RBG-47825, Request for Alternative in Accordance with 10 CFR 50.55a (a)(3)(i) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015)

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Request for Alternative in Accordance with 10 CFR 50.55a (a)(3)(i) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015)
ML18045A028
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/13/2018
From: Schenk T
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-47825, RR- RBS-ISI-015
Download: ML18045A028 (16)
v • d • e


Text

,.

.~ Entergx RBG-47825 February 13, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61 N SI. Francisville. LA 70775 Tel 225*381*4177 Timothy Schenk Regulatory Assurance Manager River Bend Station

SUBJECT:

Request for Alternative in Accordance with 10 CFR 50.55a (a)(3)(i) Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections (RR-RBS-ISI-015)

River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47

Dear Sir or Madam:

In accordance with 10 CFR 50.55a, "Codes and Standards," paragraph (a)(3)(i), Entergy requests NRC approval of the proposed alternative to American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Sub Article IWB-2500 to allow reduced requirements for nozzle-to-vessel weld and inner radius examinations. This alternative is requested for the fourth 1 O-year interval of the River Bend Station (RBS) Inservice Inspection Program.

The details of the 10 CFR 50.55a proposed alternative are enclosed as Attachment 1, and the specific components affected by this request are tabulated in Attachment 2. Attachment 3 is the River Bend Station response to BWRVIP-1 08 Plant Specific Applicability Criteria. The NRC provided a Safety Evaluation (Attachment 3, Reference 1) approving the generic technical basis and acceptability criteria for application of ASME Code Case N-702, "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1," on December 19, 2007, which Entergy has followed as detailed in the attached request. The plant specific applicability of the BWRVI P-1 08 report to RBS is demonstrated in.

Entergy requests approval of this request by November 30, 2018, in order to support refueling outage twenty (RF-20) scheduled for January 2019.

There are no regulatory commitments contained in this submittal. If you require additional information, please contact Mr. Tim Schenk at (225)-381-4177 or tschenk@entergy.com.

TAS/alc

RBG-47825 Page 2 of 2 Attachments:

1. Request for Alternative Use Of Code Case N-702 In Lieu Of Specific ASME Code Section XI Requirements RBS-ISI-015
2.

Specifi ~ Components Affected

3. Response to BW RVI P-1 08 Plant Specific Applicability Criteria cc:

(with Enclosure)

U. S. Nuclear Regulatory Commission Attn: Lisa Regner 11555 Rockville Pike Rockville, MD 20852 U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4511 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.

Austin, TX 78711 -3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821 -4312 RBF1-18-0013 LAR-2018-02

RBG-47825 Page 1 of 4 ATTACHMENT 1 RBG-47825 REQUEST FOR ALTERNATIVE USE OF CODE CASE N-7021N LIEU OF SPECIFIC ASME CODE SECTION XI REQUIREMENTS RBS-ISI-015

R8G-47825 Page 2 of 4 RIVER BEND STATION - UNIT 1 FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ALTERNATIVE RBS-ISI-015 10 CFR 50.55a(z)(1)

--Acceptable Level of Quality and Safety--

ASME Code Component(s) Affected Code Class:

Component Numbers:

Code

References:

Examination Category:

Item Number(s):

Unit / Inspection Interval Applicability:

ASME Section XI Code Class 1 Various (see Table 1 for detailed list of components)

ASME Section XI, 2007 Edition with the 2008 Addenda and Code Case N-702 8-0 83.90 and 83.100 River 8end Station (R8S), Fourth (4th) 10-Year Inservice Inspection (lSI) Interval I.

Applicable ASME Code Requirement(s)

ASME Section XI, 2007 Edition with the 2008 Addenda (Reference 1), Table IW8-2500-1,

Examination Category 8-0, "Full Penetration Welded Nozzles in Vessels" requires a volumetric examination of all nozzles with full penetration welds to the vessel shell (or head) and integrally cast nozzles each 1 O-year interval. Additionally, for ultrasonic examinations, ASME Section XI, Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," is implemented.

