ML19329E312
| ML19329E312 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 08/21/1978 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8006120620 | |
| Download: ML19329E312 (6) | |
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NUCLEAR REGULATORY COMMISslON g
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.Y WASHINGTON. D. C. 20555 V
Docket No:9 -3293 30 Consumers Power Company ATTN: Mr. S. H. HOWELL Vice President 212 West Michigan Avenue s
Jackson, Michigan 49201 Gentlemen:
SUBJECT:
PWR STEAM GENERATOR CONFERENCE The Division of Operating Reactors, Office of Nuclear Reactor Regulation, has organized a two-day PWR Steam Generator Conference to be held at the Holiday Inn in Bethesda, Maryland on September 7 and 8, 1978.
The purpose of the conference is to provide an oppor-tunity for industry, government, national laboratory, foreign, and -
possible public representatives to present and discuss operating experience relevant to steam generators and to exchange ideas for integrating design, inspection and operating procedures to ensure more reliable, safe operation of steam generators at nuclear power facilities.
Attached for your use is a Notice of the Conference and a tentative agenda.
Please notify Dr. B. D. Liaw, Division of Operating Reactors, U. S.
Nuclear Regulatory Commission, Washington, D. C. 20555, telephone (301) 492-8060 of your intent regarding attendance at the conference by August 25, 1978.
Sincerely, D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management
Enclosures:
1.
Notice of Conference 2.
Tentative agenda Mb ~
8000"120 h O cc w/ enclosures:
See Page 2 g
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p Consumers Power Company ccs:
Michael I. Miller, Esq.
Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Judd L. Bacon, Esq.
Consumers Power Company
-:212 West Michigan Avenue
' Jackson, Michigan 49201 Mr. Paul A. Perry Secretary Consumers Power Company 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.
e One IBM Plaza Chicago, Illinois 60611 I
Honorable Curt Schneider Attorney General State of Kansas Topeka, Kansas 66612 Irving Like, Esq.
Reilly, Like and Schneider 200 West Main Street Babylon, New York 11702 James A. Kendell, Esq.
Currie and Kendall 135 North Saginaw Road Midland, Michigan 48640 Lee Nute, Esq.
Michigan Division The Dow Chemical Company 47 Building Midland, Michigan 48640 9
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1 ENCLOSURE NO. 1 CONFERENCE NOTICE The Nuclear Regulatory Commission will sponsor a two-day Pressurized Water Reactor Steam Generator Workshop at the Holiday Inn in Bethesda, Maryland on September 7 and 8,1978. The purpose of the workshop is l
to provide an opportunity for industry, government, national laboratory and foreign organizations, and possibly, public representatives to
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present and discuss operating experience relevant to steam generator l
tube degradation and to exchange ideas for integrating design, inspection and operating procedures to ensure safe operation of steam generators at nuclear power facilities. The workshop will be comprised of presentations by invited speakers followed by a panel discussion..
Requests for additional information, including requests to participate, should be addressed to Dr. B. D. Liaw, Division of Operating Reactors, U. S. Nuclear Regulatory Commission, Washington, D. C.
20555.
Telephone (301) 492-8060.
A tentative agenda of the workshop is attached.
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ENCLOSURE NO. 2 PRESSURIZED WATER REACTOR STEAM GENERATOR WORKSHOP DIVISION OF OPERATING REACTORS OFFICE OF NUCLEAR REACTOR REGULATION U. 5. NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C.
20555 General Chairman:
Darrell G. Eisenhut, Assistant Director for Systems and Projects Division of Operating Reactors September 7,1978 8:00 a.m.
Registration INTRODUCTORY SESSION:
D. G. Eisenhut 9:00 a.m.
- Opening and Welcome Remarks (V. Stello) 9:10 a.m.
Licensing Bases for Continued Operation of PWR Steam Generators (D. G. Eisenhut) 9:30 a.m.
NRC Confirmatory Research Programs (C. Z. Serpan)
- Coffee Break -
GENERAL SESSION:
L. C. Shao 10:00 a.m.
Westinghouse Steam Generator Operating Experiences (Representative - Westinghouse Electric Corporation) 10:30 a.m.
Combustion Engineering Steam Generator Operating Experiences (Representative - Combustion Engineering) 11:00 a.m.
B&W Steam Generator Operating Experiences e
(Representative - Babcock & Wilcox, Inc.)
- Lunch Break -
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O TECHNICAL SESSION I:
J. P. Knight 1:30 p.m.
- Eddy Current Inspection Method Evaluation (Representative - Battelle Columbus) 1 2:00 p.m.
- Advanced ECT Probe Development (Representative - ZETEC, Inc.)
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.I 2:30 p.m.
- PNL Steam Generator Tube Integrity Program (Representative - Pacific Northwest Laboratory) j
- Coffee Break -
3:30 p.m.
- BNL Stress Corrosion Tests (Representative - Brookhaven National Laboratories) l i
4:00 p.m.
