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CASE EXHIBIT 766 UillTED STATES OF AMERICA
CASE EXHIBIT 766 UillTED STATES OF AMERICA p eonn # '*
          ,      p eonn # '*             T4UCLEAR REGULATORY COMMISS10rt                         5/4/83 BEFORE THE ATOMIC SAFETY AllD LICEllSING C0ARD in the Matter of g g cp APPLICAT10tl 0F TEXAS UTILITIES             I Do c ke t'M             50-G E riE R AT ! t(G C OMP A t1Y , ET AL. FOR A!1 OPERATING LICEtJSE FOR                                         ./ ,apdSg44
T4UCLEAR REGULATORY COMMISS10rt 5/4/83 BEFORE THE ATOMIC SAFETY AllD LICEllSING C0ARD in the Matter of g g cp APPLICAT10tl 0F TEXAS UTILITIES I
                                                                                    /
Do c ke t'M 50-G E riE R AT ! t(G C OMP A t1Y, ET AL. FOR
g
./,apdSg44 A!1 OPERATING LICEtJSE FOR
                                                                                          ,i't       vge,    j COMAtJCHE PEAK STEAM ELECTRIC                                     -
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                                                                                                      ~
,i't COMAtJCHE PEAK STEAM ELECTRIC g
STATION UNITS #1 At4D #2 (CPSES)                                      f                  * {-Q g,g                     .}
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                                                            ;                                      ,tco q ; ,+-vy>; 9 SURREBUTTAL TESTIM 0 fly OF MARK ANTHONY WALSii, !7. ,.a s             #
~
WITNESS FOR INTERVEN0R CASE               ' '. s   '
q,.
t 9.s-1           Q: Mr. Walsh, are you the same Mark Anthony Walsh who testified in 2       the July and September 1982 Operating license hearings for Comanche Peak?
/
3             A: ~Yes, I am.
f
4             Q: Have you seen a copy of CASE Exhibit 761A, which was attached to 5       the 4/26/83 Surrebuttal Testimony of Jack Doyle (CASE Exhibit 761)?
* {-Q g STATION UNITS #1 At4D #2
6             A:   Yes.
,g
7             Q: Can you identify that document for us?
.}
8             A:   Yes. This is a computer printout of a stress program similar to 9       STRUDL which I performed on May 25, 1983, at the request of Jack Doyle.
(CPSES) q,+-vy>;
10           Q: Have you seen a copy of CASE Exhibit 762A, which was attached to 11     the 4/28/82 Supplementary Surrebuttal Testimony of Jack Doyle (CASE Exhibit 12     762)?
,tco 9
13           A:   Yes.
SURREBUTTAL TESTIM 0 fly OF MARK ANTHONY WALSii, !7.,.a s #
14           Q:   Can you identify that document for us?
t 9.s WITNESS FOR INTERVEN0R CASE s
15           A: .Yes.     This is a computer printout of a similar stress program 16     which I performad on May 27, 1983, at the request of Jack Doyle.
1 Q: Mr. Walsh, are you the same Mark Anthony Walsh who testified in 2
8305110157 830504                                 r PDRADOCK05000jg
the July and September 1982 Operating license hearings for Comanche Peak?
3 A: ~Yes, I am.
4 Q: Have you seen a copy of CASE Exhibit 761A, which was attached to 5
the 4/26/83 Surrebuttal Testimony of Jack Doyle (CASE Exhibit 761)?
6 A:
Yes.
7 Q: Can you identify that document for us?
8 A:
Yes. This is a computer printout of a stress program similar to 9
STRUDL which I performed on May 25, 1983, at the request of Jack Doyle.
10 Q: Have you seen a copy of CASE Exhibit 762A, which was attached to 11 the 4/28/82 Supplementary Surrebuttal Testimony of Jack Doyle (CASE Exhibit 12 762)?
13 A:
Yes.
14 Q:
Can you identify that document for us?
15 A:.Yes.
This is a computer printout of a similar stress program 16 which I performad on May 27, 1983, at the request of Jack Doyle.
8305110157 830504 r
PDRADOCK05000jg