The RPV nozzle-to-vessel shell welds and nozzle inside radius sections or (nozzle radii) subject to this request are listed below in Table 1:

RBG-47825 Page 3 of 4 Group TABLE 1 RPV Nozzle-to-Vessel Shell Welds and Inside Radius Sections Description Total Number Minimum examined B13-D001-N01 Recirculation Outlet 2

1 B13-D001-N02 Recirculation Inlet 10 3

B13-D001 -N03 Main Steam 4

1 B13-D001 -N05 Core Spray 2

1 B13-D001-N06 Low Pressure Core Injection 3

1 B13-D001-N07 Top Head Spray 1

1 B13-D001 -N08*

Top Head Spare 1

1 B13-D001-N09 Jet Pump Instrumentation 2

1 B13-D001-N16*

Vibration Instrumentation 1

1

  • Not used Blind Flanged The minimum numbers of examinations listed above were completed during the Third 10-Year lSI Interval and all indications identified were found to be acceptable per ASME Section XI. No through wall flaws were detected and no changes in indications previously identified have been noted.

II. Reason for Request NRC Regulatory Guide 1.147, Revision 17 (Reference 2) conditionally accepts the use of Code Case N-702 (Reference 3). This code case provides an alternative to performing examination of 100% of the Nozzle-to-Vessel Shell Welds and Nozzle Radii for Examination Category B-D nozzles with the exception of the Feedwater and Control Rod Drive Return Line (CRDRL) Nozzles. The alternative is to perform examination of a minimum of 25% of the nozzle inner radius sections and nozzle-to-shell welds, including at least one nozzle from each system and nominal pipe size, excluding the Feedwater and CRDRL Nozzles.

III. Proposed Alternative and Basis for Use Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1), RBS requests approval to implement the alternative of Code Case N-702 in lieu of the code required 100% examination of all nozzles identified in Table 1. As an alternative, for the nozzle-to-vessel shell welds and inner radii identified in Table 1, R8S proposes to examine a minimum of 25% of the nozzle-to-vessel shell welds and inner radii, including at least one nozzle from each system and nominal pipe size, in accordance with Code Case N-702 and as permitted by Code Case N-702, a VT-1 visual examination of Item Nos. 83.201 and 83.100 may be performed in lieu of a volumetric examination.

1Note that Item No. 8 3.20 was removed from Section XI in the 2007 Edition.

RBG-47825 Page 4 of 4 Basis for Use Boiling Water Reactor (BWR) Vessel Internals Project (BWRVIP) has issued two topical reports:

BWRVIP-1 08 "Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," EPRI Technical Report 1003557, October 2002 (ML023330203) (Reference 5) and BWRVIP-241 "Probabilistic Fracture Mechanics Evaluation for the Boling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," EPRI Technical Report 1021005, October 2010 (ML11119A041) (Reference 6).

RBG-47825 Page 1 of 4 ATTACHMENT 2 RBG-47825 SPECIFIC COMPONENTS AFFECTED

RBG-47825 Page 2 of 4 RIVER BEND STATION - UNIT 1 FOURTH 10 YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ALTERNATIVE RBS-ISI-01S TABLE OF AFFECTED COMPONENTS COMPONENT NO CATEGORY ITEM DESCRIPTION NUMBER B 13-0001 -N01 A-O B-O B3.100 20.00" Reactor Recirculation Outlet Nozzle Inside Radius Section B13-0001 -N01 A-1 B-O B3.90 20.00" Reactor Recirculation Outlet Nozzle-to-Vessel weld B13-0001 -N01 B-O B-O B3.100 20.00" Reactor Recirculation Outlet Nozzle Inside Radius Section B13-0001 -N01 B-1 B-O B3.90 20.00" Reactor Recirculation Outlet Nozzle-to-Vessel weld B13-0001-N02A-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N02A-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001 -N02B-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N02B-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001 -N02C-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001-N02C-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001-N020-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N020-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001-N02E-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001-N02E-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001 -N02F-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N02F-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001 -N02G-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N02G-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001-N02H-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001 -N02H-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld

RBG-4782S Page 3 of 4 RIVER BEND STATION - UNIT 1 FOURTH 10 YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ALTERNATIVE RBS-ISI-01S TABLE OF AFFECTED COMPONENTS B 13-0001-N02J-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B 13-0001-N02J-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001-N02K-0 B-O B3.100 10.00" Reactor Recirculation Inlet Nozzle Inside Radius Section B13-0001-N02K-1 B-O B3.90 10.00" Reactor Recirculation Inlet Nozzle-to-Vessel weld B13-0001-N03A-0 B-O B3.100 24.00" Main Steam Nozzle Inside Radius Section B13-0001-N03A-1 B-O B3.90 24.00" Main Steam Nozzle-to-Vessel weld B13-0001-N03B-0 B-O B3.100 24.00" Main Steam Nozzle Inside Radius Section B13-0001-N03B-1 B-O B3.90 24.00" Main Steam Nozzle-to-Vessel weld B13-0001-N03C-0 B-O B3.100 24.00" Main Steam Nozzle Inside Radius Section B13-0001-N03C-1 B-O B3.90 24.00" Main Steam Nozzle-to-Vessel weld B 13-0001-N030-0 B-O B3.100 24.00" Main Steam Nozzle Inside Radius Section B13-0001-N030-1 B-O B3.90 24.00" Main Steam Nozzle-to-Vessel weld B13-0001-NOSA-0 B-O B3.100 12.00" Core Spray Nozzle Inside Radius Section B 13-0001-NOSA-1 B-O B3.90 12.00" Core Spray Nozzle-to-Vessel weld B13-0001-NOSB-0 B-O B3.100 12.00" Core Spray Nozzle Inside Radius Section B13-0001-NOSB-1 B-O B3.90 12.00" Core Spray Nozzle-to-Vessel weld B13-0001-N06A-0 B-O B3.100 10.00" Low Pressure Core Injection Nozzle Inside Radius Section B13-0001-N06A-1 B-O B3.90 10.00" Low Pressure Core Injection Nozzle-to-Vessel weld B13-0001-N06B-0 B-O B3.100 10.00" Low Pressure Core Injection Nozzle Inside Radius Section B13-0001-N06B-1 B-O B3.90 10.00" Low Pressure Core Injection Nozzle-to-Vessel weld B13-0001-N06C-0 B-O B3.100 10.00" Low Pressure Core Injection Nozzle Inside Radius Section B13-0001-N06C-1 B-O B3.90 10.00" Low Pressure Core Injection Nozzle-to-Vessel weld

RBG-47825 Page 4 of 4 RIVER BEND STATION - UNIT 1 FOURTH 10 YEAR INTERVAL INSERVICE INSPECTION PROGRAM REQUEST FOR ALTERNATIVE RBS-ISI-015 TABLE OF AFFECTED COMPONENTS B13-0001-N07-0 B-O B3.100 6.00" Top Head Spray Nozzle Inside Radius Section B13-0001-N07-1 B-O B3.90 6.00" Top Head Spray Nozzle-to-Vessel weld B13-0001-N08-0 B-O B3.100 6.00" Top Head Spare Nozzle Inside Radius Section B13-0001-N08-1 B-O B3.90 6.00" Top Head Spare Nozzle-to-Vessel weld B13-0001 -N09A-0 B-O B3.100 4.00" Jet Pump Instrumentation Nozzle Inside Radius Section B13-0001 -N09A-1 B-O B3.90 4.00" Jet Pump Instrumentation Nozzle-to-Vessel weld B13-0001-N09B-0 B-O B3.100 4.00" Jet Pump Instrumentation Nozzle Inside Radius Section B13-0001 -N09B-1 B-O B3.90 4.00" Jet Pump Instrumentation Nozzle-to-Vessel weld B13-0001 -N16-0 B-O B3.100 8.00" Vibration Instrumentation Nozzle Inside Radius Section B13-0001-N16-1 B-O B3.90 8.00" Vibration Instrumentation Nozzle-to-Vessel weld

RBG-47825 Page 1 of 6 ATTACHMENT 3 RBG-47825 RESPONSE TO BWRVIP-108 PLANT SPECIFIC APPLICABILITY CRITERIA

RBG-47S25 Page 2 of 6 RESPONSE TO BWRVIP-108 PLANT SPECIFIC APPLICABILITY CRITERIA Regulatory Guide 1.147, Revision 17 conditionally accepts the use of Code Case N-702 with the following condition "The applicability of Code Case N-702 must be shown by demonstrating that the criteria in Section 5.0 of NRC Safety Evaluation regarding BWRVIP-10S dated December 1S, 2007 (ML073600374) (Reference 7) "OR" Section 5.0 of NRC Safety Evaluation regarding BWRVIP-241 dated April 19, 2013 (ML13071A240)

(Reference S) are met.

For RBS the criteria of the BWRVIP-1 OSNP report contains the technical basis supporting American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-702 "Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds" for reducing the inspection of RPV nozzle-to-vessel shell welds and nozzle inner radii areas from 100 percent to 25 percent of the nozzles for each nozzle type during each 1 O-year interval at RBS. The evaluation found that failure probability due to a Low Temperature Overpressure event at the nozzle blend radius region and nozzle-to-vessel shell weld is very low (i.e. < 1 X 10-6 for 40 years) with or without inservice inspection. The report concludes that inspection of 25% of each nozzle type is technically justified.

