ML040210755
| ML040210755 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/21/2004 |
| From: | Donohew J NRC/NRR/DLPM/LPD4 |
| To: | Muench R Wolf Creek |
| Donohew J N, NRR/DLPM,415-1307 | |
| References | |
| TAC MB8455, WCAP-16028 | |
| Download: ML040210755 (7) | |
Text
January 21, 2004 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - TEST RESULTS FOR THE WITHDRAWAL OF SURVEILLANCE CAPSULE X (TAC NO. MB8455)
Dear Mr. Muench:
By letter dated April 8, 2003 (RA 03-0041), Wolf Creek Nuclear Operating Corporation (the licensee) submitted its report on reactor pressure vessel (RPV) surveillance Capsule X to the NRC in accordance with the requirement in 10 CFR Part 50, Appendix H. Capsule X was withdrawn from the reactor pressure vessel of Wolf Creek Generating Station at the end of Refueling Outage No. 12. The submitted report is WCAP-16028, "Analysis of Capsule X from Wolf Creek Nuclear Operating Corporation, Wolf Creek Reactor Vessel Radiation Surveillance Program," Revision 0, dated March 2003.
The staff review of WCAP-16028 focused on the following: (1) validate the licensees fluence calculation, (2) verify and compile the new and revised information on surveillance data in a format ready for updating the Reactor Vessel Integrity Database (RVID), and (3) review or perform the chemistry factor calculation based on the added surveillance data to assess the adequacy of the current pressure-temperature limits, pressurized thermal shock and upper shelf energy evaluation.
As documented in the enclosed evaluation, the staff has reviewed the report and found it acceptable. The staff concludes that the licensee's fluence calculation is acceptable and there will not be any significant impact on reactor vessel integrity due to the report results. The staff also compiled the new surveillance data for Capsule X and generated a table for RVID updating, which is attached to the enclosure. This closes out TAC No. MB8455. If you have any questions concerning this letter, contact me at 301-415-1307, or through the internet, at jnd@nrc.gov.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Evaluation of Wolf Creek Capsule X Report cc w/encl: See next page
January 21, 2004 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - TEST RESULTS FOR THE WITHDRAWAL OF SURVEILLANCE CAPSULE X (TAC NO. MB8455)
Dear Mr. Muench:
By letter dated April 8, 2003 (RA 03-0041), Wolf Creek Nuclear Operating Corporation (the licensee) submitted its report on reactor pressure vessel (RPV) surveillance Capsule X to the NRC in accordance with the requirement in 10 CFR Part 50, Appendix H. Capsule X was withdrawn from the reactor pressure vessel of Wolf Creek Generating Station at the end of Refueling Outage No. 12. The submitted report is WCAP-16028, "Analysis of Capsule X from Wolf Creek Nuclear Operating Corporation, Wolf Creek Reactor Vessel Radiation Surveillance Program," Revision 0, dated March 2003.
The staff review of WCAP-16028 focused on the following: (1) validate the licensees fluence calculation, (2) verify and compile the new and revised information on surveillance data in a format ready for updating the Reactor Vessel Integrity Database (RVID), and (3) review or perform the chemistry factor calculation based on the added surveillance data to assess the adequacy of the current pressure-temperature limits, pressurized thermal shock and upper shelf energy evaluation.