v 1                   Q: And can you tell us what the difference is between CASE Exhibit 2             761A and CASE Exhibit 762A?
v.
3                   A:   Yes. I changed the stiffness of walls A and B by changing the 4             member properties AX, by changing Young's modulus which is designated 5             as " CONSTANTS E 27650," and I also changed the member temperature coefficient
1 Q: And can you tell us what the difference is between CASE Exhibit 2
  !6                 from .000007 to .000006623 and the differential temperature from 210 F to t7                2200F. The changes were made because in the original run I was quite con-8             fident in the value of Young's modulus and therefore the stiffness to corre-9             spond to the stiffness the Applicants used, I had to change the axial 4
761A and CASE Exhibit 762A?
10             properties of members 1 and 3.         Also, I changed the CTE (Coefficient.of 11             Thermal Expansion) value and the temperature differential value to corre-12             spond to what the Applicants had used.
3 A:
13                   Q: And were these changes also made at the request of Jack Doyle?
Yes.
  ,  14                   A:   Yes.
I changed the stiffness of walls A and B by changing the 4
, 15                       Q:   Are you familiar with CASE Exhibits 705, 707, 744, 745, 747, 748, l 16 and 752 (these are all portions of the ASME Code)?
member properties AX, by changing Young's modulus which is designated 5
i 17                   A:   Yes.
as " CONSTANTS E 27650," and I also changed the member temperature coefficient
j 18                       Q: And were these part of the ASME Code which was being used at jg             Comanche Peak during your employment there?
!6 from.000007 to.000006623 and the differential temperature from 210 F to 0
20                   A:   Yes, they were.       CASE Exhibit 714, which is attached,is a copy 21               of a letter which was distributed at Comanche Peak regarding which portions i
t 7 220 F.
of the ASME Boiler and Pressure Vessel Code we were to use.
The changes were made because in the original run I was quite con-8 fident in the value of Young's modulus and therefore the stiffness to corre-9 spond to the stiffness the Applicants used, I had to change the axial 4
22 23                     Q:   Have you seen a copy of CASE Exhibit 743, Regulatory Guide 1.124?
10 properties of members 1 and 3.
                                                                                                                ~
Also, I changed the CTE (Coefficient.of 11 Thermal Expansion) value and the temperature differential value to corre-12 spond to what the Applicants had used.
24                     A:   Yes, I have.
13 Q: And were these changes also made at the request of Jack Doyle?
25                     Q:   Is it applicable to Comanche Peak?
14 A:
                                                .,,m
Yes.
, 15 Q:
Are you familiar with CASE Exhibits 705, 707, 744, 745, 747, 748, l 16 and 752 (these are all portions of the ASME Code)?
i 17 A:
Yes.
j 18 Q: And were these part of the ASME Code which was being used at jg Comanche Peak during your employment there?
20 A:
Yes, they were.
CASE Exhibit 714, which is attached,is a copy 21 of a letter which was distributed at Comanche Peak regarding which portions i
22 of the ASME Boiler and Pressure Vessel Code we were to use.
23 Q:
Have you seen a copy of CASE Exhibit 743, Regulatory Guide 1.124?
24 A:
Yes, I have.
~
25 Q:
Is it applicable to Comanche Peak?
.,,m 1
A:
It certainly appears to me that it would be applicable to Comanche 2
Peak.
3 Q: Have you.seen a copy of CASE Exhibit 750?
4 A:
Yes, l'have.
5 Q: Can you identify that document for us?
6 A:
Yes.
It is excerpts from the book THE TESTING AND INSPECTION OF 7
ENGINEERING MATERIALS, which is part of the McGraw-Hill Civil Engineering 8
Series.
9 Q:
Is it a generally recognized and accepted book?
10 A:
I would say so.
11 Q:
Have you seen a copy of CASE Exhibit 753?
12 A:
Yes, I have.
It is excerpts from the book the MANUAL OF STEEL 13 CONSTRUCTION, Seventh Edition, First Revised Printing, American Institute 14 of Steel Construction, Inc. (AISC).
15 Q:
Is it a generally recognized and accepted book?
16 A:
Yes.
17 Q:
Have you seen a copy of CASE Exhibit 755?
, 18 A:
Yes, I have.
It is the ACI Standard, Code Requirements for Nuclear 19 Safety Related Concrete Structures ( ACI 349-76), pages 349-24 and 349-25.
~
' 20 Q:
Is it a generally recognized and accepted document?
21 A:
I would say so.
22 Q: Have you seen a copy of CASE Exhibits 756 and 716?
l A:
Yes.
They are both excerpts from the PSE Manual or Guidelines 23 24 in use at Comanche Peak.
25 Q: Have you seen a copy of CASE Exhibit 759?


