ML20079M976
| ML20079M976 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/28/1983 |
| From: | Gallo J COMMONWEALTH EDISON CO., ISHAM, LINCOLN & BEALE |
| To: | Callihan A, Cole R, Smith I Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8303030381 | |
| Download: ML20079M976 (25) | |
Text
or s.
a
.y-ISHAM, LINCOLN & BEALE 0 KQED COUNSELORS AT law d l
- t, 1t20 CONNECTICUT AVENUE. N.W
- SUITE 840 WASHINGTON.D C.20036
'h h'~2 UO EDvuRD S. ISHAM. 1872-1902 202 833 9730 CAGO OmCE ROBERTT.UNCOLN. 1872 1889 THREE FIRST NATIONAL PLAZA WILLIAM G. BEALE. 1885-1923 CHICAGO. lLUNOIS 60002 TELEDHONE 312 558 7500 T ELEX: 2-5288 February 28, 1983 Ivan W.
Smith Dr. Richard F. Cole Administrative Judge and Administrative Judge Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Board U.
S. Nuclear Regulatory U.
S. Nuclear Regulatory Commission Commission Washington, D.C.
20555 Washington, D.C.
20555 Dr.
A.
Dixon Callihan Administrative Judge Atomic Safety and Licensing Board c/o Union Carbide Corporation P.
O.
Box Y Oak Ridge, Tennessee 37830 RE:
In the Matter of Commonwealth Edison Company (Byron Nuclear Power Station, Units 1 and 2)
Docket Nos. 50-454 and 50-455 Gentlemen:
the McGuire 9ccordance with the disclosure requirements of In, case, I am enclosing a letter and enclosures dated February 9, 1983 from Mr. T. R. Tramm of Commonwealth Edison Company to Mr. Harold Denton.
Mr. Tramm's letter sets forth a commitment on behalf of Commonwealth Edison Company to limit power operation to 70% or lower in the event that the steam generators installed in the Byron Station are not modified to minimize the effect of flow-induced vibration j
prior to start-up.
- /
Duke Power Company (William B.
McGuire Nuclear Station, j
Units 1 and 2), ALAB-143, 6 AEC, 623, 625 (1973).
8303030381 830228 PDR ADOCK 05000454 G
PDR i,
i C
V I
t J
WJ
. Mr. Tramm's letter and its enclosures are relevant
.to Rockford League of Women Voters' Contention 22 and DAARE/ SAFE Contention 9c.
Sincerely, 0
k/
/-
fT6seph Gallo One of the Attorneys for Commonwealth Edison Company Enclosures cc:
Service List
Commonwrith Edison
~) Ons First National Plata. Chicago. Ilknois C
C Addr:ss R; ply to: Post Othee Box 767 Chicago. Ilknois 60690 February 9, 1983 0
~ \\
DocWaf 9
Mr. Harold R. Denton, Director q
ENE Office of Nuclear Reactor Regulation 3
U.S. Nuclear Regulatory Commission JR MARO 219&3>
$0 Washington, DC 20555 3
A c'nc e%
~ eg;p w.
O
' i4 A gy}
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2
~
Steam Generator Tube Vibration NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457 References (a):
January 20, 1982 letter from D. G. Eisenhut to L. O. DelGeorge.
(b):
March 15, 1982 letter from T. R. Tramm to H. R. Denton.
(c):
Summary of February 19, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
(d):
July 27, 1982 letter from B. J. Youngblood to L. O. DelGeorge.
(e):
October 28, 1982 summary of October 22, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
Dear Mr. Denton:
This letter will document our intentions with regard to modification of the Byron /Braidwood steam generators to minimize tube dcgradation associated with flow induced vibration.
This supplements Commonwealth Edison's response to the NRC's request for informatirn in reference (a).
We presently intend to modify to the extent necessary the Byron /Braidwood steam generators pr..u. to loading fuel at each unit.
If e satisfactory modification cannot be engineered, tested, reviewed, approved and installed prior to fuel load on any of these units, we will do the modification work at the first opportunity and restrict power durinc the interim operation period.
Westinghouse's testing program has demonstrated that steam generators of this type can be operated indefinitely at 70% power.
This information has been reviewed with the NRC in meetings documented in references (c), (d), and (e).
