ML19224C634
| ML19224C634 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 06/08/1979 |
| From: | Conner T CONNER, MOORE & CORBER |
| To: | Bechhoefer C, Bright G, Hooper F MICHIGAN, UNIV. OF, ANN ARBOR, MI, Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 7907060006 | |
| Download: ML19224C634 (13) | |
Text
.
LAW OFFICES Conza. Moons & Coa 3En 1747 PE NN S YLVAN I A AVE N U E. N. W.
Taor n. coxwz a. Ja.
wAS IIINGTON. D. C.
20006 Ky.j p,,'TN" [ ROOM Ancu a. Moo m s. Ja?
n KK( ((Ih> elb monsBT J. CORBER M.AR E J. WETTE R MAJEN June 8, 1979 oox.1.o J amx.s1.zv. Ja.
ROBERT M. RADER (202) 833-3500 E EIT H EE. E LJ.2 S
- l.ov amwarvu o tw a c.
CABLE AD D RES S: ATO N law Charles Bechhoefer, Esq.
Dr. Frank F.
Hooper, Member Chairman, Atomic Safety Atomic Safety and Licensing and Licensing Board Board U.S.
Nuclear Regulatory School of Natural Resources Commission University of Michigan Washington, D.
C.
20555 Ann Arbor, Michigan 48109 Mr. Glenn O.
Bright, Member
,',+
Atomic Safety and Licensing Board
' ;/
Q U.S.
Nuclear Regulatory
.ll
'h Commission Washington, D.
C.
20555
i 3,
[,f,
- 5:f,(
In the Matter of The Cincinnati Gas & Electric Company, et a (William H.
Zi=er Nuclear Power Staticn)
Docket No. 50-358 Gentlemen:
In accordance with the schedule established by the Licensing Board, enclosed is testimony relating to Contentions 14, 15 and 16, and the professional qualifications of Messrs. Schwiers, Santa and Pence who will join the panel on these contentions.
Sincerely, S
Mg 0 W 4..
Troy 3. Conner, Jr.
l/
Counsel for the Applicant Enclosure cc:
Per Service List o ( ) (s ij-i T007060006
APPLICANTS' TESTIMONY RELATING TO CONTENTION 14 CABLE TRAYS Cable trays at Zimmer are not Class 1 safety equipment.
Accordingly, there is no requirement for " certification" of welders as is required by the ASME Code Section 3, for pressure vessels for example.
However, each Husky welder was required to have a qualification test to establish his competence for the type of welds made on Zimmer Cable Trays.
The cable trays were manufactured in accordance with design specification requiring steel having a minimum yield of 30 KSI.
Design specification further required the cable trays to sustain a working load of 404 per square foot plus a load equivalent to 200 pounds at the mid-point of a 10 foot span with a minimum load (safety) factor of 2.0, when treated in acccrdance with NEMA Standard VM-1-3.01.
When this material is received at Husky, the receiver documentation is inspected to verify that the shipment meets these specifications.
Any cable tray which did not meet specifications was rejected following quality assurance visual inspcctions at Husky such that only trays meeting specifications were shipped to Zimmer.
Additional inspection was made upon receipt at the Zimmer plant to assure that there was no damage in shipment.
A point is suggested that the production welding techniques were not identical to the test welding techniques.
It is not known what is meant by a " technique" in this
'i n.t
['t.,. ',
s contexr.
Ecwever, the welding prccedures used in the qualification for Husky welders are identical to the welding procedures used in production of the cable trays for Zimmer.
The weld procedures refers to the physical steps that are taken to complete a weld.
The type of weld refers to the physical configuration of an actual weld.
The qualification tests administered to Husky welders required completion of horiscatal or vertical groove welds.
ASME Boiler and Pressure Vessel Code,Section IX, which was followed here, specifically provides that successful qualification to perform horizontal or vertical groove welds automatically qualifies a welder to perform horizontal or vertical fillet welds, respectively, as well as flat groove and fillet welds.
The welds employed in producticn of the cable trays provided to the Zimmer project are flat fillet welds.
A point is made that " meaningful" inspections of certain welds was made impossible because the trays were galvanized.
In fact, visual inspection at Husky as to acceptability of welds was made prior to galvanizing.
Folicwing Mr. Hofstadter's ccmplaint to the NRC and others, the NRC conducted an exhaustive inspection at the site as well as destructive testing to verify tensile strength and weld acceptability and prepared a report which was forwarded to the Board and parties by the Applicant in respcnse to MVPP's interrogatory No. 9 which is hereby incorporated by reference herein.
In essence, this report established that the NRC verified the material strength and "j n /
(1-weld acceptability referred to above and subjected sample parts to destructive testing.
It is important to emphasize that the trays were all manufactured to the same specification.
Therefore, contrary to intervenors' argument, it would not matter whether the specimen trays happened to be vertical or horizontal in use.
,c,,
\\
APPLICANTS' TESTIMONY RELATING TO CONTENTION 15 MANUFACTURE OF CCNTROL RCDS In Contention 15, the Miami Valley Power Proj ect as-serts that the size specifications for control rods were not met.