1       A:   It certainly appears to me that it would be applicable to Comanche 2   Peak.
e ;
3         Q: Have you.seen a copy of CASE Exhibit 750?
1 A:
4         A:  Yes, l'have.
Yes.
5        Q: Can you identify that document for us?
It is a page from ASME Section III, Division 1 -- Subsection 2
6        A:  Yes. It is excerpts from the book THE TESTING AND INSPECTION OF 7  ENGINEERING MATERIALS, which is part of the McGraw-Hill Civil Engineering 8  Series.
NA, Table I-13.1.
9         Q:  Is it a generally recognized and accepted book?
I discovered when. I was reviewing this Table that there 0
10        A:  I would say so.
3 is an apparent error shown for SA-36 Carbon Steel at 3000 and 400 F.
11        Q:   Have you seen a copy of CASE Exhibit 753?
I asked 4
12        A:   Yes, I have.     It is excerpts from the book the MANUAL OF STEEL
Mrs. Ellis to check with ASME by phone to confirm that this was indeed an 5
  ,   13  CONSTRUCTION, Seventh Edition, First Revised Printing, American Institute 14 of Steel Construction, Inc. (AISC).
error and that the correct values for SA-36 steel are those contained in 6
15        Q:   Is it a generally recognized and accepted book?
the 1980 Edition (which is CASE Exhibit 760):
16        A:   Yes.
31.9 at 300 F and 30.8 at 0
17        Q:   Have you seen a copy of CASE Exhibit 755?
7 400 F.
, 18            A:   Yes, I have.     It is the ACI Standard, Code Requirements for Nuclear
It is my understanding that these are indeed the correct values.
                                                    ~
8 Q: Have you seen a copy of CASE Exhibits 758, 761B, 763B, 763C-1 9
19   Safety Related Concrete Structures ( ACI 349-76), pages 349-24 and 349-25.
through 763C-5, 763D-1 through 763D-4, 763D-6 through 763D-9, and 763H?
' 20            Q:  Is it a generally recognized and accepted document?
10 A:
21         A:  I would say so.
Yes. These are all documents obtained from the Applicants as 11 part of discovery by CASE in reference to the SIT Report (Investigation 12 Report 50-445/82-26,50-446/82-14).
22          Q: Have you seen a copy of CASE Exhibits 756 and 716?
13 Q: Have you seen a copy of CASE Exhibit 763E?
l 23          A:   Yes. They are both excerpts from the PSE Manual or Guidelines 24   in use at Comanche Peak.
14 A: Yes. This is a copy of pages ph-20 and ph-21 from the ITT Grinnell 15 Catalog PH79, Pipe Hangers.
25         Q: Have you seen a copy of CASE Exhibit 759?
16 Q:
Have you seen a copy of CASE Exhibit 763F?
l 17 A: Yes.
It is excerpts from the book STEEL STRUCTURES Design and
! 18 Behavior by Salmon and Johnson.
I believe there are already portions of 19 this book which have been accepted into the record.
I know that we have some port' ons from a book by Salmon and Johnson already in the record.
i 20 21 Q: Have you seen a copy of CASE Exhibit 763G?
22 A: Yes.
It is an excerpt from the book the MANUAL OF STEEL C0f4STRUCTION, 23.
Seventh Edi tion.
It is from the same AISC manual from which CASE Exhibit 24 753 was taken.
; 25 Q:
Have you seen a copy of CASE Exhibits 764 and 765?


e 1             A: Yes. It is a page from ASME Section III, Division 1 -- Subsection 2      NA, Table I-13.1.
1 A:
I discovered when. I was reviewing this Table that there 3      is an apparent error shown for SA-36 Carbon Steel at 3000 and 4000F.          I asked 4      Mrs. Ellis to check with ASME by phone to confirm that this was indeed an 5      error and that the correct values for SA-36 steel are those contained in 6      the 1980 Edition (which is CASE Exhibit 760):        31.9 at 300 F and 30.8 at 7      4000F. It is my understanding that these are indeed the correct values.
Yes. They are pages from ASME Section III -- Subsection NCA, i 2 NCA-3220--NCA-32'52 and NCA-ll30--flCA-120, respectively.
8            Q: Have you seen a copy of CASE Exhibits 758, 761B, 763B, 763C-1
3 Q:
,    9      through 763C-5, 763D-1 through 763D-4, 763D-6 through 763D-9, and 763H?
And in your opinion do all 'of the documents we've discussed in f
10            A:  Yes. These are all documents obtained from the Applicants as 11      part of discovery by CASE in reference to the SIT Report (Investigation 12      Report 50-445/82-26,50-446/82-14).
4 the preceding need to be in the record of these proceedings?
13            Q: Have you seen a copy of CASE Exhibit 763E?
5 A:
14            A: Yes. This is a copy of pages ph-20 and ph-21 from the ITT Grinnell 15      Catalog PH79, Pipe Hangers.
I believe so, so that the Board can make a decision that is based 6
16            Q:  Have you seen a copy of CASE Exhibit 763F?
on facts and not on opinions.
l 17              A: Yes. It is excerpts from the book STEEL STRUCTURES Design and
! 18        Behavior by Salmon and Johnson.        I believe there are already portions of 19      this book which have been accepted into the record.          I know that we have 20      some port'i ons from a book by Salmon and Johnson already in the record.
21            Q: Have you seen a copy of CASE Exhibit 763G?
22            A: Yes. It is an excerpt from the book the MANUAL OF STEEL C0f4STRUCTION,
: 23.      Seventh Edi tion. It is from the same AISC manual from which CASE Exhibit 24      753 was taken.                                                                        -
; 25              Q:  Have you seen a copy of CASE Exhibits 764 and 765?
 