Comr.onwealth Edison will use this
F H. R. Denton February 9, 1983 information as the basis for establishing a specific power restriction during interim operation of the Byron /Braidwood units.
We do not intend to operate any unmodified steam generators at power levels exceeding those judged acceptable at Westinghouse.
It is requested that the NRC approve this interim power rostriction option so that plant startup may proceed in the event that steam generator modifications cannot be completed prior to fuel load.
We would be happy to discuss this matter further at your convenience.
Please contact this office.
Very truly yours, T (2. %
T. R.
Tramm Nuclear Licensing Administrator im 5964N
t l
8/B February 9, 1983 Messrs:
C. Reed /N. A. Kershaw V.
I. Schlosser/C. J.
Tomashek J. S. Abel D. J. Scott (NC Only)
H.
E. Bliss W.
J. Shewski' T. C. Cihlar/G. E. Peterson T. R. Sommerfield R. Cosaro G. Sorensen L. O. DelGeorge W.
L.
Stiede J. D. Deress/J. T. Westermeier H.
K.
Stolt/W. L. Eck E. E. Fitzpatrick (Bull., Circ., & I. Not. Only)
K. L. Graesser (NC Only)
R.
J. Tamminga (ISI Only)
J. F.
Gudac G.
P. Wagner J. H.
Hughes M.
J. Wallace R.
E.
Jortberg J. Gayley - IL&B N.
J. Kalivianakis (NC Only)
P. P. Steptoe-IL&B (Letters Only)
A.
W.
Kleinrath M.
A. Bowidowicz - S&L D. E. Lindvall W.
E.
Kortier - W J. J. Maley G. Wright - State of Illinois M.
A.
Stanish (NRC/ CECO Ltrs only)
R.
E. Querio W. R. Bird - Consumers Power Co.
Q.
A.
Engineer - Braidwood
- RIII Only Q.
A.
Engineer - Byron NL Distribution Q.
A.
Engineer - SNED In.the judgement of the Nuclear Licensing Administrator, the attachec document contains the following commitments to the NRC or requirements from the NRC.
Identification of Attached Document:
February 9, 1983 letter from T. R.
Tramm to H. R. Denton regarding Byron /Braidwood steam generator tube vibration.
NRC Commitment or Reouirement:
Responsible Due Date Commitment or Reauirement Edison Deoartment For your information Distribution When it is determined by the responsible department that a due date will not be met, the Nuclear Licensing Administrator should be notified immediately.
FILE:
T.
R.
Tramm 83-41 1m
C:mm:nwrith Edison one First National Plaza Chicago. tilinois Address Reply to: Post Office Box 767
~
Chicago. Illinois 60690 February 9, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Steam Generator Tube Vibration NRC Docket Nos. 50-454, 50-455, 50-456, and 50-457 References (a):
January 20, 1982 letter from D. G. Eisenhut to L. O. DelGeorge.
(b):
March 15, 1982 letter from T. R.
Tramm to H. R. Denton.
(c):
Summary of February 19, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
(d):
July 27, 1982 letter from B. J. Youngblood to L. O. DelGeorge.
(e):
October 28, 1982 summary of October 22, 1982 NRC meeting with Westinghouse regarding Model D steam generators.
Dear Mr. Denton:
This letter will document our intentions with regard to modification of the Byron /Braidwood steam generators to minimize tube degradation associated with flow induced vibration.
This supplements Commonwealth Edison's response to the NRC's request for information in reference (a).
We presently intend to modify to the extent necessary the Byron /Braidwood steam generators prior to loading fuel at each unit.
If a satisfactory modification cannot be engineered, tested, reviewed, approved and installed prior to fuel load on any of these units, we will do the modification work at the first opportunit/ and restrict power during the interim operation period.
Westinghouse's testing program has demonstrated that steam generators of this type can be operated indefinitely at 70% power.
This information has been reviewed with the NRC in meetings documented in references (c), (d), and (e).
Commonwealth Edison will use this
H.'
R. Denton February 9, 1983 information as the basis for establishing a specific power restriction during interim operation of the Byron /Braidwood units.
We do not intend to operate any unmodified steam generators at power levels exceeding those jueged acceptable at Westinghouse.
