BVY 06-029, Relief Request ISI-013, Fourth ISI Interval

Relief Request ISI-013, Fourth ISI Interval

ML060930685
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/27/2006
From:	Devincentis J Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 06-029, ISI-013
Download: ML060930685 (8)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Vermont Yankee P.O. Box 0500 185 Old Ferry Road Ente y ,n l revBrattleboro, Tel 802 257 VT 527105302-0500 March 27, 2006 BVY 06-029 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

1. Entergy Letter to USNRC, BVY 06-011, "Relief Request ISI-012, Fourth ISI Interval," dated February 16, 2006

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

Relief Request ISI-013, Fourth ISI Interval Entergy submitted Relief Request (RR) ISI-012, Fourth ISI Interval, via Reference 1 in February 2006 which proposed to use the requirements of BWRVIP-75A, in lieu of the ASME Section XI requirements and other augmented requirements, for the examination of Category B-F, Item 5.10, nozzle-to-safe end welds. It was later discovered that this resulted in a duplicate use of relief request number ISI-012, and that the RR number had already been approved by the NRC for an earlier Vermont Yankee relief request submittal (Reference TAC. Nos. MC0303, MC0336, MC0337, MC0338, and MC0339, dated July 6, 2004).

Entergy hereby submits a revised relief request, with an updated tracking number of RR ISI-013, for the BWRVIP-75A related relief request. All information and technical basis for relief remains the same as previously submitted. A condition report has been issued in accordance with Vermont Yankee's corrective action program. There are no adverse impacts on safety as a result of the incorrectly assigned RR number.

There are no commitments contained within this letter.

Please feel free to contact me at (802) 258-4236, if there are any questions regarding this subject.

Sincerely, Vf James M. DeVincentis Manager, Licensing Vermont Yankee Nuclear Power Station 4Ao47

BVY 06-029/ Page 2 of 2 cc: Mr. Samuel J. Collins, Regional Administrator USNRC Region I 475 Allendale Road King of Prussia, PA 19406-1415 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. James J. Shea, Project Manager U.S. Nuclear Regulatory Commission Office 08G9A Washington, DC 20555 Mr. David O'Brien Commissioner Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601

BVY 06-029 Enclosure 1 VERMONT YANKEE FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM RELIEF REQUEST ISI-013 Proposed Alternative InAccordance with 10CFR50.55a(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety-

1. ASME Code Component(s) Affected Code Class: Class 1 Examination Category: B-F Item Number: B5.10, Reactor Vessel Nozzle-to-Safe End Butt Welds, NPS 4 or larger

2. Armlicable Code Edition and Addenda The Code of Record for the Fourth Inservice Inspection Interval is ASME Section Xl Code, 1998 Edition, 2000 Addenda.

3. Armlicable Code Requirements ASME Section XI Code, Subsection IWB-2412 requires the percentage of examinations to be completed In accordance with Table IWB-2412-1, except for the examinations that may be deferred until the end of the Inspection interval. Table IWB-2412-1 defines a minimum and maximum number of examinations to be performed each inspection period.

ASME Section Xi Code, Subsection IWB-2500 requires components to be examined as specified in Table IWB-2500-1. The Extent and Frequency of Examination requires that all Category B-F welds be examined over the ten-year ISI interval.

B5.10 Examine accessible areas of the reactor vessel nozzle-to-safe end butt welds, NPS 4 and larger, by volumetric and surface examination method.

These welds are covered by the augmented examination requirements of NUREG-0313 (Reference 1) and Generic Letter 88-01, Including supplement 1 (References 2 and 3).

4. Reason for Reauest The attached list of affected Category B-F welds (Attachment 1) is subjected to the inspection schedule and requirements of Generic Letter GL 88-01, including supplement 1. Entergy proposes to use the schedules and frequencies specified in the BWRVIP-75-A (Reference 5, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules) in lieu of the above listed Code requirements. BWRVIP-75-A provides the technical basis for revisions to Generic 1

BVY 06-029 Enclosure 1 Letter 88-01 Inspection Schedules, which supports a reduction in the number of welds to be examined in some categories or an increase in the time between inspections in other categories.

5. Proposed Alternative In lieu of the requirements of ASME Section Xl, 1998 Edition, 2000 Addenda, and as augmented by the requirements of Generic Letter 88-01, the proposed alternative described herein shall be used.

Entergy will examine the affected Category B-F welds (Attachment 1) in accordance with BWRVIP-75-A. The Examination Method listed in Table IWB-2500-1 is not affected by this request.

