ML061640019
| ML061640019 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/15/2006 |
| From: | Lyon C NRC/NRR/ADRO/DORL/LPLE |
| To: | Koehl D Nuclear Management Co |
| lyon C, NRR/DORL, 415-2296 | |
| References | |
| TAC MD0242 | |
| Download: ML061640019 (6) | |
Text
June 15, 2006 Mr. Dennis Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FALL 2005 STEAM GENERATOR TUBE INSPECTION REPORT (TAC NOS. MD0242)
Dear Mr. Koehl:
By letter to the Nuclear Regulatory Commission (NRC) dated February 21, 2006, Nuclear Management Company, LLC submitted its inspection report for the fall 2005 refueling outage (U1R29) for the steam generator tube inspections at Point Beach Nuclear Plant, Unit 1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. J. Gadzala of your staff on June 12, 2006, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely,
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
Request for Additional Information cc w/encl: See next page
June 15, 2006 Mr. Dennis Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE FALL 2005 STEAM GENERATOR TUBE INSPECTION REPORT (TAC NOS. MD0242)
Dear Mr. Koehl:
By letter to the Nuclear Regulatory Commission (NRC) dated February 21, 2006, Nuclear Management Company, LLC submitted its inspection report for the fall 2005 refueling outage (U1R29) for the steam generator tube inspections at Point Beach Nuclear Plant, Unit 1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. J. Gadzala of your staff on June 12, 2006, it was agreed that you would provide a response within 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.
Sincerely,
/RA/
Carl F. Lyon, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorlLpl3-1 RidsNRRPMFLyon RidsNrrLADClarke RidsAcrsAcnwMailCenter RidsRgn3MailCenter RidsNrrDorlDpr LMiller, NRR RidsNrrDciCsgb
- Previously concurred ADAMS Accession Number: ML061640019
- email from LMiller OFFICE LPLIII-1/PM LPLIII-1/LA DCI/CSGB/BC LPLIII-1/BC NAME FLyon DClarke**
TBloomer*
LRaghavan DATE 6/15/06 6/15/06 6/8/06 6/15/06 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR U1R29 POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NUMBER 50-266 In reviewing Nuclear Management Company, LLCs submittal regarding the Point Beach Nuclear Plant (Point Beach), Unit 1, fall 2005 (U1R29) steam generator tube inspection report dated February 21, 2006, the NRC staff has determined that the following information is needed in order to complete its review:
1.
Indicate if the wear indications identified in steam generator (SG) A were inspected with both bobbin and +Point' probes. If the wear indications were not inspected with a
+Point' probe, discuss how you concluded the indications were wear.
2.
In Table 1, the historical comparison of wear indications in the anti-vibration bar area of SG A were provided. The percent through-wall (TW) was given for Tube Row 40 Column 42 for 1995, 2001, 2004, and 2005. Discuss why the percent TW for this tube was not given for 1998.
3.
Confirm that a visual inspection was performed (either during Point Beach, Unit 1 Refueling Outage 28 or Point Beach, Unit 1 Refueling Outage 29) at the locations where wear indications were reported at or near the top of the tubesheet and that these inspections indicated that no loose parts or foreign objects were present at these locations.
4.
Regarding the signature tubes, discuss whether both low and high row tubes were screened for potentially having elevated susceptibility to cracking. In addition, discuss the extent to which these signature tubes were also inspected with a rotating probe in the tubesheet region.
5.
Several dents and dings were reported for SG A. Clarify the difference between a dent and a ding. If any of the dents and dings are service induced, discuss the cause. In addition, discuss whether the size of the dents and dings are changing with time.
6.
Confirm that no known loose parts or foreign objects were left in SG A. If any were, discuss the basis for leaving these parts or objects in service (i.e., with regards to tube integrity).
7.
It was indicated that no significant degradation of the swirl vanes, moisture separator, or feedring J-nozzles were found. Discuss whether any degradation was found (other than the minor weld burn noted in two closely spaced J-nozzles).
Enclosure 8.
Discuss the nature of the SG wrapper modification that led to the plugging of two tubes in 1988.
9.
Discuss the nature (chemical constituents) of the sludge removed from the SG and the scale on the tubes. If copper (or other species that can affect eddy current data quality) is present, discuss the quality of the eddy current data and whether techniques have been qualified given the levels of interference that exist in your data.
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. F. D. Kuester President & Chief Executive Officer WE Generation 231 West Michigan Street Milwaukee, WI 53201 Regulatory Affairs Manager Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Mr. Jeffery Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 Michael B. Sellman President and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016 Douglas E. Cooper Senior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Site Director of Operations Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241