It is requested that the NRC approve this interim power rostriction option so that plant startup may proceed in the event that steam generator modifications cannot be completed prior to fuel load.
We would be happy to discuss this matter further at your convenience.
Please contact this office.
Very truly yours, 4"
T. R.
Tramm Nuclear Licensing Administrator ln 5964N
N
.p uam
~
g UNITED STATES 1 (hj e j 3 #q,
p, NUCLEAR REGULATORY COMMISSION'j h?\\ %
E WASHINGTON, D. C. 20555
[
4 JAN 2 01982 Docket Nos.:
STN 50-454 and STN 50-455 Mr. Louis 0. DelGeorge Director of Nuclear. Licensing Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690
Dear Mr. DelGeorge:
Subj ect: Plans for Use of Westinghouse Model D Steam Generators Within the last few months, there has been considerable interest paid to operating nuclear powr plants with pre-heater steam generators (Model D) manufactured by Westinghouse Electric Corporation.
This interest was initiated by tube failures and degradation in steam generators of this model at non-domestic nuclear power plants. We understand that you propose to use Westinghouse Model D pre-heater type steam generators at your facility.
Because of the safety concerns relative to steam generator tube damage, we consider the potential for such damage to be of safety significance.
Therefore, we request that you provide us with your plans to address this problem at your facility within 60 days of receipt of this letter. We are especially interested to know whether or not you are relying on the results of the Westingt suse test program or testi.', at operating plants, what instrumentation you may propose for detection f flow-induced vibrations, and what testing and start-up procedures you propose for you own facility.
Your full cooperation in this matter is appreciated.
The reporting and/or record keeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L. %-511.
Sincerely, p
Ga rr}e}r
} v i fs
. Ei se h I, Di~r'e tor Division of Licensing Office of Nuclear Reactor Regulation cc:
See next page
O Mr. Louis 0. DelGeorge Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier
' Mr. James G. Keppler Atomic Power Distribution U. S. NRC, Region III Westinghouse Electric Corporation 799 Roosevelt Road P. C. Box 355 Glen Ellyn, Illinois 60137 Pittsburgh, Pennsylvania 15230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, Illinois 61107 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 Dr. Bruce von Zellen Department of Biological Sciences Northern Illinois University DeKalb, Illinois 61107 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Myron Cherry, Esq.
Cherry, Flynn and Kanter 1 IBM Plaza, Suite 4501 Chicago, Illinois 60611
, Mr. William Fourney U. S. Nuclear Regulatory Commission
' Byron / Resident Inspectors Office 4448 German Church Road Byron, Illinois 61010 Ms. Diane Chavez 602 Oak Street, Apt. #4 Rockford, Illinois 61108
0 Comm2nwacith Edis;n
~
LI 9
,M Oae nm Naticaai Ptara. Cmesco imne s L
e^
gyr Address Reply to: Post Ott.ce Box 767 7-Chicago, illinois 60690 March 15, 1982 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Steam Generator Vibration Monitoring NRC Docke t Nos. 50-454, 50-455, 50-456 and 50-457 Reference (a):
January 20, 1982 letter from D. G. Eisenhu t t o L. O. De lGe o rg e.
Dear Mr. Denton:
This is to provide information requested in reference (a) regarding reports of tube damage in steam generators similar to those to be used at Byron and Braidwood.
In late October,1981 a foreign plant with Model D-3 steam generators experienced a steam generator tube leak.
Subsequent inspections of the steam generators of that plant and the D-3 steam generators of another foreign plant showed that the tubes were experiencing vibration and wear in the pre-heater area.
The Byron /Braidwood plants utilize model D-4 and D-5 s team generators which are similar in configuration to the D-3 steam generators.
Westinghouse has identified to us the nature of the mechanism observed in two non-domestic plants with Model D-3 steam generators.
We have discussed with Westinghouse the program that is in place to understand the nature of phenomena and to justify operation of all i
pre-heat steam generators.
The Westinghouse program includes the l
use of scale model testing, analytical studies, wear testing, periodic eddy current inspection of operating units, and the use of diagnostic internal and external instrumentation in selected operating plants.
In our review of the Westinghouse program, we have determined _ws _will rely on the results o f the Westinghouse l
analysis and test programs and the experience and data gained at l
operating plants.
