ML20040D002
| ML20040D002 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/26/1982 |
| From: | Milam P TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20040C961 | List: |
| References | |
| NUDOCS 8201290464 | |
| Download: ML20040D002 (15) | |
Text
e
-o
-s UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
Docket Nos. 50-445 and TEXAS UTILITIES GENERATING
)
50-446 COMPANY, et. al,
)
)
(Application for Operating (COMANCHE PEAK STEAM ELECTRIC
)
License)
STATION, Units 1 and 2)
)
AFFIDAVIT OF P.
M. MILAM REGARDING CONTENTION &
(ROCK OVERBREAK)
I, P. M. Milam, being first duly sworn, do depose and state:
I was employed by Texas Utilities Generating Company /
Texas Utilities Services, Inc., in-the position of Quality Assurance Supervisor from June 6, 1975 to February 16, 1977.
During that time, I was responsible for assuring that specifications and procedures were followed for the placement of concrete for foundations to seismic Category I structures at the Comanche Peak Steam Electric Generating Station, Units 1 and 2.
My educational and-professional qualifications are attached to this affidavit.
This affidavit. addresses whether any loose rock or other foreign material was put into or allowed to remain in the foundation excavation prior to or during concrete placement for foundations of seismic Category I structures at Comanche Peak.
It also addresses whether any foreign material, loose rocks or voids (air pockets) were discovered F201290464 820126 PDR ADOCK 05000445 O
i o
= in those foundations after concrete placement and, if so, whether satisfactory corrective action was taken.
As Quality Assurance Supervisor, I was responsible-for supervising a program and staff which would assure that applicable specifications and procedures based on those specifications were followed.
This program included sur-veillance of quality assurance / quality control activities performed by independent' contractors concerning the concrete placement of foundations for seismic Category I structures.
During early stages of construction, I or my staff witnessed the preparation-for and placement of all major-concrete foundations for seismic Category I structures.
I or my staff also witnessed the preparation for and performance of repairs to nonconforming conditions identified in the foundations for seismic Category I structures.
Based on my personal knowledge, I can attest to the fact that all loose rock'or other foreign material was re-moved from the excavation site for the foundations of seismic Category I structures before concrete placement began.
In addition, repairs of rock overbreak and fissures were not allowed to begin until the areas undergoing repair were properly cleaned and all loose rock or other foreign material removed.
With the exception of the four incidents discussed below, I can also attest that all concrete placements for foundations to seimic Category I structures (including
o e
o
-,. those necessary to repair incidents of rock overbreak) were done in accordance with applicable specifications and pro-cedures and that there is no evidence of loose rock, foreign material or voids in them.
There were two instances in which foreign matter was present in the concrete foundations for seismic Category I structures.
First, a chainfall was imbedded in he base-mat of Unit 1 containment.
In addition, two wood spacers were left in a concrete placement.
With respect to voids, inspection indicated the presence of voids under the Unit 1 containment sumps.
The average void space was found to be 3/8 of an inch with maximum voids of 5/8 of an inch.
An additional void was found under the Unit I valve isolation embedment.
Each of these nonconforming concrete placement con-ditions were properly reported and corrected (where required) before construction resumed.
,n.
/
..f/
F'
^~
'~
W ?O
,ll Swern to before Iae this 26th day of January 1982.
Iiotary Public
.%*ri :L v.T.:..n s
?!OT.~07 MJM !C. E:t' ' :T** Tc?
l
'- O L ' n 1
Cw/'hed ta %
0::4 Can 7 C; m:-;rt?n Exp:n Na:ch 20, UJ3
9 o
y PRENTICE M. MILAM JR., P.E.
STATEMENT OF EDUCATIONAL AND PROFESSIONAL QUALIFICATIONS POSITION:
Senior Engineer FORMAL EDUCATION:
1952-1953, Civil Engineering University of Houston.
1953-1957, B.S. Civil Engineering A&M College of Texas.
(Texas Agricultural and Mechanical University).
Registered Professional Engineer, Texas Licensed Land Surveyor, Texas EXPERIENCE:
1977 - Present Texas Utilities Services Inc. Construction and Engineering.
Staff, Senior Engineer - Special assignments per Manager of Engineering and Construction, Comanche Peak Steam Electric Station.
1975 - 1977 Texas Utilities Services Inc. - Texas Utilities Generating Co. Quality Assurance Supervisor, Site, Comanche Peak Steam Electric Station.
1974 - 1975 Texas Utilities Services Inc. Quality Assurance Auditor.
1972 - 1974 Engineering Consultant in private practice, planning, development of construction drawings for residential subdivisions, utility ervices and -land surveying.