1                      A:            Yes. They are pages from ASME Section III -- Subsection NCA, i2            NCA-3220--NCA-32'52 and NCA-ll30--flCA-120, respectively.
3                       Q:             And in your opinion do all 'of the documents we've discussed in f
4         the preceding need to be in the record of these proceedings?
5                       A:             I believe so, so that the Board can make a decision that is based 6         on facts and not on opinions.
7
7
!8                           Q:             Were you contacted by anyone with the NRC regarding your co'ncerns                                                                   ,
!8 Q:
i
Were you contacted by anyone with the NRC regarding your co'ncerns i; 9 after you testified in the July 1982 hearings and the time you testified l 10 in the September 1982 hearings?
;9             after you testified in the July 1982 hearings and the time you testified l 10           in the September 1982 hearings?
11 A: No.
11                     A: No.
12 Q: Were you contacted by anyone with the NRC regarding your concerns 13 after you testified in the September 1982 hearings?
12                       Q: Were you contacted by anyone with the NRC regarding your concerns 13       after you testified in the September 1982 hearings?
14 A:
14                     A:             No.
No.
4
4' 15 Q:
' 15                         Q:           So you were not contacted by anyone from the NRC Special Inspection
So you were not contacted by anyone from the NRC Special Inspection 16 Team regarding your concerns during the SIT's investigation of what have 17 come to be known as the Walsh/Doyle allegations?
;    16       Team regarding your concerns during the SIT's investigation of what have 17       come to be known as the Walsh/Doyle allegations?
l 18 A: No.
l 18                         A: No.
19 Q:
19                       Q:           In your testimony, did you at any time identify your concerns i 20           as they are expressed in the SIT Report (i.e., as identified by the SIT 21       as items a through s)?
In your testimony, did you at any time identify your concerns i 20 as they are expressed in the SIT Report (i.e., as identified by the SIT 21 as items a through s)?
l 22                         A:             No.
l 22 A:
23                       Q: So the manner in which your concerns are identified and grouped 24       was determined by the SIT, is that correct?
No.
; 25                         A: Yes.
23 Q: So the manner in which your concerns are identified and grouped 24 was determined by the SIT, is that correct?
; 25 A: Yes.
i I
i I
I m         ,,e. , - , , , , - - , ,         . - - . , - . , - , - - , - , , - - - - - - - -                ,.n,----   - - - , - . ~   a-,,   -      n---e,m-c-
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,,e., -,,,, - -,,
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- - -, -. ~
a-,,
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e o
e o 1
1          Q: Is there anything further you would like to say at this time 2     regarding the flRC's investigation of the Walsh/Doyle allegations?
Q:
3           A: Not at this time. My testimony here is primarily to identify 4     for the record certain documents which I am familiar with and to answer 5     the specific questions posed to me by CASE. The primary surrebuttal 6     testimony regarding the SIT Report will be done by Jack Doyle.
Is there anything further you would like to say at this time 2
regarding the flRC's investigation of the Walsh/Doyle allegations?
3 A: Not at this time. My testimony here is primarily to identify 4
for the record certain documents which I am familiar with and to answer 5
the specific questions posed to me by CASE.
The primary surrebuttal 6
testimony regarding the SIT Report will be done by Jack Doyle.
7 8
7 8
9 10 11 12 13 14
9 10 11 12 13 14
                      /
/
15 16 17 18
15 16 17 18 19 l20 I 21 22 i; 23 i
;  19 l20 I 21 22 i
; 23 i                                                                                 -
l 24.
l 24.
4 l25 1
4 l25 1
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UtilTED STATES OF AMERICA flVCLEAR REGULATORY COMMISSIO!1 BEFORE THE ATOMIC SAFETY AllD LICEf1SlfiG BOARD In the Matter of                                                             l I
UtilTED STATES OF AMERICA flVCLEAR REGULATORY COMMISSIO!1 BEFORE THE ATOMIC SAFETY AllD LICEf1SlfiG BOARD In the Matter of l
APPLICATI0ft 0F TEXAS UTILITIES                                             Q GEllERATIfiG COMPAtlY, ET AL. FOR                                           Q                                           Docket flos. 50-445                       -
I APPLICATI0ft 0F TEXAS UTILITIES Q
Af1 OPERATIf1G LICENSE FOR                                                   Q                                                   and 50-446 COMAfiCHE PEAK STEAM ELECTRIC                                               Q STATION UNITS #1 AND #2 (CPSES)                                             i CERTIFICATE OF SERVICE By my signature belov/, I hereby certify that true and correct copies of Surrebuttal Testimony of Mark Anthony Walsh, Witness for Intervenor CASE (CASE Exhibit 766) l           have been sent to the names listed below this                                               4th day of                           May           , 19 8,3_,
GEllERATIfiG COMPAtlY, ET AL. FOR Q
Docket flos. 50-445 Af1 OPERATIf1G LICENSE FOR Q
and 50-446 COMAfiCHE PEAK STEAM ELECTRIC Q
STATION UNITS #1 AND #2 (CPSES) i CERTIFICATE OF SERVICE By my signature belov/, I hereby certify that true and correct copies of Surrebuttal Testimony of Mark Anthony Walsh, Witness for Intervenor CASE (CASE Exhibit 766) l have been sent to the names listed below this 4th day of May
, 19 8,3_,
by: Express Mail where indicated by
by: Express Mail where indicated by
* and First Class Mail elsewhere.
* and First Class Mail elsewhere.
O Administrative Judge Peter B. Bloch                                                   Alan S. Rosenthal, Esq. , Chairman U. S. fluclear Regulatory Comission                                                   Atomic Safety and Licensing Appeal Board 4350 East / West Highway, 4th Floor                                                   U. S. fluclear Regulatory Commission Bethesda, Maryland                           20014                                     Washington, D. C.                         20555 0 Dr. Kenneth A. -McCollom, Dean Dr. W. Reed Johnson, Member Division of Engineering,                                                               Atomic Safety and Licensing Appeal Board Architecture and Technology                                                       U. S. fluclear Regulatory Commission Oklahoma State University                                                             Washington, D. C.                         20555 Stillwater, Oklahoma 74074 Thomas S. Moore, Esq., Member                                                 '
