ML020430630
| ML020430630 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 02/25/2002 |
| From: | Colburn T NRC/NRR/DLPM/LPD1 |
| To: | Kingsley O Exelon Generation Co |
| Colburn T | |
| References | |
| TAC MB2839 | |
| Download: ML020430630 (6) | |
Text
February 25, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB2839)
Dear Mr. Kingsley:
In performing our review of your August 2, 2001, request for relief from certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code as required by Title 10 of the Code of Federal Regulations, Section 50.55a, the Nuclear Regulatory Commission (NRC) staff has determined that it will need the enclosed additional information to continue its review. These questions had previously been faxed to your staff and were discussed with your staff during a conference call on January 31, 2002. As a result of the conference call, the question faxed to your staff related to Relief Request RR-00-01 was rewritten to provide greater clarity, and the question related to Relief Request RR-00-06 was deleted. In order for the NRC staff to complete its review on schedule, please provide your response within 60 days receipt of this letter.
If you have any questions, please contact me at (301) 415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Request for Additional Information cc w/encl: See next page
February 25, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB2839)
Dear Mr. Kingsley:
In performing our review of your August 2, 2001, request for relief from certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code as required by Title 10 of the Code of Federal Regulations, Section 50.55a, the Nuclear Regulatory Commission (NRC) staff has determined that it will need the enclosed additional information to continue its review. These questions had previously been faxed to your staff and were discussed with your staff during a conference call on January 31, 2002. As a result of the conference call, the question faxed to your staff related to Relief Request RR-00-01 was rewritten to provide greater clarity, and the question related to Relief Request RR-00-06 was deleted. In order for the NRC staff to complete its review on schedule, please provide your response within 60 days receipt of this letter.
If you have any questions, please contact me at (301) 415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC MOBrien TChan B. Platchek, RI ACRS TColburn JMunday AKeim PDI-1 R/F EAdensam OGC Accession No. ML020430603 OFFICE PDI-1\PM PDI-2\LA PDI-1\(A)SC EMCB\SC NAME TColburn MOBrien JMunday TChan DATE 2/19/02 1/15/02 2/25/02 2/22/02 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION THIRD 10-YEAR INTERVAL INSERVICE INSPECTION (ISI)
REQUESTS FOR RELIEF FOR THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NUMBER: 50-289 RR-00-01 The 1995 Edition including the 1996 Addenda, of the ASME Code,Section XI, Appendix VIII addresses performance demonstration requirements for ultrasonic examination procedures, equipment, and personnel used to detect and size flaws. The licensee should address how it will meet the performance demonstration requirements of Appendix VIII for using ultrasonic examination techniques from the ID surface in detecting and sizing flaws on the OD surface.
Demonstrate that the techniques used for the B&W demonstration meet the objective of the Appendix VIII requirements providing assurance that surface flaws will be detected. What types/directions and size of flaws will the instrument, procedures and personnel be capable of detecting?
RR-00-02 Please describe your proposed VT-1 examination. Will the examination be a direct examination or a remote visual examination? What magnifications will be used? Describe the capabilities of your examination (such as resolution, detection and sizing capabilities). What percentage of the weld will the VT-1 examination cover (what percentage of the C-D surface area as shown in Figure IWB-2500-13 will be examined with this method)?
The NRC staff has also accepted UT examination from the accessible surface. (See safety evaluations for Browns Ferry Nuclear Station, Units 2 and 3, 2nd 10-year ISI interval dated June 19, 2000, and Browns Ferry Nuclear Station, Unit 2, 3rd 10-year interval, relief request 2-ISI-10, Revision 1, dated February 4, 2002.
RR-00-03 For the letdown coolers longitudinal welds, the Code requires the examination of 1 foot of longitudinal weld intersecting the circumferential weld?
What is the approximate length of the longitudinal weld that the licensee is able to examine?
Why cant the licensee examine additional longitudinal welds and/or both coolers?
Provide a drawing(s) showing welds and identify accessible areas. What percentage of the required 1 foot are you able to obtain on one cooler?
What was examined in the first and second ISI intervals? Were there any unacceptable indications? What percentage of the required examination was attained?
Are there other examinations performed that help justify that the proposed inspection provides reasonable assurance of structural integrity?