1967 - 1972 Dallas Power and Light Company. Manage the Underground Lines Construction Division.
1965 - 1967 Katy Engineering - A division of Warrior Constructors, Houston, Texas. Engineering Manager and Construction Project Engineer.
1962 - 1965 Del E. Webb Corporation. Vice President of Clear Lake Construction Co. - work included planning and construction of the Clear Lake City project for Humble Oil Refining Company.
1960 - 1962 City of Houston Public Works Department, Bridge Division.
Engineering design and specifications for structural projects.
1958 - 1960 Texas Highway Department (Texas Department of Transportation). Supervision of Structures, field inspection of structure construction.
1956 - 1958 Williams Brothers Construction.
Supervision of bridge construction and associated design of forming and scaffolding.
o e
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
TEXAS UTILITIES GENERATING
)
Docket Nos. 50-445 and COMPANY, et al.
)
50-446
)
(Comanche Peak Steam Electric
)
(Application for Station, Units 1 and 2)
)
Operating Licenses)
STATEMENT OF MATERIAL FACTS AS TO WHICH THERE IS NO GENUINE ISSUE REGARDING CONTENTION 2 Pursuant to 10 C.F.R.
S 2.749(a), Applicants hereby set forth a statement of material facts as-to which there is no genuine issue to be heard:
SCOPE OF CONTENTION 1.
Contention 2 concerns 32 topical reports or computer codes used by the Applicants in the Final Safety Analysis Report
("FSAR") for Comanche Peak, as follows:
1.
An Evaluation of Solid State L'ogic Reactor Protection in Anticipated Transients, WCAP-7706 (Non-Proprietary),
February 1973
.2.
Overpressure Protection _for Westinghouse Pressurized Water Reactors, WCAP-7769, October 1971 3.
Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, Revision 1, June 1972 4.
Evaluation of Steam Generator Tube, Tubesheet and Divider Plate Under Combined LOCA Plus SSE Conditions, WCAP-7832, December 1973 5.
LOFTRAN Code Description, WCAP-7907, June 1972 6.
FACTRAN - A FORTRAN-IV Code for Thermal Transients in a UO Fuel Rod, WCAP-7908, June 1972 2
o.
- i 10 3 7.
MARVEL, A Digital Computer Code for Transient analysis of a Multiloop PWR System, WCAP-7909, June 1972 8.
Fuel Assembly Safety Analysis for Combined Seismic and Loss of Coolant Accident, WCAP-7950, July 1972 9.
Reactor. Coolant Pump Integrity in LOCA, WCAP-8163, September 1973 10.
Safety Analysis of the 17x17' Fuel Assembly for Combined Seismic and Loss of. Coolant Accident, WCAP-8288 (Non-Proprietary), January.1974 11.
Documentation of Selected Westinghouse Structural Analysis Computer Codes, WCAP-8252, Revision 1, July 1977 12.
Hydraulic Flow Test of the 17x17 Fuel Assembly, WCAP-8279 (Non-Proprietary), February 1974 13.
Westinghouse Anticipated Transients Without Trip Analysis, WCAP-8330, August 1974 14.
An Evaluation of Loss of. Flow Accidents Caused by Power System Frequency Transients in Westinghouse PWRs, WCAP-8424, Revision 1, June 1975 15.
Fuel Rod Bowing, and WCAP-8692 (Non-Proprietary),
December 1975 16.
Improved Analytical Models Used in Westinghouse. Fuel Rod Design Computations, WCAP-8785 (Non-Pr op rietary ),
October 1976 i
17.
Westinghouse Emergency Core Cooling System Evaluation Model - Modified October 1975 Version, WCAP-9169 (Non-Propriet.ary), September 1977 18.
Properties of Fuel and Core Component Materials, WCAP-9224 (Non-Proprietary), September 1977 19.
MRI/STARDYNE, Static and Dynamic Structural Analysis System, User's Information Manual,' developed by and proprietary to Mechanics Research, Inc.
I l
l t
o 5 20.
SCONV, Gibbs & Hill 21.
SPECTRA, Gibbs & Hill 22.
Safety-Related Research and Development for Westing-house Pressurized Water Reactors, Program Summaries, WCAP-8768, latest revision 23.
THINC-IV, An' Improved Program for Thermal-Hydraulic Analysis of Rod Bundle Cores, WCAP-7956, June 1973 24.
Calculational Model for Core Reflooding After a Loss of Coolant Accident (WREFLOOD Code), WCAP-8171 (Non-Proprietary), June 1974 25.
