ML081910303
| ML081910303 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/11/2008 |
| From: | Jack Cushing NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Meyer L Florida Power & Light Energy Point Beach |
| Cushing, J S, NRR/DORL/LPLIII-1,415-1424 | |
| References | |
| TAC MD7231 | |
| Download: ML081910303 (6) | |
Text
July 11, 2008 Mr. Larry Meyer Site Vice President FPLE Point Beach 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH UNIT 1
SUMMARY
OF THE STAFFS REVIEW OF THE 2007 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 30 (TAC NO. MD7231)
Dear Mr. Meyer:
By letter dated October 25, 2007 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML072990108), FPL Energy Point Beach, LLC (the licensee),
submitted information summarizing the results of the 2007 steam generator tube inspections performed at Point Beach Nuclear Plant Unit 1 during refueling outage 30. Additional information regarding the spring 2007 Unit 1 steam generator tube inspections was provided by the licensee in a letter dated March 14, 2008 ADAMS Accession No.ML080770187).
The Nuclear Regulatory Commission staff has completed its review of these reports and concludes that the licensee provided the information required by Point Beach Nuclear Plant Unit 1 Technical Specifications and that no additional follow-up is required at this time. The staffs review of this report is enclosed.
Sincerely,
/RA/
Jack Cushing, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
As stated cc w/encl: See next page
The Nuclear Regulatory Commission staff has completed its review of these reports and concludes that the licensee provided the information required by Point Beach Nuclear Plant Unit 1 Technical Specifications and that no additional follow-up is required at this time. The staffs review of this report is enclosed.
Sincerely,
/RA/
Jack Cushing, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorlLpl3-1 RidsNRRPMJCushing RidsNrrLATHarris RidsAcrsAcnw&mMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr KKarowski AHiser AObodoako ADAMS Accession Number: ML081910303
- Memo dated 6/16/08 OFFICE LPL3-1/PM LPL3-1/LA DCI/CSGB/BC LPL3-1/BC NAME JCushing THarris AHiser*
LJames DATE 07/10/08 07/9/08 06/16/08 7/11/08
Point Beach Nuclear Plant, Units 1 and 2 cc:
Licensing Manager FPL Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Mr. J. A. Stall Executive Vice President, Nuclear and Chief Nuclear Officer FPL Group P. O. Box 14000 Juno Beach, FL 33408-0420 T. O. Jones Vice President, Nuclear Operations Mid-West Region Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Peter Wells Acting Vice President, Nuclear Training and Performance Improvement Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 John Bjorseth Plant General Manager Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241 Mark E. Warner Vice President, Nuclear Plant Support Florida Power & Light Company P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. Antonio Fernandez Senior Attorney FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420 Abdy Khanpour Vice President Engineering Support FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420 J. Kitsembel Electric Division Public Service Commission of Wisconsin P. O. Box 7854 Madison, WI 53707-7854 Mr. M. S. Ross Managing Attorney FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420 July 2008
ENCLOSURE POINT BEACH NUCLEAR PLANT UNIT 1
SUMMARY
OF THE STAFFS REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORTS FOR THE SPRING 2007 REFUELING OUTAGE DOCKET No. 50-266 By letter dated October 25, 2007 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML072990108), FPL Energy Point Beach, LLC (the licensee),
submitted information summarizing the results of the 2007 steam generator (SG) tube inspections performed at Point Beach Nuclear Plant (PBNP) Unit 1 during refueling outage 30.
Additional information regarding the spring 2007 Unit 1 (U1R30) SG tube inspections was provided by the licensee in a letter dated March 14, 2008 (Accession No. ML080770187).
PBNP Unit 1 has two Westinghouse 44F SGs each containing 3214 thermally-treated Alloy 600 tubes. Unit 1 SGs were replaced during refueling outage 11 in 1984. The tubes have an outside diameter of 0.875 inches, a wall thickness of 0.050 inches, and are supported by six stainless steel tube support plates and a baffle plate. The tube support plate holes are quatrefoil shaped. The U-bend region of the tubes in rows 1 through 8 was stress relieved after bending.
The licensee provided the scope, extent, methods, and results of their SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings. Only the tubes in SG B were inspected this outage.
After review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission staff has the following comments/observations:
- 1. The replacement SGs have accumulated approximately 228.6 effective full power months (EFPM) of operation. At the time of the U1R30 outage, the SGs had operated approximately 7.1 EFPM in the 60-EFPM sequential period.
- 2. A very small fine wire was observed in the bundle of SG B following sludge lancing. The wire was not removed from the SG. The licensee determined that the wire would not adversely affect the SG for at least two operating cycles. The licensee plans to perform chemical cleaning of the Unit 1 SGs in 2008, which may eliminate the presence of any remaining fine wires and may remove the sludge pile (which contains copper).
- 3. Secondary side inspections were performed in SGs A and B during the U1R30 outage.
The inspections in SG B included the steam drum, feedring, J-nozzles, and the quatrefoil-shaped holes in the uppermost (sixth) tube support plate. The inspections in SG A included follow up inspections for the melt-through on J-nozzles 2 and 3 and the bulge of the E-bank secondary moisture separator perforated plate. In addition, the inspections in SG A included trending of the deposit buildup in the quatrefoil-shaped holes in the uppermost (sixth) tube support plate.
In SG B, flow impingement patterns were observed on the feedring, on the outside of some primary moisture separator riser barrels as well as under and around several J-nozzles. In addition, one perforated plate on the secondary moisture separator is bowed and melt-through was observed on the interior of some J-nozzles (where the J-nozzle is welded to the feedring).
The quatrefoil-shaped holes had deposit buildup ranging from 0- to 100-percent blockage. Similar conditions were observed in SG A during the previous U1R29 outage.
In SG A, no change was noted (since the prior inspection) in the bowing of the perforated plate and the melt-through in the J-nozzles. In addition, no significant change was observed in the deposit buildup in the quatrefoil-shaped holes in the uppermost tube support plate in SG A since the last outage. The quatrefoil-shaped holes had deposit buildup ranging from 0- to 100-percent blockage, with an overall average of approximately 40-percent blockage. Chemical cleaning is scheduled for the fall of 2008.
This cleaning is expected to eliminate or minimize this blockage.
Based on a review of the information provided, the staff concludes that the licensee provided the information required by the technical specifications. In addition, the staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Principal Contributor: A. Obodoako Date: July 11, 2008