At the present time one Model D-3 unit (split flow pre-heater) and one Model D-4 unit (counter flow pre-heater) i l
l l
l l
l
- ?
,t H. R. Denton March 15, 1982
~
are equipped with diagnostic internal and external instrumentation as part of the Westinghouse program.
After the data from these units are collecteo and evaluated, we will be able to determine if any diagnostic instrumentation should be attached to or installed in the steam generators at our plant.
This determination should be made by September 1,1982 and a further response will be submitted at that time.
If you have any questions concerning this matter, please contact this office.
One (1) signed original and fifty-nine (59) copies of this letter are provided for your use.
Very truly yours, ji b ef&=- -
T. R.
Tramm Nuclear Licensing Administrator 1m 3622N
[t!^KEGUq'o UNITED STATES
[ h f., [
NUCLEAR REGULATORY COMMISSION 7 \\%f / j WASHING TON, D. C. 20555 Docket Nos.:
STN 50-454, STN 50-455, STN 50-456, STN 50-457 50-369, 50-370, 50-390, 50-391, STN 50-546, STN 50-547, 50-445, 50-446, 50-395, 50-413, 50-414, 50-498, 50-499, 50-400, 50-401, 50-402 and 50-403 MEMORANDU'1 FOR:
- 8. J. Youngblood, Chief, Licensing Branch No.1, DL FROM:
S. Chesnut, Project Manager, Licensing E. Inch No.1, DL
SUBJECT:
SU.44ARY OF MEETING ON WESTINGHOUSE MODEL D STEAM GENERATORS A meeting was held February 19, 1982 in Bethesda, Maryland with representatives from Westinghouse and various utilities which had purchased Westinghouse Model D steam generators.
A list of attendees is given in Enclosure (1).
Westinghouse representatives presented the results of their initial evaluations of accelerated tube wear on Model D steam generators noted at two non-domestic plants in Ringhals, Sweden (Model D3) and Almaraz, Spain (Model D3). Eddy current data and information derived from internal and/or external flow monitoring instruilentation of scale models and other Model 9 steam generators at McGuire (02) and Krsko, Yugoslavia (D4) was also discussed.
Westinghouse representatives reported the the accelerated tube wear was flow related and had only been observed at two non-domestic plants. The accelerated wear was attributed to turbulence in the preheater region caused by the feed inlet inpingement plate and flow limiter.
Initial data from the instrumented steam generators showed that the onset of the increased turbulence occured at high feed flow rates (approximately 50% for Models 02 and 03, 70% for D4, 05).
Westinghouse indicated that increased instrumentation and additional analyses would continue until a resolution was reached. Westinghouse also discussed several preliminary design change possibilities which would decrease the flow-induced vibrations and turbulence. Westinghouse indicated that it wnuld make reconnendations to utilities but that each utility would respond to the staff as to appropriate measures to prevent the accelerated tube wear.
l
{
S. 4. Chesnut, Project Manaqer Licensing Branch No. 1 Division of Licensing
Enclosure:
As stated cc:
See next.,9 age
Mr. Louis 0. DelGeorge Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier Atomic Power Distribution Westinghouse Electric Corporation Post Office Box 355 Pittsburgh, Pennsylvania 15230 Paul M, Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 C. Allen Bock, Esq.
Post Office Box 342 Urbana, Illinois 61801 Thomas J. Gordon, Esq.
Waaler, Evans-& Gordon 2503 S. Neil Champaign, Illinois 61820 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street
.Essex, Illinois 60935 l
Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 U. S. Nuclear Regulatory Commission Resident Inspectors Office RR#1, Box 79 Braceville, Illfrois 60407 Mr. James G. Keppler U. S. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 l
l 9
6
\\
o Mr. Louis 0. DelGeorge Driector of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier Mr. James G. Keppler Atomic Power Distribution U. S. NRC, Region III Westinghouse Electric Corporation 799 Roosevelt Road Post Offica Box 355 Glen Ellyn, Illinois 60137 Pittsburgh, Pennsylavania 15230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, Illinois 61107 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 Dr. Bruce von Zellen Department of Biological Sciences Northern Illinois University DeKalb, Illinois 61107 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Myron Cherry, Esq.