O Administrative Judge Peter B. Bloch Alan S. Rosenthal, Esq., Chairman U. S. fluclear Regulatory Comission Atomic Safety and Licensing Appeal Board 4350 East / West Highway, 4th Floor U. S. fluclear Regulatory Commission Bethesda, Maryland 20014 Washington, D. C.
i O Dr. Walter H. Jordan                                                                   Atomic Safety and Licensing Appeal Board 881 W. Outer Drive                                                                     U. S. .fluclear Regulatory Comission Oak Ridge, Tennessee                           37830                                   Washington, D. C.                           20555 I
20555 0 Dr. Kenneth A. -McCollom, Dean Dr. W. Reed Johnson, Member Division of Engineering, Atomic Safety and Licensing Appeal Board Architecture and Technology U. S. fluclear Regulatory Commission Oklahoma State University Washington, D. C.
flichol as S. Reynolds , Esq.                                                         Atomic Safety and Licensing Appeal Panel Debevoise & Liberman                                                                   U. S. fluclear Regulatory Commission 1200 - 17th St., N. W.                                                                 Washington, D. C.                         20555 Washington, D. C.                           20036 Docketing and Service Section 0
20555 Stillwater, Oklahoma 74074 Thomas S. Moore, Esq., Member O Dr. Walter H. Jordan Atomic Safety and Licensing Appeal Board i
Marjorie Ulman Rothschild, Esq.                                                       Office of the Secretary Office of Executive Legal Director , USNRC                                             U. S. Nuclear Regulatory Comission
881 W. Outer Drive U. S..fluclear Regulatory Comission Oak Ridge, Tennessee 37830 Washington, D. C.
,            Maryland flational Bank Building                                                       Washington, D. C.                           20555 1             7735 Old Georgetown Road - Room 10105 l             Bethesda, Maryland                           20814
20555 I
* Ms. Lucinda Minton, Law Clerk Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board                                                     4350 East /Wes t Highway, 4th Floor Panel                                                               Bethesda, Maryland                         20014 U. S. Nuclear Regulatory Commission Washington, D. C.                           20555
flichol as S. Reynolds, Esq.
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Washington, D. C.
20555 Washington, D. C.
20036 Docketing and Service Section 0 Marjorie Ulman Rothschild, Esq.
Office of the Secretary Office of Executive Legal Director, USNRC U. S. Nuclear Regulatory Comission Maryland flational Bank Building Washington, D. C.
20555 1
7735 Old Georgetown Road - Room 10105 l
Bethesda, Maryland 20814
* Ms. Lucinda Minton, Law Clerk Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board 4350 East /Wes t Highway, 4th Floor Panel Bethesda, Maryland 20014 U. S. Nuclear Regulatory Commission Washington, D. C.
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4 Certificate of Service Page 2 David J. Preister, Esq.
Assistant Attorney General Environmental Protection Division Supreme Court Building Austin, Texas                                   78711 John Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Dr., Suite 1000 Arlington, Texas                                 76011 Mr. R. J. Gary Executive Vice President and General Manager Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas                                 75201 Lanny Alan Sinkin 838 East Magnolia Avenue San Antonio, Texas                                   78212 I
Assistant Attorney General Environmental Protection Division Supreme Court Building Austin, Texas 78711 John Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Dr., Suite 1000 Arlington, Texas 76011 Mr. R. J. Gary Executive Vice President and General Manager Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Lanny Alan Sinkin 838 East Magnolia Avenue San Antonio, Texas 78212 I
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rs.) Juanita Ellis, President CASE (Citizens Association for Sound Energy) 1426 S. Polk l
                                                                                                                                        - JK'i           f]A w rs.) Juanita Ellis, President CASE (Citizens Association for Sound Energy)
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CASE EXHIBIT 714 CPPA-7970 o ;--- e I :.: E.! O R <'s :
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ASME CODE DisTRuiuT10N At: ached for your use are ;; pies a? :ne ::1:w listec portions of :he AillE Boiler and Fressure Yessei Code for your use in pipe support design and installation activities.
ASME CODE DisTRuiuT10N At: ached for your use are ;; pies a? :ne ::1:w listec portions of :he AillE Boiler and Fressure Yessei Code for your use in pipe support design and installation activities.
_        SECTION III - DIVISI0ft I Nuclear Power Plant Comconents - 1974 Edition ._
Nuclear Power Plant Comconents - 1974 Edition._
')                         1)         Subsection NF - Component Supports, including W'74 Addenda                           .
SECTION III - DIVISI0ft I
: 2)         Subsection ::A - Generai Re:;u:. aments, ir.cluding W'74 Addenda
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: 3)         Subsection NA - Appendices including W'74 Addenda
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Subsection ::A - Generai Re:;u:. aments, ir.cluding W'74 Addenda 3)
Subsection NA - Appendices including W'74 Addenda 4)
Also included as a separate section are those pages of the Appendices that changed between the issuance of tne 1974 Edition and the W'74 Addenda Themandatorieditiongoverningpipe support design and fabrication is the 1974 Editiert.;itn Addenda issueo :nrougn ano including W'74.
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'ethen addrettirg w3Med It c.M2rt: t: Oi;;ing in2 stres; values thru S'74 are candatory. henca ;he. aason for a ttac.iing ite.n 4 above.
If there are any cuestions, plea;e de ot hesitate to contact the under-signed.
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Latest revision as of 22:54, 14 December 2024