As demonstrated below, there is no basis for such assertion.
The centrol rods are described in detail in Section 4.2 in the FSAR beginning on Page 4.2-31 (See Figures 4.2-11 and 12 for specific dimensions).
The control rods were manuf ac-tured at General Electric's plant in Wilmington, North Carolina.
All quality assurance procedures at the manu-facturing facility were satisfied.
Control rods weI.e in-spected pursuant to General Electric's quality assurance procedures to assure that design specification requirements are met before being released for shipment to the Zi=mer site.
Control rods were packed and shipped according to special requirements which have been established to maintain the integrity and configuration of the rods and thus assure delivery to the site in the same condition as when they were packed at Wilmington.
Af ter the control rods were uncrated at the reactor site, and cofore installation into the reacter, they were As a inspected for possible shipping and handling damage.
result of this inspection, sur control rods did not =een n G (, O' l General Electric's inspection criteria and were returned to Wilmington and replaced.
Six other control rods had minor dimensional variations.
After an engineering analysis and subsequent inspections, these six were accepted for use.
As a part of the inspection at the reactor site, gages were used to check envelope requirements.
A forty pound spring clamp was used with these gages to remove normal sheath waviness.
The forty pound load removed waviness of the sheath without permanently deforming the sheath.
While certain damage such as significant dents or bent rods could be a reason for rejection, normal waviness, which is over-come by the clamp, is acceptable.
The control rod is designed to operate with substantial rubbing friction between the control rod and the fuel bundles which is substantially in excess of forty pounds.
Therefore, the forty pound inspection clamp load has no effect on safety or normal operation.
The NRC's Office of Inspection and Enforcement has verified the acceptability of the rods and has witnessed certain of the inspections.
In January 1979, during initial fuel leading at the Fukushima 6 reactor, it was noticed that several fuel chan-nels hit the small ledge that exists in the corner of the control rod wings at the top of the velocity limiter just before the fuel bundle seated on the orificed fuel support.
') G (
d:
_3-Under maximum material tolerance conditions, this ledge While nicking does could nick the corner of a fuel channel.
affect fuel channel or control red life or reactor not ledge was chamfered to eliminate the possibili-safety, the This chamfering was done with a handheld ties of nicking.
' burr).
high speed air motor containing a small milling tool The ledge nicked the fuel channel only at maximum material tolerance conditions.
Therefore, a gage was utilized which duplicated the f uel channel corner.
If the gage hit the ledge, the ledge was chamfered.
If the gage did not hit the ledge, no action was taken.
The result was that all corners of all control rods had to pass the gage before the control rod was accepted.
As the result of this operation, all control rods which have been installed in the Zimmer reactor meet all requirements for operation.
706 n' q
APPLICANTF' TESTD10NY REI.ATING TO CONTENTION 16 CONTROL ROD SEALS Miami Valley Power Project charges that the seals on the control rods which prevent radioactive water from leak-ing out when the reactor is shutdown '.or maintenance do not meet minimum specifications for smoothness.
As demonstrated below, there is no basis for such assertion.
Under, normal conditions, the primary seal which retains water in the reactor is that created by the mating surfaces of the control rod drive and control rod drive housing flanges.
The seal noted in Contention 16 is the velocity limiter to guide tube backseat.
These seals are shown in FSAR Section 4.2 in Figures 4.2-12, 13 and 14.
The only function that these control rod seals in question serve is to limit the leakage of water from the reactor vessel during the time when the drive mechanism is disassembled for maintenance.
Therefore, these seals would only see the pressure caused by the head of water in the vessel and are not subject to operating pressure.
They serve no other function.
The specifications for the seals, which are AISI Type 304 stainless steel, are a 63 RMS finish and dimensional constraints in size and shape.
To determine that these specifications were met, control rod seals were subjected to visual inspection with a compara-tor and a dimensional check in a special inspection fixture.
o n (,
('
These inspections are performed at Wilmington as a planned part of General Electric's Quality Assurance program.
After the control rods were shipped to the site, the seals were inspected for possible damage in shipment.
The visual inspection was conducted with a comparator.
One control rod was returned to General Electric and replaced because of a scratch across the seal surface.
All control rod seals installed at the Zimmer reactor meet design speci-fications for operation.
O r a,
- l
W. W. SCHWIERS
^
PRINCIPAL QUALITY ASSURANCE 5 ST7dDARCS ENGINEER N
THE CINCINNATI CAS & ZI.ECTRIC CCMPANY crg?2m tG.
CCVds My name is William W.
Schwiers.
I an empicyed by h)
The Cincinnati Gas & Slectric Cc=pany whose principal offices teca-are 1ccated at 139 E. ?curth S tree t, Cincinesti, Chic, 45202.
gg I as Principal Engineer of the cuality Assursace and pr.
Standards Section of the General Engineering cepartment in which ~s cacacity I am respcasible for the es tablishcent and i=pleanta-g tien of The Cincinnati Gas & Electric Cenpany Quality Assurance Q
Program for the Wm. E. Zin=cr Nuciaar Pcwer S tatice.