Cherry & Flynn Suite 3700 Three First National Plaza Chicago, Illinois 60602 Mr. William Fourney U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Office 4448 German Church Road Byron, Illinois 61010 Ms. Diane Chavez 602 Cak Street, Apt. #4 Rockford, Illinois 61108
1 Enclosuro 1 Attendees List NRC Westinghouse E. Doolittle J. Schulties K. Kiper D. MNalinowski C. D. Sellers N. Mueller B. Turovlin T. Timmons J. Gleim R. Twogood E. G. Adensam J. McAdoo S. Chesnut D. Sheats G. Lanias G. L. Calhoun W. Johnston D. R. Grain C. Cheng W. E. Pennell T. A. Ippollto T. J. Kerrigan TVA K. N. Jabbour S. B. Burwell P. G. Ioannides P. Bemis A. R. Herdt Swedish Nuclear Power Plant A. Taboada K. Wichman L. G. Larsson R. L. Tedesco B. Erikigaard B. Senseney R. A. Birkel McGuir_e J. Rajan E. J. Brown P. Bemis J. Youngblood G. A. Coop
' J. I. Villadoniga K. S. Canady Krs,ko (Yugoslavia)
D. Ieretic C. V. Dadd Westinghouse Nuclear (Spain)
Argonne National Lab.
R. DeHara J. Jendrezejczyk
- 14. Wambsganss J. Gorosami, F. Alomar T_exas Utilities B. S. Kacko E. Alarcon
_S_outh Car _olina Electr'c & Gas Company R. Clary C. A. price
'l. O. Quinton
.._e.
~
l
+
n v i.,' {.,{e..
l 'v!/[N - l
'. '/,r
/.*
/
i g
v B/B March 15, 1982 Massrs:
C. Reed /N. A. Kershaw Q. A. Engineer - SNED J. S. Abel V. 1. Schlosser/C. J. Tomashek H.
E. Bliss D. J. Scott (NC Only)
T.
C. Cihlar/G. E. Peterson W.
J. Shewski R. Cosaro T. R. Sommerfield J. D. Deress/J. T. Westermeier G. Sorensen E.
E. Fitzpatrick W.
L.
Stiede K.
L. Graesser (NC Only)
H. K. Stolt/W.
L.
Eck J. F. Gudac (Bull., Circ., & I. No t. Only)
J.
H.
Hughes R.
J.
Tamminga (ISI Only)
R. E. Jortberg G. P. Wagner N.
J, Kalivianakis (NC Only)
P.
P. Steptoe-IL&B (Letters Only)
A.
W. Kleinrath M.
A. Bowidowicz - S&L O. E. Lindvall W.
E. Kortie r - W J.
J. Maley G. Wright - State of Illinois M.
A. Stanish (NRC/ CECO Ltrs only)
R. E. Querlo W. R. Bird - Consumers Power Co.
Q.
A.
Engineer - Byron RIII Only NL Distribution In the judgement of the Nuclear Licensing Administrator, the attached document contains the following commitments to the NRC or requirements from the NRC.
Identification of Attached Document:
March 15, 1982, letter from T. R.
Tramm to H. R. Denton regaroing oyron/Braidwood Steam Generator Vibration Monitoring.
NRC Commitment or Requirement:
Responsible Due Date Commitment or Requirement Edison Departmen t 8/31/82 Provide information on monitoring Projects /Westermeier system.
then it is determined by the responsible department that a due date will not be met, the Nuclear Licensing Administrator should be notified immediately.
T. R. Tr.amm 82-54
,,f 1m
- ./
- n' Commonwe:lth Edison O+j '
Ons First National Ptna. Chicago. Illinois Q p~ Addrtss Riply to: Past Offica Box 767
~
Chicago. Illinois 60690 i
March 15, 1982 4
4 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatcry Commission i
Washington, DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Steam Generator Vibration Monitoring NRC Docket Nos. 50-454, 50-455, 50-456 and 50-457 Reference (a):
January 20, 1982 letter from D. G. Eisenhut to L. O. DelGeorge.
Dear Mr. Denton:
This is to provide information requested in reference (a) regarding reports of tube damage in steam generators similar to those to be used at Byron and Braidwood.
