ML20027B573
| ML20027B573 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/17/1982 |
| From: | Ridgway D SHAW, PITTMAN, POTTS & TROWBRIDGE, WISCONSIN ELECTRIC POWER CO. |
| To: | Bloch P, Kline J, Paxton H Atomic Safety and Licensing Board Panel |
| Shared Package | |
| ML20027B574 | List: |
| References | |
| NUDOCS 8209210299 | |
| Download: ML20027B573 (3) | |
Text
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e 00CKETED SHAw PITTMAN, PoTTs & TROWBRIDGE e
A PARTNERSMep OF PROFESSsONAL CORPORATIONS 82 S9 20 m 1800 M STR E ET. N. W.
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- NOT ADeaiTTED ese D C WRITER S DIRECT OtAL NUMBER (202) 822-1227 September 17, 1982 Peter B. Bloch, Esquire Dr. Jerry R.
Kline Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C.
20555 Washington, D.C.
20555 Dr. Hugh C. Paxton Administrative Judge Atomic Safety and Licensing Board Panel 1229 41st Street Los Alamos, New Mexico 87544 In the Matter of Wisconsin Electric Power Company (Point Beach Nuclear Plant, Units 1 & 2)
Dear Administrative Judges:
Enclosed is a copy of the " Affidavit of W.D. Fletcher,"
in response to the Board's question on radiolysis in the sleeve /
tube annulus, which was posed in the course of the September 9 conference call in this proceeding.
82092102 D b sD3 a
SHAW, PITTMAN. PoTTs & TROWBRIDGE A PARTNERSMap OF PROFESSIONAL ComPORAfiONS Letter to the Administrative Judges September 17, 1982 Page Two The substantive text of the affidavit is precisely the same as that transmitted to the Board and the parties by our letter dated September 16, except that the word "from" was inadvertently omitted from the third sentence of the first paragraph of the response transmittal previously; that error has been corrected in the enclosed affidavit.
Sincerely, 1-SHAW, PITTMAN, POTTS & TROWBRIDGE By
[d mp V' Bruce W. WhurchiU 0
Delissa A. Ridgway Counsel for Licensee Enclosure cc:
Service List e
0
UNITED STATES OF AMERICA NUCLEAR REGULATORY CO". MISSION Before the Atomic Safety anf Licensine Board (n the Matter of
)
)
ilSCONSIN. ELECTRIC POWER COPPANY
)
Docket Nos. 50-266
)
50-301
{ Point Beach Nuclear Plant,
)
(OL Amendment)
Units 1 and 2)
)
SERVICE LIST feter B.
Bloch, Chairman
'Stuart A. Treby, Esq.
\\tomic Safety and Licensing Office of the Executive Board Legal Director
.S.
Nuclear Regulatory Commission U.S.
Nuclear Regulatory Commissio
'asington, D.C.
20555 Washington, D.C.
20555
- r. Hugh C.
Paxton Richard G. Bachmann, Esq.
229 - 41st Street Office of the Executive os Alamos, New Mexico 87544 Legal Director U.S. Nuclear Regulatory Co:n.issior pr. Jerry R.
Kline Wasington, D.C.
20555
\\tomic Safety and Licensing Board Kathleen M. Falk, Esq.
- f. S.
Nuclear Regulatory Cc= mission Wisconsin's Environmental Decade 7ashington, D.C.
20555 114 North Carroll Street Suite 208 ttomic Safety and Licensing Madison, Wisconsin 53703 Board Panel
- f. S. Nuclear Regulatory Commission Francis X. Davis, Esq.
7ashington, D.C.
20555 Monroeville Nuclear Center Westinghouse Electric Corporatien ttomic Safety and Licensing P. O.
Box 355 Appeal Board Panel Pittsburgh, PA 15230
- f. S. Nuclear Regulatory Commission fashington, D.C.
20555 Barton Z.
Cowan, Esq.
John R.
Kenrick, Esq.
ocketing and Service Section Eckert, Seamans, Cherin & Mellott ffice of the Secretary Forty-Second Floor
.S.
Nuclear Regulatory Cc=missien 600 Grant Street ashingten, D.C.