Surrebuttal Testimony of Ma Walsh.Certificate of Svc Encl. Related Correspondence
ML20079P851
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 05/04/1983
From: Mary Walsh
Citizens Association for Sound Energy
To:
References
NUDOCS 8305110157
Download: ML20079P851 (9)
v • d • e


Text

-

CASE EXHIBIT 766 UillTED STATES OF AMERICA p eonn # '*

T4UCLEAR REGULATORY COMMISS10rt 5/4/83 BEFORE THE ATOMIC SAFETY AllD LICEllSING C0ARD in the Matter of g g cp APPLICAT10tl 0F TEXAS UTILITIES I

Do c ke t'M 50-G E riE R AT ! t(G C OMP A t1Y, ET AL. FOR

./,apdSg44 A!1 OPERATING LICEtJSE FOR

/

j

,i't COMAtJCHE PEAK STEAM ELECTRIC g

vge,

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q,.

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  • {-Q g STATION UNITS #1 At4D #2

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(CPSES) q,+-vy>;

,tco 9

SURREBUTTAL TESTIM 0 fly OF MARK ANTHONY WALSii, !7.,.a s #

t 9.s WITNESS FOR INTERVEN0R CASE s

1 Q: Mr. Walsh, are you the same Mark Anthony Walsh who testified in 2

the July and September 1982 Operating license hearings for Comanche Peak?

3 A: ~Yes, I am.

4 Q: Have you seen a copy of CASE Exhibit 761A, which was attached to 5

the 4/26/83 Surrebuttal Testimony of Jack Doyle (CASE Exhibit 761)?

6 A:

Yes.

7 Q: Can you identify that document for us?

8 A:

Yes. This is a computer printout of a stress program similar to 9

STRUDL which I performed on May 25, 1983, at the request of Jack Doyle.

10 Q: Have you seen a copy of CASE Exhibit 762A, which was attached to 11 the 4/28/82 Supplementary Surrebuttal Testimony of Jack Doyle (CASE Exhibit 12 762)?

13 A:

Yes.

14 Q:

Can you identify that document for us?

15 A:.Yes.

This is a computer printout of a similar stress program 16 which I performad on May 27, 1983, at the request of Jack Doyle.

8305110157 830504 r

PDRADOCK05000jg

v.

1 Q: And can you tell us what the difference is between CASE Exhibit 2

761A and CASE Exhibit 762A?

3 A:

Yes.

I changed the stiffness of walls A and B by changing the 4

member properties AX, by changing Young's modulus which is designated 5

as " CONSTANTS E 27650," and I also changed the member temperature coefficient

!6 from.000007 to.000006623 and the differential temperature from 210 F to 0

t 7 220 F.

The changes were made because in the original run I was quite con-8 fident in the value of Young's modulus and therefore the stiffness to corre-9 spond to the stiffness the Applicants used, I had to change the axial 4

10 properties of members 1 and 3.

Also, I changed the CTE (Coefficient.of 11 Thermal Expansion) value and the temperature differential value to corre-12 spond to what the Applicants had used.

13 Q: And were these changes also made at the request of Jack Doyle?

14 A:

Yes.

, 15 Q:

Are you familiar with CASE Exhibits 705, 707, 744, 745, 747, 748, l 16 and 752 (these are all portions of the ASME Code)?

i 17 A:

Yes.

j 18 Q: And were these part of the ASME Code which was being used at jg Comanche Peak during your employment there?

20 A:

Yes, they were.

CASE Exhibit 714, which is attached,is a copy 21 of a letter which was distributed at Comanche Peak regarding which portions i

22 of the ASME Boiler and Pressure Vessel Code we were to use.

23 Q:

Have you seen a copy of CASE Exhibit 743, Regulatory Guide 1.124?

24 A:

Yes, I have.

~

25 Q:

Is it applicable to Comanche Peak?

.,,m 1

A:

It certainly appears to me that it would be applicable to Comanche 2

Peak.

3 Q: Have you.seen a copy of CASE Exhibit 750?

4 A:

Yes, l'have.

5 Q: Can you identify that document for us?

6 A:

Yes.

It is excerpts from the book THE TESTING AND INSPECTION OF 7

ENGINEERING MATERIALS, which is part of the McGraw-Hill Civil Engineering 8

Series.

9 Q:

Is it a generally recognized and accepted book?

10 A:

I would say so.

