ML20217Q593
| ML20217Q593 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/04/1998 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1195, TAC-MA1196, NUDOCS 9805080213 | |
| Download: ML20217Q593 (8) | |
Text
!
(
UNITED STATES
,1 NUCLEAR REGULATORY COMMISSION
- ~ '
,~
2 WASHINGTON, D.C. 2006H001
- l May 4, 1998-i l
l Mr. Oliver D. Kingsley, President l-Nuclear Generation Group Commonwealth Edison Company Executive Towers West lil l
1400 Opus Place, Suite 500 1
Downers Grove, IL 60515 t
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - REACTOR PRESSURE VESSEL INTEGRITY AT LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS.-
MA1195 AND MA1196) l
Dear Mr. Kingsley:
i l
l-Generic Letter 92-01, Revision 1, Supplement 1 (GL), " Reactor Vessel Structural Integrity" was l
issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report'any new data pertinent to the analysis of the structuralintegrity of their RPVs and to assess the impact of p
those data on their RPV integrity analyses relative to the requirements of Section 50.60 of l
Title <10 of the.Qgfqe of Federal Reaulations (10 CFR 50.60),10 CFR 50.61, Appendices G and H i
l
~ to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy pressure-temperature (P-T) limits.
(USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or l
1 L
After reviewing CcmEd's response, the NRC issued Comed a letter dated July 31,1996, for LaSalle, Units 1 and 2. In this letter the NRC acknowledged receipt of Comed's response, noted
.that additional RPV information may become available as a result of Owners Group efforts and requested that Comed provide the NRC with the results of the Owners Groups' programs relative -
to LaSalle. We further indicated that a plant specific TAC Number may be opened to review this l
material. Following issuance of these letters, the Boiling Water Reactor Vessel and Intemals i
Project (BWRVIP) submitted the report, " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel integrity issues (BWRVIP-46)." This report included bounding assessments of 1
new data from (1) the Combustion Engineering Owners Group (CEOG) database released in July 1997 that contains all known data for Combustion Engineering (CE) fabricated welds in Pressurized Water Reactor (PWR) and BWR vessels; (2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are documented in NRC inspection Report 99901300/97-01 dated January 28,1998; (3) FTi's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities' P-T limits submittel dated September 20,1996; and (4) Chicago Bridge 3
and Iron quality assurance records. New data for one vessel fabricated by Hitachi was also
' included in the BWRVIP report.
l.
L The staff is requesting that Comed re-evaluate the RPV weld chemistry values that were previously submitted as part of the licensing basis in light of the information presented in the CEOG, FTl and BWRVIP reports. The staff expects that Comed will assess this new information to determine whether any values of RPV weld chemistry need to be revised for LaSalle.
Therefore, in order to provide a complete response to items 2,3 and 4 of the GL, the NRC requests that Comed provide a response to the enclosed request for additional information (RAI) within 90 days of receipt of this letter. If a question does not apply to LaSalle, please indicate 1
9905000213 980504
\\
PDR ADOCK 05000373 P
PDR 1
NS 0
Vuv),))
l
m a
O. Kingsley ' '
s this in the RAI response along with the technical basis and, per the GL, provide a certification that previously submitted evaluations remain valid.
The information provided will be used in updating the, Reactor Vessel Integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identified data could result in the
- need for license amendments in order to maintain compliance with 10 CFR 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If soditional license amendments or assessments are necessary, the enclosed requests that
- Comed provide a schedule for such submittals.
If there should be any questions regarding this request, please contact me at (301) 415-1322.
l Sincerely, Original signed by:
4
~
Donna M. Skay, Project Manager
<u*
. Project Directorate lll-2
' Division of Reactor Projects - til/lV Office of Nuclear Reactor Regulation Docket Nos. 5d-373,50-374
Enclosure:
- cc w/ encl: See next page i
1 DISTRIBUTION-Docket File PUBLIC PDill-2 r/f.
E. Adensam, EGA1 S. Richards C. Moore D. Skay OGC,015818 ACRS, T2E26 D. Hills A.D, Lee DOCUMENT NAME: G:\\CMNTSP\\LASALLE\\LA1195.RAI To receive a oopy of this document,Indicat M the bc ki "C" = Copy without enclosures *E" = Copy with enclosures *N" = No copy OFFICE -
PM:PDill-2 A:D) -2 4-0:PDill-2 G
NAME DSKAY J/e W WdOFE SRICHARDS <S@
DATE-O'# L /98 05/
/b8 05/ 9 /98 OFFICIAL RECORD COPY -
l g
c,
'e q[ "
O. Kingsley - this in the RAI response along with the technical basis and, per the GL, provide a certification that previously submitted evaluations remain valid.