In late October,1981 a foreign plant with Model 0-3 steam generators experienced a steam generator tube leak.
Subsequent inspections of the steam generators of that plant and the D-3 steam generators of another foreign plant showed that the tubes were experiencing vibration and wear in the pre-heater area.
The Byron /Braidwood plants utilize model D-4 and D-5 steam generators which are similar in configuration to the D-3 steam generators.
Westinghouse has identified to us the nature of the mechanism i
observed in two non-domestic plants with Model D-3 steam generators.
We have discussed with Westinghouse the program that is in place to understand the nature of phenomena and to justify operation of all pre-heat steam generators.
The Westinghouse program includes the use of scale model testing, analytical studies, wear testing, periodic eddy current inspection of operating units, and the use of diagnostic internal and external instrumentation in selected operating plants.
In our review of the Westinghouse program, we have determined we will rely on the results of the Westinghouse analysis and test programs and the experience and data gained at operating plants.
At the present time one Model D-3 unit (split flow pre-heater) and one Model D-4 unit (counter flow pre-heater)
,,.-,-v-n - - - - - -
l
'H. R. Denton March 15, 1982 are equipped with diagnostic internal and external instrumentation as part of the Westinghouse program.
After the data from these units are collecteo and evaluated, we will be able to determine if any diagnostic instrumentation should be attached to or installed in the steam generators at our plant.
This determination shculd be made by September 1,1982 and a further response will be submitted at that time.
If you have any questions concerning this matter, please contact this office.
One (1) signed original and fifty-nine (59) copies of this letter are provided for your use.
Very truly yours, ji h ef&= -
T. R.
Tramm Nuclear Licensing Administrator 1m 3622N I
e f
l
/
f a
)
+ -
r -
s.1 g,
UNITED STATES j$
E NUCLEAR REGULATORY COMMISSION 5,(
g g'
. j WASHINGTON, D. C. 20555
$AR 2 7 IS2
%,,,,,+
Docket Nos.:
STN 50-454, STN 50-455 and STN 50-456, STN 50-457 Mr. Louis 0. DelGeorge Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. DelGeorge:
Subject:
Summary of Meeting with Westinghouse on Model D and E Steam Generators A p'roprietary meeting was held with Westinghouse on July 21, 1982 to discuss progress made in resolving accelerated tube wear experienced on operating plants with Model D steam generators. Since Byron and Braidwood Stations will utilize Models D-4 and D-5 steam generators a summary of the issues discussed is attached for your information.
Sincerely, k
N. L A F0A B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing
Attachment:
As stated cc:
See next page I
J
.,e f
0
.L
l j
Mr. Louis 0. DGlGe8rge Director of Nuclear Licensing Comonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier Atomic Power Distribution Westinghouse Electric Corporation -
Post Office Box 355 Pittsburgh, Pe.1nsylvania 15230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois. 60603 C. Allen Bock, Esq.
Post Office Box 342
. Urbana, Illinois 61801 Thomas J. Gordon, Esq.
Waaler, Evans & Gordon 2503 S. Neil Champaign, Illinois 61820
' Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 4
Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 U. S. Nuclear Regulatory Commission Resident Inspectors Office RR#1, Box 79 Braceville, Illinois 60407 Mr. James G. Keppler U. S. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 3
g 4
..,.,,, _., _. ~.,
,.3_,.
.~w e.
Mr. Louis 0. DelGeorge Driector of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc:
Mr. William Kortier Mr. James G. Keppler Atomic Power Distribution U. S. NRC, Region III Uestinghouse Electric Corporation 799 Roosevelt Road Post Office Box 355 Glen Ellyn, Illinois 60137 Pittsburgh, Pennsylavania 1S230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, Illinois 61107 Ms. Briciget Little Rorem Appleseed Coordinat'or 117 North Linden Street Essex, Illinois 60935 Dr. Bruce von Zellen Department of Biological Sciences Northern Illinois University DeKalb, Illinois 61107 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Myron Cherry, Esq.
' Cherry & Flynn Suite 3700 Three First National Plaza Chicago, Illinois 60602 Mr. William Fourney.