11 Q:

Have you seen a copy of CASE Exhibit 753?

12 A:

Yes, I have.

It is excerpts from the book the MANUAL OF STEEL 13 CONSTRUCTION, Seventh Edition, First Revised Printing, American Institute 14 of Steel Construction, Inc. (AISC).

15 Q:

Is it a generally recognized and accepted book?

16 A:

Yes.

17 Q:

Have you seen a copy of CASE Exhibit 755?

, 18 A:

Yes, I have.

It is the ACI Standard, Code Requirements for Nuclear 19 Safety Related Concrete Structures ( ACI 349-76), pages 349-24 and 349-25.

~

' 20 Q:

Is it a generally recognized and accepted document?

21 A:

I would say so.

22 Q: Have you seen a copy of CASE Exhibits 756 and 716?

l A:

Yes.

They are both excerpts from the PSE Manual or Guidelines 23 24 in use at Comanche Peak.

25 Q: Have you seen a copy of CASE Exhibit 759?

e ;

1 A:

Yes.

It is a page from ASME Section III, Division 1 -- Subsection 2

NA, Table I-13.1.

I discovered when. I was reviewing this Table that there 0

3 is an apparent error shown for SA-36 Carbon Steel at 3000 and 400 F.

I asked 4

Mrs. Ellis to check with ASME by phone to confirm that this was indeed an 5

error and that the correct values for SA-36 steel are those contained in 6

the 1980 Edition (which is CASE Exhibit 760):

31.9 at 300 F and 30.8 at 0

7 400 F.

It is my understanding that these are indeed the correct values.

8 Q: Have you seen a copy of CASE Exhibits 758, 761B, 763B, 763C-1 9

through 763C-5, 763D-1 through 763D-4, 763D-6 through 763D-9, and 763H?

10 A:

Yes. These are all documents obtained from the Applicants as 11 part of discovery by CASE in reference to the SIT Report (Investigation 12 Report 50-445/82-26,50-446/82-14).

13 Q: Have you seen a copy of CASE Exhibit 763E?

14 A: Yes. This is a copy of pages ph-20 and ph-21 from the ITT Grinnell 15 Catalog PH79, Pipe Hangers.

16 Q:

Have you seen a copy of CASE Exhibit 763F?

l 17 A: Yes.

It is excerpts from the book STEEL STRUCTURES Design and

! 18 Behavior by Salmon and Johnson.

I believe there are already portions of 19 this book which have been accepted into the record.

I know that we have some port' ons from a book by Salmon and Johnson already in the record.

i 20 21 Q: Have you seen a copy of CASE Exhibit 763G?

22 A: Yes.

It is an excerpt from the book the MANUAL OF STEEL C0f4STRUCTION, 23.

Seventh Edi tion.

It is from the same AISC manual from which CASE Exhibit 24 753 was taken.

25 Q

Have you seen a copy of CASE Exhibits 764 and 765?

1 A:

Yes. They are pages from ASME Section III -- Subsection NCA, i 2 NCA-3220--NCA-32'52 and NCA-ll30--flCA-120, respectively.

3 Q:

And in your opinion do all 'of the documents we've discussed in f

4 the preceding need to be in the record of these proceedings?

5 A:

I believe so, so that the Board can make a decision that is based 6

on facts and not on opinions.

7

!8 Q:

Were you contacted by anyone with the NRC regarding your co'ncerns i; 9 after you testified in the July 1982 hearings and the time you testified l 10 in the September 1982 hearings?

11 A: No.

12 Q: Were you contacted by anyone with the NRC regarding your concerns 13 after you testified in the September 1982 hearings?

14 A:

No.

4' 15 Q:

So you were not contacted by anyone from the NRC Special Inspection 16 Team regarding your concerns during the SIT's investigation of what have 17 come to be known as the Walsh/Doyle allegations?

l 18 A: No.

19 Q:

In your testimony, did you at any time identify your concerns i 20 as they are expressed in the SIT Report (i.e., as identified by the SIT 21 as items a through s)?

l 22 A:

No.

23 Q: So the manner in which your concerns are identified and grouped 24 was determined by the SIT, is that correct?

25 A
Yes.

i I

I m

,,e., -,,,, - -,,

,.n,----

- - -, -. ~

a-,,

n---e,m-c-

e o 1

Q:

Is there anything further you would like to say at this time 2

regarding the flRC's investigation of the Walsh/Doyle allegations?

3 A: Not at this time. My testimony here is primarily to identify 4

for the record certain documents which I am familiar with and to answer 5

the specific questions posed to me by CASE.

The primary surrebuttal 6

testimony regarding the SIT Report will be done by Jack Doyle.

7 8

9 10 11 12 13 14

/

15 16 17 18 19 l20 I 21 22 i; 23 i

l 24.