The information provided will be used in updating the Reactor Vessel integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potentialimpact on P-T limits. If additional license amendments or assessments are necessary, the enclosed requests that Comed provide a schedule for such submittals.
l.
If there should be any questions regarding this request, please contact me at (301) 415-1322.
Sincerely, l
Original signed by:
Donna M. Skay, Project Manager Project Directorate 111-2 l~
Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374 l
Enclosure:
RAI l
cc w/ encl: See next page I
DISTRIBUTION:
Docket File PUBLIC PDill-2 r/f E. Adensam, EGA1 S. Richards C. Moore D. Skay OGC,015B18 1!'
ACRS, T2E26.
D. Hills A.0, Lee
[
l
- DOCUMENT NAME: G:\\CMNTSP\\LASALLE\\LA1195.RAI Ya vocehne e oopy of this doousnent. Indcat =% the t,c k: "C" = Copy without enclosures "E" = Copy with enclosures "N* = No copy OFFICE PM:PDill-2
_6 19DJt -2 L0:PDill-2 C
NAME DSKAY-M WdOFE SRICHARDS ?>6 -
DATE 05f &
' 19 8 05/ !
/98 ~
05/ d /98 OFFICIAL RECORD COPY
4 O. Kingsley
-2.
L this in the RAI response along with the technical basis and, per the GL, provide a certification 4
that previously submitted evaluations remain valid.
The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR 50.60, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits, if additional license amendments or assessments are necessary, the enclosed requests that
- Comed provide a schedule for such submittals.
If there should be any questions regarding this request, please contact me at (301) 415-1322.
Sincerely
. ca )
Donna M. Skay, Project Ma ger Project Directorate 111-2 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation
. Docket Nos. 50-373, 50-374
Enclosure:
. RAI cc w/ encl: See next page 4
O. Kingsley LaSalle County Station a
Commonwealth Edison Company Units 1 and 2 cc:
Phillip P. Steptoe, Esquire Michael I. Miller, Esquire Sidley and Austin Sidiey and Austin One First National Plaza One First National Plaza Chicago, Illinois 60603 Chicago, Illinois 60603 Assistent Attomey General Document Control Desk-Licensing 100 W. Randolph St. Suite 12 Commonwealth Edison Company Chicago, Illinois 60601 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 U.S. NRC-LaSalle Resident inspectors Office 2605 N. 21st Road Commonwealth Edison Company Marseilles, Illinois 61341-9756 Site Vice President-LaSalle 2601 N. 21st Road Chairman Marseilles, Illinois 61341-9757 LaSalle County Board of Supervisors LaSalle County Courthouse Mr. David Helwig Ottawa, Illinois 61350 Senior Vice President Commonwealth Edison Company Attomey General Executive Towers West lil 500 S. Second Street 1400 Opus Place, Suite 900 Springfield, Illinois 62701 Downers Grove, IL 60515 Chairman Mr. Gene H. Stanley lilinois Commerce Commission PWR's Vice President 527 E. Capitol Avenue, Leland Building Commonwealth Edison Company Springfield, Illinois 62706 Executive Towers West lli 1400 Opus Place, Suite 900 lilinois Department of Nuclear Safety Downers Grove,IL 60515 Office of Nuclear Facility Safety 1035 Outer Park Drive Mr. Steve Perry Springfield, Illinois 62704 BWR's Vice President Commonwealth Edison Company Regional Administrator Executive Towers West til U.S. NRC, Region ill 1400 Opus Place, Suite 900 801 Warrenville Road Downers Grove,IL 60515 Lisle, Illinois 60532-4351 Mr. Dennis Farrar Commonwealth Edison Company Regulatory Services Manager
.LaSalle Station Manager Commonwealth Edison Ccmpany 2601 N. 21st Road Executive Towers West lll Marseilles, Illinois 61341-9757 1400 Opus Place, Suite 500 Downers Grove, IL 60515 Robert Cushing, Chief, Public Utilities Division -
Illinois Attomey General's Office 100 W. Randolph Street Chicago,.lllinois 60601
I O. Kingsley LaSalle County Station
- Commonwealth Edison Company Units 1 and 2 Ms. Irene Johnson, Licensing Director Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove, IL 60515 Commonwealth Edison Company Reg. Assurance Supervisor-LaSa!!e 2601 N. 21st Road Marseilles, Illinois 61341-9757 Mr. Michael J. Wallace Senior Vice President Commonwealth Edison Company Executive Towers West 111 1400 Opus Place, Suite 900 Downers Grove,IL 60515 i
J-Bff0UEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY
. Section 1.0: Assessment of Best-Estimate Chemistry The staff recently received the Boiling Water Reactor Vessel and Intemals Project (BWRVIP) report,
" Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity lasues (BWRVIP-46)".
Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, Supplement 1, the NRC requests the following:
- 1. - An evaluation of the bounding assessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of the reactor pressure vessel (RPV) beltline welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. If the limiting material for the vessel's pressure-temperature (P-T) limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
With respect to Comed's response to this question, the staff notes that some issues regarding the evaluation of the data were discussed in a public meeting between the staff, NEl, and industry
. representatives on November 12,1997. A summary of this meeting is documented in a meeting summary dated November 19,1997 (Reference 1). The information in Reference 1 may be usefulin helping to prepare the response, in addition to the issues discussed in the referenced meeting, Comed should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best-estimate chemistry. If a weld (or welds) were fabricated as weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters,
- and using the same coil (or coils in the case of tandem arc welds) of weld consumables, it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry determination. If information is not available to confirm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry should be evaluated both by assuming the data came from "one weld" and i
by assuming that the data came from an appropriate number of" multiple welds." A justification should then be provided for which assumption was chosen when the best-estimate chemistry ~was determined.
Section 2.0 P-T Limit Evaluation
- 2. If the limiting material for LaSalle changes or if the adjusted reference temperature for the limiting materialincreases as a result of the above evaluations, provide the revised RT, value for the limiting material. In addition, if the adjusted rte value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR Part 50, Appendix G, is maintained.
Reference
- 1. Memorandum from Keith R. Wichman to Edmund J. Sullivan, " Meeting Summary for November 12, 1997 Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses," dated November 19,1997.
Attachment:
Table 1 ENCLOSURE
E TN r
e E
td M
g nTL H
RO C
rE A
o T
t T
Ta A
RA g
n e
g ra M
30 w
s
,o la ire ta r
e M
Ty g
r R e n
i laT it m
R i
i it
)
L n(
I 1
r
(
o 0
/d g
1 n
f a
oin n
n d
dim o
1 e
omF i
t l
tc s
hrC e
e E
W t e L
et S
H B
V Me A
P D
n e
r i
i T
R d
W e
n t
)
s d
o yF e
e l
dl d
eatrC u
W e
nis(
q ri ts gemr e
h it r
e saeto c
s a
u sMhc a
E q
A Ca e
F a
r l
R i a fo r
n et t a d
o ad e
n i
De9 me s
o t
I n0 c
U a
c i
m L
s e1 gn Ou n a a
s ro u
m f
elf (x i
ta c
t l i l n
mie D
is I
v i
r d
D leu n
e hs a
t l t
- ae m
d a
t f
smk o o h
A o
m eic i
r BtsN nf t
or e
E io M
tac s s
e is if er i b y
e, l
t r
t e
t a e n a l
r.
smp et a
z p
d n
e eio im A
ru BtsC lar e
o E
tc if h
r t
t a
a ed f
e f
t u
e a e o
H n
n r
mi n
e VWiW m
o r
a M
t er We P
a he is l
d y
t e
Rl e t t s
s eH re u
d i;
od c
W i
l c
s
))
is e
a e
12 D
W F
V
((
.