View source for NL-03-134, Steam Generator Tube Inspection - Revision to Technical Specification 5.6.8 Report on Tubes Plugged, Indian Point Unit 3

{{Adams
| number = ML032330262
| issue date = 08/19/2003
| title = Steam Generator Tube Inspection - Revision to Technical Specification 5.6.8 Report on Tubes Plugged, Indian Point Unit 3
| author name = Dacimo F
| author affiliation = Entergy Nuclear Northeast
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000286
| license number = DPR-064
| contact person = 
| case reference number = NL-03-134
| document type = Letter type:NL
| page count = 3
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 EntLegy        %=%=Wff                                                         ~~~~~~~~~~~~~~~~~~~~~~~P.O Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations August 19, 2003 Re:     Indian Point Unit No. 3 Docket No. 50-286 NL-03-134 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1 -17 Washington, D.C. 20555-0001

==Subject:==
Steam Generator Tube Inspection - Revision to Technical Specification 5.6.8 Report on Tubes PluQed

==Reference:==
: 1)    Entergy letter (NL-03-069) to NRC, Steam Generator Tube Inspection -
Technical Specification 5.6.8 Report on Tubes Plugged," dated April 25, 2003.

==Dear Sir:==

By letter dated April 25, 2003 (Reference 1), Entergy Nuclear Operations, Inc. (Entergy) reported twelve Steam Generator (SG) tubes plugged following the Inservice Inspection (ISI) of Steam Generators in Refueling Outage 12 at Indian Point 3 Nuclear Power Plant. This letter revises the calculated depth of flaw reported in Reference 1 for eight of the twelve tubes.
The eight tubes had wear scars attributed to contact with sludge lance equipment used in Refueling Outage 11. The wear scars were not identified during Refueling Outage 11 because sludge lancing occurred after the ISI. The cause of the wear of the eight tubes was identified from the location of the indication. Visual inspection of two of the wear scars confirmed that the scars faced the tube lane and were about 1.1 inches long by 0.2 inches wide. During the recent SG inspection, the sludge lance wear indications were sized with EPRI eddy current technique 21998.1. This technique over-estimates the depth of volumetric indications greater than 0.25 inches long because the amplitude of a flaw is related to its volume, and this technique uses a standard with very low volume holes. Entergy has re-evaluated the sludge lance wear scar depths using an amplitude-based curve constructed using as-built depths. This is essentially the methodology of EPRI ETSS-21998.1, with a more representative flaw volume from the ASME flat bottom hole standard. Using this technique, the depth of the largest Indian Point 3 wear scar was reduced from 47 to 26% through wall. Virginia Electric & Power Company identified similar sludge lance equipment wear scars at Surry 1 during that station's 2001 inspection, and sized the depth of those indications using an amplitude curve based on the ASME flat bottom hole standard.
4-

NL 134 Page 2 of 3 The revised calculated depth of flaw data for Indian Point 3 is as follows:
SG           Tube               Location         Indication*       Flaw Depth Percent 31         R28  C29          -4.96 to 5.04          PVN                     n/a 32         R41  C28          TSH +0.15              VOL                    34%
32         R40  C29          TSH +0.0               VOL                    32%
32         R41  C29          TSH +0.05              VOL                    24%
32         R1   C85          TSH +16.70             VOL                  11%**
32         RI    C9          TSC +16.01             VOL                  _8_    _
32         R1   C66          TSC +18.16             VOL                  13_**
33         RI   C66          TSH +15.62             VOL                  26%**
TSH +18.04             VOL                  16%**
33         Ri   C27          TSC +17.86             VOL                  12%**
33         R1    C8          TSC +16.51             VOL                    9%**
34         R1    C8          TSH +16.69             VOL                  10%**
34         RI C84            TSC +16.92             VOL                  11%**
  *PVN is permeability variation, VOL is volumetric wear and TW is through wall wear for the plugged tubes.
  **These volumetric indications were attributed to wear from sludge lance equipment and were evaluated using an amplitude-based curve constructed from as-built depths developed using the ASME flat bottom hole standard.
 -There are no commitments contained in the correspondence. If you have any questions
--regarding this submittal, please contact Mr. John McCann, Manager, Licensing, at
;(914)734-5074.
Fred R. Dacimo Vice President, Operations Indian Point Energy Center i
i cc: see next page I

NL-03-134 Page 3 of 3 cc: Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Patrick Milano, Sr. Project Manager Project Directorate 1-1 Division of Ucensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555-0001 Resident Inspectors Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Paul Eddy Public Service Commission 3 Empire Plaza Albany, NY 12223 Mr. William M. Flynn New York State Energy Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399}}