As documented in the enclosed evaluation, the staff has reviewed the report and found it acceptable. The staff concludes that the licensee's fluence calculation is acceptable and there will not be any significant impact on reactor vessel integrity due to the report results. The staff also compiled the new surveillance data for Capsule X and generated a table for RVID updating, which is attached to the enclosure. This closes out TAC No. MB8455. If you have any questions concerning this letter, contact me at 301-415-1307, or through the internet, at jnd@nrc.gov.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION PUBLIC NRay
Enclosure:
Evaluation of Wolf Creek Capsule X Report PDIV-2 Reading SCoffin RidsNrrDlpmPdiv(HBerkow) cc w/encl: See next page RidsNrrPMJDonohew RidsNrrLAEPeyton
- EMCB memorandum dated 12/15/2003 RidsOGCRp SRXB memorandum dated 11/07/2003 RidsACRSACNWMailCenter RidsRegion4MailCenter (D. Graves)
ACCESSION NO.: ML040210755 OFFICE PDIV-2/PM PDIV-2/LA EMCB/SC PDIV-2/SC NAME JDonohew EPeyton SCoffin* SDembek DATE 1/20/04 1/20/04 12/15/03 1/21/04 OFFICIAL RECORD COPY
Wolf Creek Generating Station cc:
Jay Silberg, Esq. Site Vice President Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P.O. Box 411 Washington, D.C. 20037 Burlington, KS 66839 Regional Administrator, Region IV Superintendent Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 400 P.O. Box 411 Arlington, TX 76011-7005 Burlington, KS 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office P.O. Box 311 8201 NRC Road Burlington, KS 66839 Steedman, MO 65077-1032 Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Vick L. Cooper, Chief Air Operating Permit and Compliance Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366
EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO CAPSULE X SURVEILLANCE CAPSULE PROGRAM REPORT
SUMMARY
OF FINDINGS (REACTOR VESSEL INTEGRITY NEUTRON IRRADIATION)
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 INTRODUCTION By letter dated April 8, 2003, Wolf Creek Nuclear Operating Corporation (the licensee) submitted its report on reactor pressure vessel (RPV) surveillance Capsule X to NRC.
Capsule X was withdrawn from the reactor pressure vessel of Wolf Creek Generating Station (WCGS) at the end of Refueling Outage No. 12. The submitted report is WCAP-16028, "Analysis of Capsule X from Wolf Creek Nuclear Operating Corporation, Wolf Creek Reactor Vessel Radiation Surveillance Program," Revision 0, dated March 2003.
The licensee stated that Capsule X reached the peak RPV surface fluence equivalent to 54 effective full power years (EFPY) after an actual exposure of 13.83 EFPY, since the lead factor (discussed below) for the capsule is 4.3. The capsule was withdrawn from the RPV on April 12, 2002.
The licensee has not requested and the staff, in reviewing WCAP-16028, Revision 0, is not approving, in any manner, any change to the licensing basis for WCGS.
REGULATORY REQUIREMENTS Section IV of Appendix H, "Reactor Vessel Material Surveillance Program Requirements," to 10 CFR Part 50 requires that a report be submitted to the Nuclear Regulatory Commission for each capsule that is withdrawn from a RPV. The report is to be submitted within one year of the date of capsule withdrawal. The report must describe the capsule and the test results for the capsule.
SUMMARY
OF STAFFS FINDINGS The staffs review of the report focused on three subjects: (1) to validate the licensees fluence calculation, (2) to verify and compile the new and revised information on surveillance data in a format ready for updating the Reactor Vessel Integrity Database (RVID), and (3) to review or perform the chemistry factor calculation based on the added surveillance data to assess the adequacy of the current pressure-temperature limits, pressurized thermal shock (PTS) and upper shelf energy (USE) evaluation. The report for Capsule X was submitted by the licensee within one year of when the capsule was withdrawn from the RPV.
Surveillance Capsule X results are credible for use in calculating chemistry factors in accordance with Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials." Heat #90146 is applicable only to WCGS axial and circumferential welds.
Lead Factors and Capsule Fluence Since last reported in 1995, the fluence calculation methodology has been changed. This results in a change to the capsule lead factors. Lead factors and capsule fluence reported in WCAP 16028, Revision 0, are different than originally reported in RVID.
Capsule Capsule Lead Factors Capsule Fluence (1019n/cm2)
Location WCAP 16028 RVID WCAP 16028 RVID U 58.50 F 4.25 4.38 .316 .343 Y 2410 F 3.93 4.00 1.19 1.308 V 60.10 F 4.02 4.08 2.22 2.528 X 238.50F 4.3 --- 3.49 ---
Note: WCAP-16028 updated lead factors and also provided plant-specific fluence evaluation based on Capsule X dosimetry analysis.