U. S. Nuclear Regulatory Commission Byron / Resident Inspectors Office 4448 German Church Road Byron, Illinois 61010 Ms. Diane Chavez 602 Oak Street, Apt. #4 Rockford, Illinois 61108 e
---r-
UNITED STATES j
g NUCLEAR REGULATORY COMMISSION y
j WASHINGTON, D. C. 20555 s
j JUL 2 31982 Docket No.: 50-395 MEMORANDUM FOR:
B. J. Youngblood, Chief, Licensing Branch No.1, DL FROM:
W. F. Kane, Project Manager, Licensing Branch No. 1, DL
SUBJECT:
SUMMARY
OF MEETING REGARDING WESTINGHOUSE MODEL D AND E STEAM GENERATORS A meeting was held on July 21, 1982 in Bethesda, Maryland with representatives from Westinghouse and a number of utilities that had purchased plants utilizing these steam generators. A list of attendees is provided in the enclosure.
The purpose of the meeting was to have Westinghouse discuss the progress made since our last meeting in resolving the accelerated tube wear experienced on operating plants with Model D steam generators. A summary of the previous meeting shich was held on May 14, 1982 is provided in a memorandum dated May 20, 1982 from W. Kane to B. J. Youngblood.
The major points made by Westinghouse at the meeting for the D2/D3 program are as follows:
1.
Major Developments Preliminary design completed Fabrication development initiated Long lead material procured Tooling and procedures development 50% complete One month operation of 75% completed on McGuire Full scale testing facility (SSPB) commissioned 2.
Open Items Full scale verification testing Tube vibration acceptance criteria 3.
Near Term Milestones SSPB initial tests complete - 7/22/82 High temperature tests complete - 7/16/82 Final design review complete - 8/11/82 Third party review ccomplete - 8/16/82 First plant modification hardware complete - 8/30/82 Tooling, procedures, and trained crew available - 9/14/82 Major milestones in the 04/05/E program were given as follows:
Generic counterflow S/G program definition - complete Scale model testing - commenced KRSK0 system modifications - complete
, JUL 2 31982 Diagnostic data available from KRSK0 - 8/15/82 Scale model testing complete - 11/1/82 Design review and generic modification selection - 1/8/83 It was agreed that a followup generic meeting with Westinghouse would be appro-priate in about a month.
,/
./
,/ W.
'. A W. F'. Kane, Project Manager Licensing Branch No. 1 Division of Licensing
Enclosures:
As stated cc: See next page i
I l
I I
.a....
ENCLOSURE LIST OF ATTENDEES NRC Staff Westinghouse Duke Power W. Kane T. Timmons S. Copp R. Tedesco J. Schulties J. Youngblood R. Nath T. Ippolito G. Calhoun Bechtel
- 0. Parr P. McDonough S. Chesnut W. Cummins N. Chapman C. Liang L. Clements E. Licitra H. Bermudez R. Serbu M. Spennati TSI H. Conrad D. Burns L. Frank N. Singleton J. McEwen*
R. Birkel K. Kiper D. Sells Argonne National Laboratory CNASCO E. Adensam T. Kenyon M. Wambsganss A. Burillo H. Brammer J. Rajan B. Singh TVA Commonwealth Edison R. Martin S. Burwell D. Ku11sek T. Tramm G. Wiedenhamer S. Stout J. Gallo l
l t
l l
- Part time attendee - not cleared for proprietary information i
Y
- I Mr. O. W. Dixon, Jr, Vice President,'. Nuclear Operations-South Carolina Electric & Gas Company Post Office Box 764 (Mail Code F-04)
Columbia, South Carolina 29218
- c: Mr. Henry Cyrus Senior Vice President South Carolina Public Service Authority 223 North Live Oak Drive 3
Moncks Corner, South Carolina 29461 J. B. Knotts, Jr., Esq.
Debevoise & Liberman
~
1200 17th Street, N. W.
~
Washington, D. C.
20036 Mr. Mark B. Whitaker, Jr.
Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company Posc Office 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1, Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o U. S. NRC
~,
~
Route 1, Box 64 Jenkinsville, South Carolina 29065 Mr. James P. O'Reilly U. S. NRC, Region II 101 Marietta Street Suite 3100 Atlanta, Georgia 30303 e
4 e e 9
,e e -- -
_