- DOE Chemical Cleaning Program (Representative - U. S. Department of Energy)
September 8, 1978 TECHNICAL SESSION II:
B. D. Liaw.
- Model Boiler Test for Reproducing Tube Denting) 9:00 a.m. '
(Representative - Combustion Engineering, Inc.
9:30 a.m.
- Improved Westinghouse Steam Generator Design to Avoid Various Forms of Tube Degradation (Representative - Westinghouse Electric Corporation) 10:30 a.m.
- Experience with Condenser Failures, Retubing and Consequence (Representative - Westinghouse Electric Corporation) 11:00 a.m.
- Turkey Point Steam Generator RepTacement Program 1
(Representative - Bechtel Power Corporation)
- Lunch Break -
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PANEL DISCUSSIONS:
D. G. Eisenhut 1:30 p.m.
Panel Members:
J. R. Weeks, L. Frank, J. Muscara, J. Scinto, F. Almeter, B. D. Liaw, and various industry representatives
. Need for Secondary Water Chemistry Control Steam Generator Tube Denting, Support Plate Cracking t
and Deformation
. Regulation and Regulatory Gutde Interpretations -
Tube Plugging Criteria, ISI Requirements
.- Development ECT Inspection Techniques
. Additional Research Programs
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IE Circular No. 77-06 April 5, 1977 EFFECTS OP !!YDRAULIC FLUID ON ELECTitICAL CABLES DESCRIPTIOt OF CIRCU11STA;;CES:
Cotononucalth' Edison Company, by letter to the NRC dated April 1, 1976, (copy enclosed), described the circumstances under which fire resistant hydraulic fluid had a deleterious effect on the innulation and jacketinr, of cicctrical cabics.
k'hile the solvent characteristics of phosphate-cater fire resistant fluids are well documented in literature, it appears that thin information may not be generally availabic to nuclear power plant operating staffs. Our evaluation of this occurrence emphasizes the importance of:
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1.
Reviewing design and operating procedures for systems containing synthetic hydraulic fluids and other potentially aggressive fluid.4 to minimize the probability of Icakage, overflow or inadvertant spill of' fluid.
2.
Reviewing houscheeping practices to assure that they provide for prbmpt cicanup of spills or leakage of any type of fluid.
Enclosure:
Letter from Commonwealth Edison Co.
to J. Keppler, Director, Region III dtd. 4/1/76 g.,
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l The next course of action was to determine tr c types of cable in the Unit 1 cable tunnel that were' af fected by the CllC fluid.
The types of cable construction wnre categorized as foilows:
Control & Power (Iow voltage):
Individual or multiconductor PVC 1.
Jacketed; mylar wrapped, PVC,over butyl rubber insulated conductors.
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Instrumentation:
PVC jacketed, shleided, mylar wrapped, ' polyethylene insulated conductors.
3 Instrumentation:
Single and multiconductor PVC Jacketed, polyethylene insulated, mylor wrapped and shicided twisted pairs.
4.
Instrumentation:
PVC Jacketed, polyethylene insulated, coaxial cable.
The control and power cables comprised approximately 80% of all cables in the Unit 2 cable tunnel.
Close inspection revealed that the EHC fluid had not permeated through the PVC overall Jacket.
Since butyl rubber is not affected by EHC fluid, it was' recommended that these cables be cleaned and lef t in place after the cable pans were cleaned out.
The Instrumentation cables as described above in cases 2 and 3 revealed that 'some saturation through the overall PVC jacketing resul ted.
- However, in no cases had the EHC fluid permeated through the mylar shielding covering.
It was recommended that the plasticized sections of jacketing be removed and a suitable Jacketing tape be applied.
Case 4 as described above, consisted of coaxial nuclear instrumentation The coaxial cables' overall jacketing is very thin and consequently cables.
suffered greatly from the effects of plasticization.
Plastic 1:ation had exposed the, shielding conductor, such that possible electrical interference could resul t.
The coaxial cables' functions ware as follows:
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Local Power Range Monitoring (LPRM)'
2.
Intermediate Range Monitoring (IRH) 3 Source Range Monitoring (SRM)
Since there were only 90 coaxial cables affected by the EHC fluid, it was recommended to splice in new coaxial cable sections and not tape over the shleiding.
Splicing in this case was considered more acceptable than taping.
All coaxial cables were identified and labeled before splicing was permitted.
cables were tested against acceptable electrical properties The coaxial after being spliced, figure 1 shows the approximate locations where CHC fluid accumulated.
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Figure 2 illustrates the postulated path of EHC flui/ 6 Njration from the EHC fluid reservoir to the Unit 2 cable tunnel are4.
7:e accumulation of EllC fluid around the EHC fluid reservoir fovad,tl*e and subsequent migration between the finish floor and rough si L. v:. _, mall cracks in the concrete, is the postulated cause of the EHC fluid prabiem.
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