Chemistry Factors Capsule X dosimetry analysis updated capsule fluence numbers for current capsule X and the previous capsules. This results in a change in chemistry factors.
Capsule Material Chemistry Factor WCAP 16028 RVID Lower Shell Plate R2508-3 39.1 35.93 Weld (heat#90146) 44.1 (32.04)a 28.36 Note a: 32.04 is based on ratio of chemistry factors (vessel chemistry factor to capsule chemistry factor) of 0.726.
USE USE values for lower shell plate (longitudinal and transverse) and circumferential weld (heat
- 90146) weld remain higher than 50 ft/lbs. USE for other beltline materials remain above 50 ft/lbs.
PTS The reference temperature evaluated at the end-of-life fluence (RTPTS) values for the WCGS vessel beltline materials remain below the screening criteria.
Pressure Temperature Operating Limits Pressure temperature operating limits will not be significantly affected by the Capsule X results.
Fluence Calculated neutron fluence (projected) (E >1.0 MeV) at the core midplane (clad/base metal interface) for 32 and 54 EFPY are: 2.03 x1019 n/cm2 and 3.51 X1019 n/cm2, respectively.
Impact on Capsule X Results on RVID The staff verified and compiled the new surveillance data for Capsule X and generated a table for RVID updating. The table is attached to this evaluation.
Attachment:
Table 1 Principal Contributor: N. Ray Date: January 21, 2004
TABLE 1 DOCUMENTATION AND EVALUATION OF ALL SURVEILLANCE DATA FROM WOLF CREEK GENERATING STATION
(
REFERENCE:
WCAP-16028, REVISION 0)
Material* Capsule Fluence FF RTNDT FF x FF 2 Scatter/ Credible? USE and lead (10E19 (Fluence (EF) (a) RTNDT RTNDT (ft-lb) factor n/cm 2) Factor) -CFxFF (EF) (b)
Lower U,4.25 .316 .684 36.46 24.94 .468 9.72 Yes 145 Shell Plate-L Y,3.93 1.19 1.05 16.03 16.83 1.1 -25.03 No 131 R2508-3 V, 4.02 2.22 1.22 52.03 63.48 1.49 4.33 Yes 129 X, 4.3 3.49 1.33 61.06 81.21 1.77 9.06 Yes 142 Lower U,4.25 .316 .684 23.79 16.27 .468 -2.95 Yes 96 Shell Plate-T Y,3.93 1.19 1.05 35.39 37.16 1.1 -5.67 Yes 94 R2508-3 V, 4.02 2.22 1.22 54.53 66.53 1.49 6.83 Yes 88 X, 4.3 3.49 1.33 53.96 71.77 1.77 1.96 Yes 95 Sum: 378.19 9.656 CFR2508-3 =378.19/9.656=39.1 0 F Surveilla U,4.25 .316 .684 27.21 18.612 .468 -2.95 Yes 92 nce Weld Y,3.93 1.19 1.05 45.09 47.34 1.1 -1.22 Yes 94 Material V,4.02 2.22 1.22 46.3 56.49 1.49 -7.5 Yes 89 X,4.3 3.49 1.33 68.36 90.92 1.77 9.71 Yes 93 Sum: 213.362 4.828 CF Surv. Weld= 213.363/4.828=44.1 0 F, Modified CF=32.04 0F(c)
Notes:
- a. RTNDT values are measured.
- b. Predicted RTNDT is based on CF*FF. For example, CF for plate CF is 39.1 and ff is .684 and thus predicted RTndt is 39.1*.684=26.74. Hence the scatter is 36.46-26.74=9.72.
- c. CF for weld is 32.04EF considering the ratio of vessel chemistry factor to surveillance weld chemistry factor (44.1*31.6/43.5=32.04EF). Chemistry factors for capsule and vessel are taken from RVID.