I function gm as the pricary centact siith the cifice of Inspectica and Enferce Od sent of Region III cf the Hucisar acquiatory Cc =issien.
I graduated f'rca the Calversity of Scuthern Ca #
a in 1946 and received a Bachelcr of Engineering Cegree in Mechan,.c#
Engineering.
I have attended specialized courses in Welding Inspectica, 3ccdestructive Exa=tnatice, and a ccmprehensive course provided by NUS Corpcration titled 'Introducticn to Nuclear Pcwcr".
The NiJS course covered 26 weekly sessions of four hcur duration and included subjects such as Intreduction to Nuclear Phisics, Reacter ber=al Hydraulic and Centrcl Characteristics, Chc=istry and Zadiatica Safe ty, and Nech Scver Plant.Cperaticn.
Prior to e=plcytent with The Cincinnati Gas & Electric Ccapany, I worked for cne and one-half years as a Cesign Engineer at the Wm. Pcwell Cc=pany designing high pressure steam and spec.alty type falves.
I have been ecpicyed by The Cincinnati Gas s Electric Cc=pany since June, 1948, working in the Mechanical Sectica of the General Engineering Cepart=cnt, the Plant Acccunting Divisien of the General Acccunting Cepart=ent, and in 1970, was assigned to the Cnality Assurance and Standards Section cf the General Engineering >partncnt.
My experience in Quality Assuranca censists of assistance in preparatica of The Cincinnati Gas & Electric Cc=pany Cuality Asser- :~ gram, conduct of audits of ficilitics of =anuf acturers su plying safety related ecuipcent, and for two years, I functiened as ric1d Quality Assurance Engineer dnring the early construction of the Wm. H.
Oir:.er Nuclear ?cwer Statien.
I represented The Cincinnati Cas & Electric Cc=pany as its Senior Field Prcject Engineer providing 11asen between The Cincinn'ati Gas s Electric Cc= any and the Architect Engineer, Cons tructor and various sub-centracters providing eculpment and ccnstruction services at the Zi.-- e r P ref ect.
In Sepec=ber, 1976, I was assigned the responsi-bility of Principal Engineer for the Gcality Assurance and S tandards Sectica of the General Encincerine Ccca--~--
nor n..)
t u
o I as an af filiate -a,5cr of ASME/MSPE since 1972.
I a r.
a ccmber of the Engineering Society of Cincinnati, the American Wclding Scciety and have been a ce=ter cf ASME for 70 years.
I represent C'.ncinnati Can & Electric Cc=pany as an organizational
= ember of AiTM.
PROFESSIONAL QUALIFICATIONS FRED L.
BANTA MANAGER ENGINEERING-INSPECTION AND DEVELOPMENT HUSKY PRCDUCTS, INC.
DIVISION OF BURNDY CORPORATION Education:
Bachelor of Science in Electrical Engineering, University of Cincinnati, 1975.
Bachelor of Business Administration, University of Cincinnati, 1967.
Employment:
Burndy Corporation District Sales Engineer, June 1967 -
December 1968.
1968 - 1970 - two years leave of absence to serve in the U.S. Army.
Husky Products, Inc.
Cable Bus Specialist, 1970-71 Marketing Manager, 1971-1976 Marketing-Engineering Manage, 1976-78 Engineering-Inspection and Development Manager, 1978-79.
Husky's principal business is the design, manufacture and sale of electrical cable trays for industrial applications.
I have been personally involved in each and every phase of the design, manufacturing and marketing of cable trays and cable tray accessory devices.
In my present position, I personally participate on a daily basis in the cperations involved in designing and manufacturing cable trays.
I personally observe welders and welding operations daily in the normal course of my employment in connection with design evaluations and quality assurance operations.
I personally perform welding operations for various 14-4ted purposes in connection with cesting and design of Husky cable trays.
,q g.
PROFESSIONAL QUALIFICATIONS VERNON W.
PENCE MANAGER DRIVE LINE CCMPCNENTS GENERAL ELECTRIC COMPANY My name is Vernon W.
Pence.
My business address is 175 Curtner Avenue, San Jose, California 95125.
I am Manager, Drive Line Components for the Boiling-Water Reactor Systems Department of the General Electric Company.
In this position I am responsible for the design, manufacture and field service of major components such as the control rods, hydraulic control units, control rod drive system hardware, and other components associated with the control rod drive system.
I have a Bachelors Degree in Mechanical Engineering from California Polytechnic State University, a Masters Degree in Engineering from University of Santa Clara and a Masters Degree in Business Administration, also from the University of Santa Clara.
I was employed for approximately six years by Lockheed Corporation in Sunnyvale, California as a design engineer where I was responsible for design of aircraft and missile components.
In 1968, I joined General Electric Company as a Design Engineer responsible for design and manufacture of ccmponents for boiling water reactors, including stress evaluation and
[ O b UI' b
compliance with applicable codes.
As stated above, since 1976 I have been Manager of the drive line components where I supervised the design, manufacture and field service of control rod and other components for boiling water reactors.
I am a Professional Engineer in the State of California.
.3 G, (,
(,1' G
~