20555 Pitcsburgh, PA 15219
~
o AFFIDAVIT OF W. D. FLETCHER Commonwealth of Pennsylvania:
l l
Ss County of Allegheny:
W. D. Fletcher, being duly sworn according to law, deposes.and says that:
(1) hy position and a statement of my professional qualifications are parts of the record in this proceeding.
(2)
In response to the question of what are the consequences of radiolytic production of oxygen from water contained in the sleeve-tube annulus region with regard to corrosion resis-tance of thermally-treated Inconel 600 sleeve material, my answer is:
The radiolytic decomposition of water is accompanied by the radiolytic recombination of hydrogen and oxygen species to reform water.
This leads to steady-state concentrations of oxygen in the water.
Radiolytic produc-tion of oxygen or oxidi=ing species from radiolysis of water in the annular region between a sleeve and tube is expected to be insignificant at steady-state conditions because of the relatively low gamma radiation field in that region.
The gamma radiation field in the sleeve / tube annulus at the steam generator inlet is only, on the order of 100 R/ hour with the plant operating at full power conditions.
This gamma energy arises primarily from the N-16 content of the reactor coolant.
e 2-9 Steady-state levels of oxygen from radiolytic decomposition of water at these low radiation levels are small, con-servatively estimated to be less than 1 part per billion.
Due to the radiolysis of water in the reactor coolant system, excess hydrogen is emp,loyed as the basis for oxygen control.
Small quantities of hydrogen from the reactor coolant dif-fuse through the Inconel sleeve wall at operating temperatures.
Thus, the water assumed in the annulus between the sleeve and tube is expected to have an excess hydrogen content.
The presence of this hydrogen further red' ces the concentration u
..uiolysis of water in of oxidizing species fc mou
..wm m.=
the sleeve-tube annulus.
Thus, the presence of an oxidiring environment in the sleeve to tube' annular region due to radiolysis of water that may be present, is not expected.
The corrosion testing program included corrosion tests where-thermally-treated Inconel 600 was evaluated in comparison with mill-annealed Inconel 600 in the presence of oxygen or oxidizing environments.
These tests demonstrated the enhanced corrosion resistance of thermally-treated Inconel 600.
Examples of these tests are summarized as follows:
Stressed specimens of mill-annealed and thermally-treated a.
Inconel 600 were exposed in high temperature water (572*F)
. containing 100 ppm, chloride, as Nacl, and 7.7 ppm oxygen for 2,034 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br />.
Examination of the samples following this test indicated intergranular stress' corrosion cracking in the mill-annealed material to have progressed to depth of 7 to 15 times that observed in the thermally-treated material.
This indicates that thermally-treated Inconel is substan-tially more resistant to intergranular stress corrosion cracking than mill-annealed Inconel 600, even at oxygen concentrations several orders of magnitude higher than
. expected by radiolysis of water. in the sleeve-tube annulus.
b.
Oxidizing environments have also been included during corrosion tests by impressing an anodic electrical potential on the test specimens.
Mill-annealed and thermally-treated Inconel 600 tubing specimens have been exposed to ' caustic solutions (0.1, 1, 10, 25 and 50 wt. percent) at 600 and 650'F where a range of electrical potentials of 0 to 250 millivolts was applied to the specimens.
In these tests, the thermally-treated material showed better corrosion resistance than the mill-annealed material.
The effect of oxidizing species in the corrosien test c.
environment has also been evaluated by including copper
i
-4 oxide in the caustic test solution.
After 4,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at high temperature (600*F) with a test mixture of 89 parts water, 10 parts sodium hydroxide and 1 part copper oxide only the mill-annealed material exhibited stress corrosion cracking, At more aggressive test conditions of 80 parts water, 10 parts sodium hydroxide and 10 parts copper oxide, mill-annealed and thermally-treated material showed approximately the same extent of stress corrosion cracking.
(3)
The averments in this Affidavit are true to the best of his information, knowledge and 'eelief.
Further the affiant sayeth not.
I W. D. Fletcher Sworn to and subscribed before me this 17th day of September, 1982.
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