ML13225A598

Review of the Steam Generator Tube Inspection Report for the Spring 2012 Refueling Outage

ML13225A598
Person / Time
Site:	Palisades
Issue date:	08/29/2013
From:	Mahesh Chawla Plant Licensing Branch III
To:	Entergy Nuclear Operations
Chawla M
References
TAC ME9924
Download: ML13225A598 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 29, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530

SUBJECT:

PALISADES NUCLEAR PLANT - REVIEW OF THE STEAM GENERATOR TUBE INSPECTION REPORT FOR THE SPRING 2012 REFUELING OUTAGE (TAC NO ME9924)

Dear Sir or Madam:

By letter dated November 01, 2012 (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML12306A534), as supplemented by letter dated May 28,2013 (ADAMS Accession No. ML13151A046), Entergy Nuclear Operations, Inc. (ENO, the licensee) submitted information to the U.S. Nuclear Regulatory Commission (NRC) summarizing the results of the 2012 steam generator tube inspections at Palisades Nuclear Plant (PNP). In addition to this report, the NRC staff summarized a conference call about the 2012 steam generator tube inspections at PNP in a letter to the licensee dated June 21,2012 (ADAMS Accession No. ML12165A389).

The NRC staff has completed its review of the report and concludes that the licensee provided the information required by the PNP Technical Specifications. No additional follow up is required at this time. The NRC staff's review is enclosed. If you have any questions or concerns, please contact me at 301-415-8371 or Mahesh.Chawla@nrc.gov.

Sincerely, Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255

Enclosure:

NRC staff's review of the steam generator tube Cc w/encl: Distribution via Listserv

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PALISADES NUCLEAR PLANT

SUMMARY

OF THE NRC STAFF'S REVIEW OFTHE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE 2012 REFUELING OUTAGE DOCKET NUMBER 50-255 By letter dated November 01, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12306A534), Entergy Nuclear Operations, Inc., the licensee, submitted information pertaining to their 2012 steam generator (SG) tube inspections at the Palisades Nuclear Plant (PNP). The licensee provided additional information regarding the SG inspections in a letter dated May 28,2013 (ADAMS Accession Number ML13151A046). In addition to this report, the U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call about the 2012 SG tube inspections at Palisades in a "ENOC-12-00021, Entergy Nuclear Operations, Inc., NRC Confirmatory Order EA-10-090, EA-10-248, EA-11-106,[[ASME section" contains a listed "[" character as part of the property label and has therefore been classified as invalid..F. Assessment Plan Available for Review|letter dated June 21, 2012]] (ADAMS Accession Number ML12165A389).

PNP has two Combustion 'Engineering Model 2530 replacement SGs. Each SG has 8,219 mill-annealed, Alloy 600 tubes. The tubes have an outside diameter of 0.75 inches, and a wall thickness of 0.042 inches. The tubes were expanded through the full depth of the tubesheet using an explosive process.

The licensee provided the scope, extent, methods, and results of their steam generator tube inspections in the documents referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.

After review of the information provided by the licensee, the NRC staff has the following comments/observations:

• There was no tube-to-tube wear detected in either SG A or SG B during the inspection.

• A steam drum inspection of SG B was performed. The feed ring, J-nozzles, welds, and support brackets were inspected with no abnormalities noted. Three J-nozzles were inspected internally for erosion and none was observed. Nine randomly spaced

. separator cans were inspected with no erosion issues noted; however, there was a slight amount of surface related corrosion at the base of the cans. The chevron separators, the main steam nozzle, and the deflection plate were inspected and all components were found to be in good condition with no degradation noted.

One tube had a freespan axial outside diameter stress corrosion cracking indication.

The indication was associated with a ding whose voltage amplitude was less than 2.0 volts. The indication was detected during the bobbin coil inspection.

• There were no cracks detected at historical wear locations within eggcrates, diagonal bars, or vertical straps. All new wear indications were inspected with a +Point' rotating pancake coil to characterize the indications.

Enclosure

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• There are small demister wires in both SGs. The sources of these wires were moisture separator reheaters that were installed prior to refueling outage 21 (Fall 2D1 D). The source was eliminated with the replacement of the moisture separator reheaters. The demister wires are D.D6-inches in diameter and are constructed of type 3D4 stainless steel. No tube wear has been associated with the wires.

Based on a review of the information provided by the licensee, the staff concludes that the licensee provided the information required by their technical specifications. The SG tube inspections at PNP 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.

ML13151A046), Entergy Nuclear Operations, Inc. (ENO, the licensee) submitted information to the U.S. Nuclear Regulatory Commission (NRC) summarizing the results of the 2012 steam generator tube inspections at Palisades Nuclear Plant (PNP). In addition to th'is report, the NRC staff summarized a conference call about the 2012 steam g!3nerator tube inspections at PNP in a letter to the licensee dated June 21,2012 (ADAMS Accession No. ML12165A389).

The NRC staff has completed its review of the report and concludes that the licensee provided the information required by the PNP Technical Specifications. No additional follow up is required at this time. The NRC staff's review is enclosed. If you have any questions or concerns, please contact me at 301-415-8371 or Mahesh.Chawla@nrc.gov.

Sincerely" IRA!

Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255

Enclosure:

NRC staff's review of the steam generator tube cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL3-1 RlF RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-1 Resource RidsNrrLAMHenderson Resource RidsNrrPMPalisades Resource RidsOgcMailCenter Resource RidsRgn3MailCenter Resource RidsNrrDeEsgb Resource KKarwoski, NRR AJohnson, NRR ADAMS Accession No.: ML13225A598

• See memo dated 7/26/2013 OFFICE NAME DATE LP3-1/PM MChawla 08/28/13 LPL3-1/LA MHenderson 08/19/13 ESGB/BC*

GKulesa 07/26/13 LP3-1/BC RCarlson 08/29/13 LPL3-1/PM MChawla 08/29/13