Basis for Use By letter dated May 14, 2002 (Reference 4) the NRC issued their Final Safety Evaluation (SE) on BWRVIP-75. Inthat Safety Evaluation, the NRC staff concluded that, licensee implementation of the guidelines of BWRVIP-75 report, as modified, will provide an acceptable level of quality for inspection of the safety-related components." Additionally, the NRC concluded that, "the revised BWRVIP-75 guidance is acceptable for licensee referencing as the technical basis for relief from, or as an alternative to, the ASME Code and 10 CFR 55.55a, in order to use the sample schedules and frequencies specified in the revised BWRVIP-75 report that are less than those required by the ASME Code." BWRVIP-75-A is the updated version of the report which incorporated proposed changes by BWRVIP in response to recommendations in the NRC Safety Evaluation and other necessary revisions identified since the previous publication of the report.

Entergy concludes that the use of BWRVIP-75-A, as defined by the NRC Final Safety Evaluation, in lieu of the above specified Code requirements will provide an acceptable level of quality and safety. Therefore, approval is requested pursuant to 10 CFR 50.55a(a)(3)(i).

6. Duration of Proposed Alternative Entergy proposes to use the alternative for the remaining term of the Fourth Inservice Inspection Interval for Vermont Yankee Nuclear Power Station.

7. Precedents A similar relief request was approved for Edwin I. Hatch Nuclear Plant - Units 1 and 2 for the 3d Inservice Inspection Interval as RR-39 (Reference SER dated January 7, 2005 - TAC Nos.

MC2383 and MC2384))

8.

Attachment:

1. List of Affected Category B-F Welds.

2

BVY 06-029 Enclosure 1

9. References

1. W.S. Hazelton and W.H. Koo, 'Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, NUREG-0313, U

Rev. 2, USNRC, January 1988.

2. USNRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel," January 25, 1988.

3. USNRC Generic Letter 88-01, Supplement 1, "NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel," February 4, 1992.

4. William H. Bateman, Letter from NRC to Carl Terry, BWRVIP Chairman, "Final Safety Evaluation of the "BWRVIP Vessel and Internals Project, BWR Vessel and Internals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75)," EPRI Report TR-1 13932, October 1999 (TAC NO.

MA5012), dated May 14, 2002.

5. BWRVIP-75-A: BWR Vessel and Internals Project Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules, Final Report, October 2005.

3

BVY 06-029 Attachment 1 Relief Request to Use BWRVIP-75-A Guideline Requirements In Lieu of ASME Section Xi Code Requirement for the Examination of Category B-F Welds Relief Request ISI-013 Attachment 1 List of Affected Category B-F Welds

List of Affected B-F Welds Compoif~nt SYSTEM ID Description ASME Item MATERIAL BWRVIP SIZE ID Category Category N1A-SE RECIRCULATION OUTLE1 Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 28.8r N1 B-SE RECIRCULATION OUTLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 28.8r N2A-SE RECIRCULATION INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5" N2B-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5" N2C-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5" N2D-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5' N2E-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD Al 82 F316 A 15.5' N2F-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5" N2G-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5' N2H-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5' N2J-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5' N2K-SE RECIRC. INLET Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD A182 F316 A 15.5" N5A-SE CORE SPRAY Nozzle to Safe End Butt Weld BF B5.10 A508 C02 W/CLAD B168 INCONEL 600 E 13.5' N5B-SE CORE SPRAY Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W/CLAD B168 INCONEL 600 E 13.5' N6A-SE INSTRUMENTATION Nozzle to Safe End Butt Weld BF 85.10 A508 CL2 W /CLAD SA336 CL F8 A 9.0' N6B-SE INSTRUMENTATION Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD SA336 CL F8 A 9.0'

List of Affected B-F Welds SYSTEM ID Description ASIE Item MATERIAL BWRVIP SIZE Cornponent ID IIL Z Catoetory Category N7-SE VENT Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD SA336 CL F8 A 6.37-JET PUMP A508 W/CLAD E308 to 304SS Header N8A-SE INSTRUMENTATION Nozzle to Safe End Butt Weld BF B5.10 E308 Weld A 16.75" JET PUMP A508 W/CLAD E308 to 304SS Header N8B-SE INSTRUMENTATION Nozzle to Safe End Butt Weld BF B5.10 E308 Weld A 16.75 N9-SE CONTROL ROD DRIVE Nozzle to Safe End Butt Weld BF B5.10 A508 CL2 W /CLAD SA336 F8 & TP316 A 5.5" I 4 $ 4 +

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