View source for BVY 05-071, Clarifications to Relief Request RI-01 Table

{{Adams
| number = ML052170159
| issue date = 08/01/2005
| title = Clarifications to Relief Request RI-01 Table
| author name = Devincentis J
| author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 05-071
| document type = Code Relief or Alternative, Letter type:BVY
| page count = 4
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
Verrnont Yankee mP.O.
Box 0500 185 Old Ferry Road LJJIEnterI         y                                                               Brattleboro, VT 05302-0500 Tel 802 257 5271 August 1, 2005 BVY 05-071 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

==Subject:==
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Clarifications to Relief Request RI-01 Table By letter dated October 1, 2003', as supplemented by letters dated December 23, 20032, January 22, 20043 and June 8, 20054, Vermont Yankee Nuclear Power Station (VY) submitted Relief Request RI-01. Relief Request RI-01 proposed to use various Boiling Water Reactor Vessel Internals Program guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Inservice Inspection of Reactor Pressure Vessel internal components.
Following discussion with your staff, VY is submitting a revised comparison table to correct a typographical error for one item and provide clarification to another. Accordingly, this letter and the attachment, provides a replacement table with the changes noted by revision bars There are no regulatory commitments contained within this letter.
Please feel free to contact me at (802) 258-4236, if there are any questions regarding this submittal.
Sincerely, M. DeVincentis Manager, Licensing Vermont Yankee Nuclear Power Station Attachment (1) cc:       USNRC Region I Administrator USNRC Resident Inspector - VY USNRC Project Manager - VY Vermont Department of Public Service 1 Reference VY Letter to USNRC, BVY 03-89, "Supplement 2 to Fourth-Interval Inservice Inspection (ISI)
Program Plan - Submittal of Relief Request RI-al," dated October 1,2003.
2 Reference VY Letter to USNRC, BVY 03-120, "Supplement to Relief Request RI-0l:' dated December 23, 2003.
3   Reference VY Letter to USNRC, BVY 04-07, "Supplement to Relief Request RI-01," dated January 22,2004.
4   Reference VY Letter to USNRC, BVY 05-059, "Revised Response to Request for Additional Information Regarding Relief Request RI-0 1," dated June 8,2005.
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ATTACHMENT TO BVY 05-071 Revised Comparison Table Regarding Relief Request RI-01 ENTERGY NUCLEAR OPERATIONS, INC.
VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271

Comparison of ASME Category B-N-1 and B-N-2 Requirements With BWRVIP Guidance Requirements (Note 1)
ASME Item                      Component                      ASME Exam     ASME         ASME          Applicable       BWRVIP         BWRVIP         BWRVIP Frequency No. Table                                                       Scope      Exam       Frequency        BWRVIP            Exam           Exam IWB-2500-1                                                                                             Document           Scope     l B 13.10        Reactor Vessel Interior                       Accessible   VT-3      Each period BWRVIP-18,                  Per VY Program Procedure PP 7027 Areas                              25,26, 38, 41,                    See Attached Table I (Non-specific)                            47, 48, 76 B 13.20         Interior Attachments Within                  Accessible   VT-I        Each 10-     BWRVIP48          Riser Brace       EVT-I       100% in first 12 Beltline - Riser Braces                         Welds                     year        Table 3-2       Attachment                    years, 25% during Interval                                                    each subsequent 6 years Lower Surveillance Specimen                                                         BWRVIP-48           Bracket          VT-I       Each 10-year Interval I Holder Brackets                                                                        Table 3-2      Attachment B 13.30        Interior Attachments Beyond                   Accessible   VT-3        Each 10-     BWRVIP-48           Bracket          VT-3       Each 10-year Interval Beltline - Steam Dryer Hold-                    Welds                     year         Table 3-2      Attachment down Brackets                                                           Interval Guide Rod Brackets                                                                  BWRVIP48            Bracket          VT-3       Each 10-year Interval Table 3-2      Attachment Steam Dryer Support Brackets                                                        BWRVIP-48           Bracket         EVT-I       Each 10-year Interval Table 3-2       Attachment Feedwater Sparger Brackets                                                          BWRVIP-48           Bracket         EVT-I       Each 10-year Interval Table 3-2       Attachment Core Spray Piping Brackets                                                          BWRVIP-48           Bracket         EVT-1       Every 4 Refueling Table 3-2      Attachment                    Cycles Upper and Middle Surveillance                                                       BWRVIP-48           Bracket          VT-3       Each 10-year Interval Specimen Holder Brackets                                                               Table 3-2      Attachment Shroud Support (Weld H9)                                                             BWRVIP-38         Weld H9        EVT-I or Maximum of 6 years 3.1.3.2,                          UT        for EVT-i, Maximum Figure 3-5                                    of 10 years for UT Shroud Support Legs (H12                       (Rarely                              BWRVIP-38             Not            Not             Not Required Welds)                                       Accessible)                                 3.2.3         Required       Required             (Note 2)
(Note 2)        (Note 2)                           I B 13.40         Integrally Welded Core Support               Accessible   VT-3        Each 10-     BWRVIP-38         Welds H8,       EVT-I or Maximum 6 years for Structure - Shroud Support                     Surfaces                   year          3.1.3.2,          H9              UT        EVT-1, 10 years for Interval      Figure 3-5                                    UT Shroud                                                                               BWRVIP-76        Welds HI,       EVT-I or Maximum 10 years 2.2.1            H2              UT BWRVIP-76          Vertical,      EVT-I or Maximum 6 years for Figure 3-3       Ring Seg.          UT        one-sided EVT-I, 10 Welds                      years for UT Below H2 BWRVIP-76           Tie-rod          VT-3       All four within 10 3.5           Repair                      years NOTE 1: This Table provides only an overview of the requirements. For more details, refer to ASME Section Xl, Table IWB-2500-1, and the appropriate BWRVIP document.       I BVY 03-89. Attachment 2. Page 4a of 6 (new page submitted by BVY 05-071)                                                                                                   I

NOTE 2: Periodically VY will have access to the lower plenum welds due to maintenance activities not related to the inspection recommendations in the BWRVIP guidelines.
In such cases, VY will perform a visual inspection of the shroud support leg welds to the extent practical. When inspection tooling and methodologies are developed that allows access to the lower plenum without disassembly beyond normal refueling activities, shroud support leg welds will be inspected with an appropriate NDE method. Results of inspections will be used to determine a re-inspection schedule. VY will adopt future inspection methods and schedules as they are developed and included into BWRVIP-38 and approved by the NRC staff.
BVY 03-89, Attachment 2, Page 4a of 6 (new page submitted by BVY 05-071)}}