Enclosure
REQUEST FOR ADDITIONAL INFORMATION THIRD 10-YEAR INTERVAL INSERVICE INSPECTION (ISI)
REQUESTS FOR RELIEF FOR THREE MILE ISLAND NUCLEAR STATION, UNIT 1 DOCKET NUMBER: 50-289 RR-00-05 How frequently are the decay heat removal coolers repaired/maintained so as to allow access to the weld location? Does the repair/maintenance program assure that one of the coolers will be disassembled each interval? Were either of the welds (DH-0399 and DH-0404) examined in the previous interval?
RR-00-07 Code Case N-546 is listed in the Draft Regulatory Guide (DG) 1091 which is out for public comment. The ADAMS accession number for DG-1091 is ML013120019. DG-1091 lists three conditions for the use of Code Case N-546. Please incorporate the three conditions.
Should resolution of the public comments change the conditions the licensee will be expected to follow the requirements in the Code Case and any additional requirements listed in the future revision to Regulatory Guide 1.147.
RR-00-08 Initially the licensee references Class 1 and Class 2 under the heading of COMPONENT IDENTIFICATION. In the proposed alternative the licensee references only Class 1 systems.
Will the alternative be applied to only Class 1 or to Class 1 and Class 2.
(Code Case N-533-1 with a condition is also referenced in the Draft Regulatory Guide DG-1091)
RR-00-11 The alternative should be drafted in terms of Code Case-566-1 (Vogtle SER dated 5/4/2001)
RR-00-13 Rewrite in terms of CC N-598. (See SER for Vogtle dated 5/4/2001).
Licensees proposed alternative did not address Table IWD.2412-1 Three Mile Island Nuclear Station, Unit No. 1 cc:
John Skolds Chairman Chief Operating Officer Board of County Commissioners Exelon Generating Company, LLC of Dauphin County 4300 Winfield Road Dauphin County Courthouse Warrenville, IL 60555 Harrisburg, PA 17120 William Bohlke Chairman Senior Vice President Nuclear Services Board of Supervisors Exelon Generating Company, LLC of Londonderry Township 4300 Winfield Road R.D. #1, Geyers Church Road Warrenville, IL 60555 Middletown, PA 17057 John B. Cotton Senior Resident Inspector (TMI-1)
Senior Vice President - Operations Support U.S. Nuclear Regulatory Commission Exelon Generating Company, LLC P.O. Box 219 4300 Winfield Road Middletown, PA 17057 Warrenville, IL 60555 Michael P. Gallagher Joseph J. Hagan Director - Licensing Senior Vice President - Exelon Generation Company, LLC Mid Atlantic Regional Operating Group Correspondence Control Desk Exelon Generation Company, LLC P.O. Box 160 200 Exelon Way, Suite 305 Kennett Square, PA 19348 Kennett Square, PA 19348 David J. Allard, Director Jeffrey A. Benjamin Bureau of Radiation Protection Vice President - Pennsylvania Department of Licensing and Regulatory Affairs Environmental Protection Exelon Generation Company, LLC P.O. Box 8469 4300 Winfield Road Harrisburg, PA 17105 Warrenville, IL 60555 George H. Gellrich Mark E. Warner Plant Manager Vice President TMI Unit 1 TMI Unit 1 AmerGen Energy Company, LLC AmerGen Energy Company, LLC P. O. Box 480 P. O. Box 480 Middletown, PA 17057 Middletown, PA 17057 James J. McElwain Regional Administrator Manager - Regulatory Assurance Region I TMI Unit 1 U.S. Nuclear Regulatory Commission AmerGen Energy Company, LLC 475 Allendale Road P.O. Box 480 King of Prussia, PA 19406 Middletown, PA 17057
Three Mile Island Nuclear Station, Unit No. 1 cc: continued John F. Rogge, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Edward J. Cullen, Jr., Esquire Vice President, General Counsel and Secretary Exelon Generation Company, LLC 300 Exelon Way Kennett Square, PA 19348 Michael A. Schoppman Framatome ANP Suite 705 1911 North Ft. Myer Drive Rosslyn, VA 22209 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Eric Epstein TMI Alert 4100 Hillsdale Road Harrisburg, PA 17112