WFLASH, A Fortran-IV Computer Program for Simulation of Transients in a Multi-Loop PWR, WCAP-8261, Revision 1 (Non-Proprietary), July 1974 26.
LOCTA-IV Program: Loss of Coolant Transient Analysis, WCAP-8306 (Non-Proprietary), June 1974 27.
SATAN-IV Program: Comprehensive Space-Time Dependent Analysis of Loss of. Coolant, WCAP-8306 (Non-Proprietary),
June 1974 28.
Containment Pressure Analysis Code (COCO),
WCAP-8326 (Non-Proprietary), June 1974 29.
Westinghouse ECCS Evaluation Model-A Summary, WCAP-8339, July 1974 30.
Westinghouse ECCS Plant Sensitivity Studies, WCAP-8356 (Non-Proprietary), July 1974 31.
Westinghouse ECCS Evaluation Model Sensitivity Studies, WCAP-8342 (Non-Proprietary) July 1974.
32.
Westinghouse ECCS Evaluation Model-- Supplementary Information, WCAP-8472 (Non-Proprietary), April 1975
-Q; y NRC STAFF ACCEPTANCE 2.
The~NRC Staff has accepted for use in nuclear power reactor license applications the following topical reports or computer programs:
Numbers 4, 5,
8, 10, 11, 12, 16,'23 - 32.
" Topical Report Review Status," NUREG - 0390, Vol. 5, No. 1 (July 15, 1981).
3.
Of the remaining topical reports, the NRC Staff has accepted Applicants' analysis of particular sequences of events which are based, in whole or in part, on the following topical reports or computer programs:
Number 3
See SER S 5.2.2, SSER S 5.2.2 Number 6
See SER S 15.1.2 Number 7
See SER S 6.2, SSER S 6.3 Number 9
See SER S 5.4.1 Numbers 1,13 See SER S 15.3.9, SSER S 15.3.9 Number 14 See SER S 15.2.2 Number 18 See SER S 4.2.1, SSER S 4.2.1 4.
Topical report Numbers 2 and 17 have not been used by Applicants in performing safety-related analyses in the FSAR.
Af fidavit of William R. Spezialetti at 4.
5.
Topical report Number 22 was submitted for informational purposes only.
FSAR S 1.6.
i N
o
- 6.
The topical report concerning fuel rod bowing (Number
- 15) was not relied upon by the NRC Staff in performing their analysis of this phenomenom.
SER S 4.2.3.
The Staff has approved an interim method for evaluating rod bowing and has found analyses results for Comanche Peak acceptable. SER S 4.2.3.
7.
The NRC Staff has accepted the analyses for which the codos employed by Gibbs & Hill (Numbers 19-21) were used in the Comanche Peak FSAR.
SER S 3.7.
i VERIFICATION OF COMPUTER CODES 8.
Number 19 is a widely recognized computer program in the public domain which has been employed for approxi-mately 12 years by many engineering organizations for performing structural analyses of buildings.
This program has had a sufficient history of use to justify its applicability and validity without fur ther demonstration. Af fidavit of Chun-Mong Jan at 2.
9.
Numbers 20 and 21 are computer codes which have been verified by Gibbs & Hill.
The SCONV code (Number 20) was verified by comparing results obtained from sample problems using the CSMP code, which is a well-recognized and accepted IBM scientific program.
The SPECTRA code
1 t
, (Number 21) was verified by comparison of results obtained using the code with those interpolated from NRC Regulatory Guide 1.60. Affidavit of Cnun-Mong Jan at 3.
10.
Westinghouse computer programs are subject to one or more verification techniques which provide assurance that the computer program will produce accurate (or conservative) results.
Verification of these programs is performed pursuant to Westinghouse procedures established prior to the initiation of work on the Comanche Peak FSAR.
Afticavit of Arthur C. Spencer.-
-r
e i
G UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
Docket Nos. 50-445 and TEXAS UTILITIES GENERATING
)
50-446 COMPANY, g al.
)
)
(Application for Operating (Comanche Peak bteam Electric
)
Licenses)
Station, Units 1 and 2)
)
STATEMENT OF MATERIAL FACTS AS TO WHICH THERE IS NO GENUINE ISSUE REGARDING CONTENTION 7 Pursuant to 10 C.F.R.. S 2.749(a), Applicants hereby set forth a statement of the material facts as to which there is no genuine issue to be heard:
OVERBREAK AND FISSURES 1.
During excavation for seismic Category I structures at Comanche Peak, there were incidents of detrimental rock overbreak around the foundations of both Containment Builaings and under the Fuel Building.
Affidavit of Raymond C.. Mason at 1.
2.
These inciaents of rock overbreak were repaire6 in accordance witn applicable specifications and procedures.