Additionally, BWRVI P-241 provides supplemental analyses for BWR reactor pressure vessel (RPV) recirculation inlet and outlet nozzle-to-shell welds and nozzle inner radii that RBS also meets. BWRVIP-241 was submitted to address the limitations and conditions specified in the December 19, 2007, Safety Evaluation for the BWRVIP-10SNP report, "BWR Vessel and Internals Project, Technical Basis for the Reduction of Inspection Requirements for the Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii, but was not needed for RBS.

Based on the evaluation in BWRVIP-10SNP, the failure probabilities due to a low temperature over pressure (L TOP) event at the nozzle blend radius region and the nozzle-to-vessel shell welds for RBS recirculation outlet and inlet nozzles are very low and meet the NRC safety goal.

Section 5.0 of the NRC Safety Evaluation (SE) for BWRVIP-10SNP states:

Each licensee should demonstrate the plant-specific applicability of the BWRVI P-1 OS report to their units in the request for alternative by meeting the criteria discussed in Section 5 of the Safety Evaluation. RBS applicability was evaluated and demonstrated under RBS Calculation G 13.1S.1 0.1-019 Rev. 000 to support the Third Interval Request RBS-ISI-015 that was authorized in accordance with 10 CFR 50.55a(3)(i) and is still valid for this request. The plant specific parameters and assumptions used for the calculations and Criterion Evaluation in Table 2 are as follows:

RBG-47825 Page 3 of 6 Plant Specific Parameters The following parameters were utilized to demonstrate satisfaction of the plant-specific criterion for RBS:

RPV normal operating pressure, p = 1070 psia - 14.7 = 1055.3 psig RPV inner radius, r = 109.9375 in.

The RBS maximum heatup and cooldown rate is 100°F/Hour' Average longitudinal RPV wall thickness at N2, AvgLong = 6.2292 in Average transverse RPV wall thickness at N2, AvgTrans = 6.2917 in RPV wall thickness at Nozzle N2, t2 = 6.2605 in ((AvgLong +AvgTrans)/2)

RPV constant for inlet nozzle, CRPV2 = 19332 psi Nozzle outer radius for inlet nozzles, ro = 11.6875 in Nozzle inner radius for inlet nozzles, ri = 5.8125 in Nozzle constant for inlet nozzle, Cnozzle3 = 1637 psi Average longitudinal RPV wall thickness at N1, AvgLong = 6.2292 in Average transverse RPV wall thickness at N1, AvgTrans = 6.3229 in RPV wall thickness at Nozzle N1, t4 = 6.2761 in ((AvgLong +AvgTrans)/2)

RPV Constant for outlet nozzle, CRPV 4 = 16171 psi Nozzle outer radius for outlet nozzles, ro = 16.3125 in Nozzle inner radius for outlet nozzles, ri 9.016 in Nozzle constant for outlet nozzle, Cnozzle5 = 1977 psi Assumptions The following assumptions were made in developing the calculations that were utilized to demonstrate satisfaction of the plant-specific criterion for RBS.

The vessel inner radius is taken to be the maximum as-built dimension at location R3 because a larger inner radius is more conservative for this determination.

Location R3 was chosen because it is closer to the N 1 and N2 nozzles.

An average of the longitudinal and the transverse section is used for the RPV wall thickness at nozzle N1 and N2. Since these values are not as-built dimensions, the average of the nominal value, minimum tolerance, and maximum tolerance is used.

The maximum tolerance for the inner radius and the minimum tolerance for the outer radius were used for the N 1 and N2 nozzle radii because these values yield a larger number for Criteria 3 and 5 which is more conservative.