4 l25 1

e

UtilTED STATES OF AMERICA flVCLEAR REGULATORY COMMISSIO!1 BEFORE THE ATOMIC SAFETY AllD LICEf1SlfiG BOARD In the Matter of l

I APPLICATI0ft 0F TEXAS UTILITIES Q

GEllERATIfiG COMPAtlY, ET AL. FOR Q

Docket flos. 50-445 Af1 OPERATIf1G LICENSE FOR Q

and 50-446 COMAfiCHE PEAK STEAM ELECTRIC Q

STATION UNITS #1 AND #2 (CPSES) i CERTIFICATE OF SERVICE By my signature belov/, I hereby certify that true and correct copies of Surrebuttal Testimony of Mark Anthony Walsh, Witness for Intervenor CASE (CASE Exhibit 766) l have been sent to the names listed below this 4th day of May

, 19 8,3_,

by: Express Mail where indicated by

  • and First Class Mail elsewhere.

O Administrative Judge Peter B. Bloch Alan S. Rosenthal, Esq., Chairman U. S. fluclear Regulatory Comission Atomic Safety and Licensing Appeal Board 4350 East / West Highway, 4th Floor U. S. fluclear Regulatory Commission Bethesda, Maryland 20014 Washington, D. C.

20555 0 Dr. Kenneth A. -McCollom, Dean Dr. W. Reed Johnson, Member Division of Engineering, Atomic Safety and Licensing Appeal Board Architecture and Technology U. S. fluclear Regulatory Commission Oklahoma State University Washington, D. C.

20555 Stillwater, Oklahoma 74074 Thomas S. Moore, Esq., Member O Dr. Walter H. Jordan Atomic Safety and Licensing Appeal Board i

881 W. Outer Drive U. S..fluclear Regulatory Comission Oak Ridge, Tennessee 37830 Washington, D. C.

20555 I

flichol as S. Reynolds, Esq.

Atomic Safety and Licensing Appeal Panel Debevoise & Liberman U. S. fluclear Regulatory Commission 1200 - 17th St., N. W.

Washington, D. C.

20555 Washington, D. C.

20036 Docketing and Service Section 0 Marjorie Ulman Rothschild, Esq.

Office of the Secretary Office of Executive Legal Director, USNRC U. S. Nuclear Regulatory Comission Maryland flational Bank Building Washington, D. C.

20555 1

7735 Old Georgetown Road - Room 10105 l

Bethesda, Maryland 20814

  • Ms. Lucinda Minton, Law Clerk Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board 4350 East /Wes t Highway, 4th Floor Panel Bethesda, Maryland 20014 U. S. Nuclear Regulatory Commission Washington, D. C.

20555

,--n

,--e.w--n 4, + - - -,

-~

4 Certificate of Service Page 2 David J. Preister, Esq.

Assistant Attorney General Environmental Protection Division Supreme Court Building Austin, Texas 78711 John Collins Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Dr., Suite 1000 Arlington, Texas 76011 Mr. R. J. Gary Executive Vice President and General Manager Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Lanny Alan Sinkin 838 East Magnolia Avenue San Antonio, Texas 78212 I

?- JK'i f]A w i

rs.) Juanita Ellis, President CASE (Citizens Association for Sound Energy) 1426 S. Polk l

Dallas, Texas 75224 214/946-9446 e

')

/

TEXAS UTILITIES SERVICES INC.

CASE EXHIBIT 714 CPPA-7970 o ;--- e I :.: E.! O R <'s :

'J M To Distribution cien !we. TeusRecember ?2.1990 Sut et C"A*1CHE PEl" STE'lt EL ECT'3 'C STAT ~ ^ :

ASME CODE DisTRuiuT10N At: ached for your use are ;; pies a? :ne ::1:w listec portions of :he AillE Boiler and Fressure Yessei Code for your use in pipe support design and installation activities.

Nuclear Power Plant Comconents - 1974 Edition._

SECTION III - DIVISI0ft I

')

1)

Subsection NF - Component Supports, including W'74 Addenda 2)

Subsection ::A - Generai Re:;u:. aments, ir.cluding W'74 Addenda 3)

Subsection NA - Appendices including W'74 Addenda 4)

Also included as a separate section are those pages of the Appendices that changed between the issuance of tne 1974 Edition and the W'74 Addenda Themandatorieditiongoverningpipe support design and fabrication is the 1974 Editiert.;itn Addenda issueo :nrougn ano including W'74.

The mandatory

.-- 4di tian fr.r other C."SES con.nonenta maj va,, f ra di.e a bo e, a s for instance pi? ' ig wh ;c n i s ;ne d14 de. ;.ca ui.i..u.c _... -...;u ;J 03f0Jgn anC InC!uCing S'74.

'ethen addrettirg w3Med It c.M2rt: t: Oi;;ing in2 stres; values thru S'74 are candatory. henca ;he. aason for a ttac.iing ite.n 4 above.

If there are any cuestions, plea;e de ot hesitate to contact the under-signed.

s i-V.

R. T. Wolantejus i

RTW:ajs

\\

Distribution:

ARMS OL (witnout attachment)

"I L. Montanaro 4L, 4A J. C. Finneran IL,1A D. H. Wade IL, 1A J. J. Ryan IL, 1A 1

R. O. Stone IL,1A

. cc:

M. R. McBay ll, OA

" ' Q, 1 E. B. Cox IL, CA g..

f

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