Affidavit of P.M. Milam at 3.
O i
'4 5
_2_
3.
The performance of foundations for seismic Category I structures during a seismic event would be no cifferent than if the rock overbreak had not occurrea.
Affidavit of Ralph McGrane at 2.
4.
Fractures were also identified in the rock on which or against which the founaations fcr Unit 1 Containment, Unit 1 and 2 Safeguard Buildings and the Fuel Building would be poured.
Affidavit of Raymond C. Mason at 2.
5.
These fractures were prope:;1y identified, mapped for grouting and repaired in accordance with the applicable specifications and procedures.
Affidavits of Raymond C.
Mason at 2 and John T.
Merritt at 1-2.
6.
The performance of the foundations located above or adjacent to these repaired fissures during a seismic event will be no different than if such fissuring had not occurreo.
Affidavit of Ralph E. McGrane at 2.
LOOSE ROCK, FOREIGN MATERIAL AND VOIDS 7.
No loose rock or other foreign material was allowed to remain in the excavation site of foundations for seismic Category I structure's and such sites were properly cleaned before foundation placements began.
Affidavit of P.M.
Milam at 2-3.
v 4
v 8.
The only two instances in which foreign material and/or loose rock was found to be present in foundations to seismic Category I structures were when a chainfall was imbeddea in the base mat of Unit 1 containment and two wood spreaders were leo in a concrete placement.
Affidavit of P.M. Milam at 3 and Charles A. Gatche'll at 2.
9 The only two instances of voiding in foundations to seismic Category I structures occurred under both sumps in the Unit 1 containment base mat and under the Unit 1 valve isolatior embedments.
Affidavits of P.M.
Milam at 2 and Charles H. Gatchell at 2.
10.
Corrective action if necessary was taken to repair incidents of foreign material and voics discovered in foundations to seismic Category I structures.. Affidavits of Charles H. Gatchell at 2-3 and P.M.
Milam at 3.
11.
There is no foreign material, loose rock and/or voids in the foundations of seismic Category I structures which will have an effect on the static, dynamic and engineering properties of those structures.
Affidavits of Charles H.
Gatchell at 3 and P.M. Milam at 3.
O O
4 9
I I
DothETU uw UNITED STATES OF AhERICA NUCLEAR REGULATORY COMMISSION
'82 JAN 27 A9:45 BEFORE THE ATOMIC SAFETY AND LICENSING BOARD 0Ff KE G E u"-
00cKETmG & S.LRi In the Matter of
)
6 RANCH
)
TEXAS UTILITIES GENERATING
)
Docket Nos. 50-445 COMPANY, et al.
)
50-446
)
(Comanche Peak Steam Electric )
(Application for Station, Units 1 and 2)
)
Operating License)
CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing
" Applicants' Motion for Summary Disposition of CFUR's Contentions 2 and 7",
in the above-captioned matter were served upon the following persons by express delivery
(***),
by overnight delivery
(**),
or by deposit in the
' United States mail, first class postage prepaid this 26th day of January, 1982, or by hand delivery on the 27tn day of January 1982 (*):
- Marshall E.
Miller, Esq.
Chairman, Atomic Safety and Chairman, Atomic Safety and Licensing Appeal Panel Licensing Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C.
20555 washington, D.C.
20555
- Dr.
Kenneth A. McCollom
- Marjorie Ulman hothschild, Esq.
Dean, Division of Engineering Office of the Executive Architecture anc Technology Legal Director Oklahoma State University U.S. Nuclear Regulatory Stillwater, Oklahoma 74074 Commission Washington, D.C.
20555
- Dr. Richard Cole, Member Atomic Safety and Licensing David J. Preister, Esq.
Board Assistant Attorney General U.S. Nuclear Regulatory Environmental Protection Commission Division Washington, D.C.
20555 P.O. Box 12546 Capitol Station Chairman, Atomic Safety and Austin, Texas 78711 Licensing Board Panel U.S. Nuclear Regulatory
- J.
Marshall Gilmore, Esq.
Commission 1060 W.
Pipeline Road Washington, D.C.
20555 Hurst, Texas 76053
+. **Mr.
Richard Fouke Mr. Chase R. Stephens 1669-B Carter Drive' Docketing & Service Branch Arlington, Texas 76010 U.S. Nuclear Regulatory Commission
- Mrs. Juanita Ellis Washington, D.C.
20005 President, CASE 1426 South Polk Street
-Dallas, Texas 75224
,I
}
Y b
William A.
Horin cc:
Homer C. Schmidt Spencer C.
Relyea, Esq.
l l
I
.