RBG-47825 Page 4 of 6 TABLE 2 Evaluation of RBS against Criterion 1, 2, 3, 4, and 5 contained in NRC SER for BWRVIP-108NP Criterion 1 Rate constant = 115°F/Hour Rate actual = 100°F/Hour 100°F/Hour < 115°F/Hour Criterion 1 is Met Recirculation Inlet Nozzles (N2)

Recirculation Outlet Nozzles (N1)

Criterion 2:

Criterion 4:

(pr/t)/CRPV<1.15 (pr/t)/CRPV < 1.15 P = RPV normal operating 1055.3 psi P = RPV normal operating 1055.3 psi pressure pressure r = RPV inner radius 109.9375 in r = RPV inner radius 109.9375 in t = RPV wall thickness 6.2605 in t = RPV wall thickness 6.276 in CRPV 19332 psi CRPV 16171 psi 0.959 < 1.15 1.143 < 1.15 Criterion 2 is Met Criterion 4 is Met Criterion 3:

Criterion 5:

[p(ro2 + ri2) / (ro2 - ri2)]/CNOZZLE < 1.15

[p(ro2 + ri2) / (ro2 - ri2)]/CNOZZLE < 1.59 P = RPV normal operating 1055.3 psi p = RPV normal operating 1055.3 psi

RBG-47825 Page 5 of 6 pressure ro = nozzle outer radius ri = nozzle inner radius CNOZZLE 1.068 < 1.15 11.6875 in 5.8125 in 1637 psi Criterion 3 is Met pressure ro = nozzle outer radius 16.3125 in ri = nozzle inner radius 9.0162 in CNOZZLE 1977 psi 1.003 < 1.15 Criterion 5 is Met In conclusion, based on meeting the criterion specified in the NRC condition (Le., use of BWRVIP-108) listed in Regulatory Guide 1.147, Revision 17, the content of this proposed alternative to use the ASME Code Case N-702 in lieu of the ASME Section XI requirements in the 2007 Edition with the 2008 Addenda is acceptable. Thus, RBS believes that this alternative provides an acceptable level of quality and safety in accordance with 10 CFR 50.55a(z)(1) for all applicable RPV Nozzle-to-Vessel welds and Nozzle inside Radius Sections identified in Table 1.

IV. Duration of the Proposed Alternative The analyses in BWRVIP-108 is based on the assumption that fluence at the nozzles is negligible and a number of heatup and cooldown cycles that represent the initial 40 years of plant operation and does not address a possible increase fluence or operating cycles for the extended operating period. Based on this analysis assumption and upon authorization by NRC, this request will be utilized during the RBS Fourth 10-Year lSI Interval beginning on December 1, 2017 to the end of the current operating license NFP-47, which will be at midnight on August 29, 2025.

V. Precedents

1. LaSalle County Station, Units 1 and 2, Relief from the requirements of the ASME Code RE: RR13R14, Proposed Alternative to the examination requirements for Nozzle-to-Vessel Welds and Inner Radii Sections in Accordance with 10 CFR 50.55a(z)(1) - NRC SE for Use of Code Case N-702 - Dated: October 30, 2015, (TAC NOS MF5654 and MF5655) and (ADAMS Accession No. ML15226A412).
2. Columbia Generating Station - Request for Alternative 31SI-14 to the requirements of the ASME Code - NRC SE for Use of Code Case N-702-Dated: February 13, 2015, (TAC NO. MF3435) and (ADAMS Accession No. ML15036A220).

RBG-47825 Page 6 of 6

3. River Bend Station, Unit 1 - RBS-ISI-15 Proposed Alternative to 10 CFR 50.55a Examination Requirements for Reactor Pressure Vessel Weld Inspections - NRC SE for Use of Code Case N-702 - Dated: August 2, 2010, (TAC NO. ME2817) and

[ADAMS Accession No. ML101440097]

VI. References

1. ASME Code,Section XI, 2007 Edition with the 2008 Addenda
2. USNRC Regulatory Guide 1.147 Revision 17, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Dated August 2014
3. ASME Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR)

Nozzle Inner Radius and Nozzle-to-Shell Welds,Section XI, Division 1, Dated:

February 20, 2004

4. BWRVIP-108 "Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," EPRI Technical Report 1003557, October 2002 (ADAMS Accession No. ML-023330203)
5. BWRVIP-241 "Probabilistic Fracture Mechanics Evaluation for the Boling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii," EPRI Technical Report 1021005, October 2010 (ADAMS Accession No. ML11119A041)
6. Section 5.0 of NRC Safety Evaluation regarding BWRVI P-1 08 dated December 18, 2007 (ADAMS Accession No. ML073600374)
7. Section 5.0 of NRC Safety Evaluation regarding BWRVIP-241 dated April 19, 2013 (ML13071A240) Section 5.0 of NRC Safety Evaluation regarding BWRVIP-241 dated April 19, 2013 (ADAMS Accession No. ADAMS Accession No. ML13071A240)
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