ML20236K260
| ML20236K260 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 06/04/1998 |
| From: | Stewart Bailey NRC (Affiliation Not Assigned) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| TAC-MA0696, TAC-MA0697, TAC-MA696, TAC-MA697, NUDOCS 9807090245 | |
| Download: ML20236K260 (5) | |
Text
.
June 4, 1998 Mr. Oliver D. Kingsley, President Nuclear Generation Group
+ : p' ' C l U r g Commonwealth Edison Company Executive Towers West ll1
,,,,..,.,;g g 3 yy 1400 Opus Place, Suite 500 m"
Downers Grove;IL 60515 PUBUC 00;UmT rs00M
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REDUCE DOSE EQUIVALENT IODINE FOR BRAIDWOOD STATION, UNIT 1 (TAC NOS. MA0696 AND MA0697)
Dear Mr. Kingsley:
By letter dated January 14,1998, Commonwealth Edison Company (Comed) submitted a license i
amendment request to reduce the dose equivalent iodine (DEI) in the reactor coolant system for Braidwood Station, Unit 1. The change is needed due to an increase in the predicted primary to secondary leak rate during a design basis accident (DBA), which can increase the offsite and control room doses.
The NRC staff has identified the need for additional information in order to complete its review of the proposed license amendment; Please respond to the following question within 45 days to support the staff's review schedule:
l Provide an assessment to confirm that the main steamline break (MSLB) is the bounding l
DBA for offsite and control room doses for the level of steam generator tube degradation that is assumed as the basis for the proposed license amendment. The assessment should consider (1) increased primary-to-secondary leakage during a Locked Rotor or Control Rod Ejection accident, (2) any assumed fuel failure for these accidents, and (3) potential for steam generator (SG) tube uncovery. Comed may include, as part of its assessment, an f
evaluation of the constraining effect against leakage provided by the support plates and corrosion product in the tube-to-support plate crevices under the assumed accident pressure /temperat'aro conditions, including the potential for steam flashing to cut through the corrosion product. Supporting data, analyses, and assumptions should be provided.
Sincerely, Q
Stewart N. Dailey, Pr e ger 9007090245 900604 Project Directorate 111-2 I
l PDR ADOCK 05000456 Division of Reactor Projects - lil/IV P
PDR Office of Nuclear Reactor Regulation l
Docket Nos. STN 50-456, STN 50-457 I
l cc: See next page l
Distribution:
. Docket File PUBLIC PDill 2 r/f E. Adensam, EGA1 S. Richards i
C. Moore S. Bailey OGC,015B18 ACRS, T2E26 M. Jordan, Rill i
R. Emch T. Sullivan i
DOCUMENT _ NAME:G:\\CMNTSP\\ BRAID \\BR0696.RAI
- See previous page for concurrence To r:ceive a copy of this document. Indicate >% box: "C" = Copy without enclosures *E' = Copy with enclosures "N" = No copy OFFICE PM:PDill-2 6
L6:Phil-2 6
D:PDill-2 C
EMCB PERB q
NAME SBAILEY =A6 Chil2f0RE SRICHARDS @ *TSULLIVAN
- REMCH 1
DATE 06/ y /98 06/ S /98 06/ 4 /98 05/27/98 05/22/98 OFFICIAL RECORD COPY
June 4, 1998 t
Ir. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West lll 1400 Opus Place, Suite 500 Downers Grove',IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REDUCE DOSE EQUIVALENT IODINE FOR BRAIDWOOD STATION, UNIT 1 (TAC NOS. MA0696 AND MA0697)
Dear Mr. Kingsley:
By letter dated January 14,1998, Commonwealth Edison Company (Comed) submitted a license amendment request to reduce the dose equivalent lodine (DEI) in the reactor coolant system for Braidwood Station, Unit 1. The change is needed due to an increase in the predicted primary to secondary leak rate during a design basis accident (DBA), which can increase the offsite and control room doses.
The NRC staff has identified the need for additionalinformation in order to complete its review of the proposed license amendment. Please respond to the following question within 45 days to support the staff's review schedule:
Provide an assessment to confirm that the main steamline break (MSLB) is the bounding DBA for offsite and control room doses for the level of steam generator tube degradation that is assumed as the basis for the proposed license amendment. The assessment should con ider (1) increased primary-to-secondary leakage during a Locked Rotor or Control Rod Ejection accident, (2) any assumed fuel failure for these accidents, and (3) potential for steam generator (SG) tube uncovery. Comed may include, as part of its assessment, an l
evaluation of the constraining effect against leakage provided by the support plates and l
corrosion product in the tube-to-support plate crevices under the assumed accident pressure / temperature conditions, including the potential for steam flashing to cut through the corrosion product. Supporting data, analyses, and assumptions should be provided.
i Sincerely, Stewart N. Bailey, Pr Project Directorate 111-2 i
Division of Reactor Projects - Ill/IV l
Office of Nuclear Reactor Regulation l
1 Docket Nos. STN 50-456, STN 50-457 l
l cc: See next page Distribution:
Docket File PUBLIC PDill-2 r/f E. Adensam, EGA1 S. Richards C. Moore S. Bailey OGC,015818 ACRS, T2E26 M. Jordan, Rlll R. Emch T. Sullivan DOCUMENT NAME:G:\\CMNTSP\\ BRAID \\BR0696.RAI
- See previous page for concurrence Ta r:ceive a copy of thle document, indicate 4 box: "C" = Copy without enclosures *E" = Copy with enclosures "N* = No copy OFFICE PM:PDill-2 6
LA:PM-2 (b
D:PDill-2 C
EMCB PERB t
NAME SBAILEY =;AB CMd" ORE SRICHARDS @ *TSULLIVAN
- REMCH DATE 06/ y /98 06/ 3 /98 06/ 4 /98 05/27/98 05/22/98 OFFICIAL RECORD COPY
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. enmaa ann 3
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+9 * * * * *,o June 4, 1998 L
Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company L
Executive Towers West lli 1400 Opus Place, Suite 500 Downers Grove,IL 60515
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION'RELATED TO LICENSE AMENDMENT REQUEST TO REDUCE DOSE EQUlVALENT LODINE FOR l.
