by the NRC is based on the interpretation of 10 CFR 50.59a cov,ering changes, tests Con Edison may f
'and experiments for operating nuclear power plants.
proceed without NRC authorization if they can' show that the proposed test program does not indicate the existence of an unreviewed safety question, and changes to the technical specification are not required.
T e discussion of the unreviewed safety question was left unresolved h
However, Con Edison.will provide the NRC with all at this meeting.
necessary information to assure that the safety integrity of all iffected l
systems and components are maintaindd. The following is typical information required for NRC review:
~
l A listing of all materials (identified as to components when 1.
applicable) exposed to the chemical cl.eaning solvents, 2.
T'est.res91ts of 'the material surveillance program, Analytical reports and test results of potential steam generator 3.
tube vibration to include straight and U-bend tubes, Pre-cicaning and post-cleaning inspection reports including all 4.
nondestructive test reruits, s
g A detailed description of the i.uintenance method and system 5.
modifications and/cr system additions for removing accumulated deposits and helping to maintain good secondary water chemistry,
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6.
A descriptien of the developed c1 caning procedures, including process system flow diagrams, 7.
Methods for handling potential radioactive wastes, including any temporary and permanent stora!p.; Consideration given on the radiological exposure to operating personnel during all phases of the cleaning operatinns.
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s Dominic C. Dilanni Engineering Branch l
Division of Opereting Reactors
Enclosures:
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[.b NRC Attendees Ip1 and IP2 Steam Generator ChETiCal Cleaning Morton B. Fairtile, Project Manager Schedule Oper& ting 8!eactors Branch f4 Division of Operating Reactors
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LIST OF. ATTENDEES
., August 18, 1977 Name Loca tion P. J. Pettit ERDA/ LWR Branch B. H. Webster Carolina Power and Light Company R. F. Dudley ERDA/ LWR B, ranch I. H. Welinsky Consui, tant to BNL '
J. R. Weeks Brookhaven National Laboratory l
E. A. J. Olson Con Edison Company j
C. W. Jackson Con Edison Company W. Stein Con Edison Com'pany l
J. Dusch
. Con Edison Companv 5, S..Rothstein '
Con Edison Company A. Flynn Con Edison Company l
P. McTigue Con Edison Company l
W. Way Carolina Power and Light Company K. I. Parczewski RSB/00R/NRC B. Buckley PSB/ DOR /HRC l
P. W. O'Connor
~ 0RBf2/ DOR /NRC j,
G. Lear ORBf3/DDR/NRC j-
.D. vanRooyen Brookhaven National Laboratory R. 7evadoski EEB/ DOR /HRC i
F. Clemenson PSB/0T/ DOR /NRC R. L. Wright ACRS/HRC H. E. Tilbe London l'uclear Decont. Ltd.
W. P. London & Associates P.11. Lang ERDA/LilR Branch H. B. Fairtile[
DOR /NRC,
'D. C. Di'lanni
' EB/ DOR /NRC' 4
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