j BRAIDWOOD STATION, UNIT 1 (TAC NOS. MA06g6 AND MA06g7)
Dear Mr. Kingsley.
By letter dated January 14,1998, Commonwealth Edison Company (Comed) submitted a license amendment request to reduce the dose equivalent lodine (DEI) in the reactor coolant system for Braldwood Station, Unit 1. The change is needed due to an increase in the predicted prirn.ary to secondary leak rate during a design basis accident (DBA), which can increase the offsite and control room doses.
The NRC staff has identified the need for additionalinformation in crder to complete its review of the proposed license emendment. Please respond to the following question within 45 days to support the staff's review schedule:
Provide an assessment to confirm that the main steamline break (MSLB) is the bounding DBA for offsite and control room doses for the level of steam generator tube degradation that is assumed as the basis for the proposed license amendment. The assessment should i
consider (1) increased primary-to-secondary leakage during a Locked Rotor or Control Rod Ejection accident, (2) any assumed fuel failure for these accidents, and (3) potential for i
steam generator (SG) tube uncovery. Comed may include, as part of its assessment, an i
evaluation of the constraining effect against leakage provided by the support plates and corrosion product in the tube-to-support plate crevices under the assumed accident pressure / temperature conditions, including the potential for steam flashing to cut through the corrosion product. Supporting data, analyses, and assumptions should be provided.
j l
Sincerely, 2
l Stewart N. Bailey, P.,':d L.ger Project Directorate 111-2 l
Division of Reactor Projects - lil/IV
. Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457 cc: See next page
r_
e I
O.. Kingsley Braidwood Station Commonwealth Edison Company Units 1 and 2 l
cc:
Michael Miller, Esquire Ms. Lorraine Creek Sidley and Austin RR 1, Box 182 One First National Plaza Manteno, Illinois 60950 I
Chicago, Illinois 60603 Mr. Ron Stephens i
Regional Administrator Illinois Emergency Services & Disaster Agency U.S. NRC, Region lli 110 E. Adams Street 801 Warrenville Road Springfield, Illinois 62706 Lisle, Illinois 60532-4351 Chairman Illinois Department of Nuclear Safety Will County Board of Supervisors Office of Nuclear Facility Safety Will County Board Courthouse 1035 Outer Park Drive Joliet, Illinois 60434 Springfield, Illinois 62704 Attomey General Document Control Desk-Licensing 500 S. Second Street Commonwealth Edison Company Springfield, Illinois 62701 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 George L. Edgar Morgan, Lewis and Bochius Ms. C. Sue Hauser, Project Manager 1800 M Street, N.W.
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Westinghouse Electric Corporation Washingto::, DC 20036 1
Energy Systems Business Unit Post Office Box 355 Commonwealth Edison Company Pittsburgh, Pennsylvania 15230 Braidwood Station Manager RR 1, Box 84
. Joseph Gallo Braceville, Illinois 60407 Gallo & Ross 1250 Eye St., N.W., Suite 302 Commonwealth Edison Company i
Washington, DC 20005 Site Vice President - Braidwood RR 1, Box 84 Ms. Bridget Little Rorem Braceville,IL 60407 Appleseed Coordinator 117 N. Linden Street Mr. David Helwig Essex, Illinois 60935 Senior Vice President.
Commonwealth Edison Company Howard A. Leamer Executive Towers Wost til Environmental Law and Policy 1400 Opus Place, Suite 900 Center of the Midwest Downers Grove, IL 60515 35 East Wacker Dr., Suite 1300 Chicago, Illinois 60601 Mr. Gene H. Stanley PWR's Vice President U.S. Nuclear Regulatory Commission Commonwealth Edison Company Braidwood Resident inspectors Office Executive Towers West lli RR 1, Box 79 1400 Opus Place, Suite 900 Braceville, Illinois 60407 Downers Grove,IL 60515
1 i
O. Kingsley Braidwood Station Commonwealth Edison Company Units 1 and 2 Commonwealth Edison Company Mr. Michael J. Wallace Reg. Assurance Supervisor-Braidwood Senior Vice President RR 1, Box 79 Commonwealth Edison Company Braceville, Illinois 60407 Executive Towers West lli 1400 Opus Place, Suite 900 Mr. Steve Perry Downers Grove,IL 60515 BWR's Vice President Commonwealth Edison Company Executive Towers West lli 1400 Opus Place, Suite 900 Downers Grove,IL 60515 Mr. Dennis Farrar Regulatory Services Manager Commonwealth Edison Company Executive Towers West 111 l
1400 Opus Place, Suite 500 l
Downers Grove, IL 60515 l
l Ms. Irene Johnson, Licensing Director i
Nuclear Regulatory Services Commonwealth Edison Company i
i Executive Towers West 111 1400 Opus Place, Suite 500 Downers Grove, IL 60515 4
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