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10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals
	ML13059A315
Person / Time
Site:	Davis Besse
Issue date:	02/27/2013
From:	Lieb R; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	L-13-076
	Download: ML13059A315 (66)
	v • d • e

FENOCTM

---

RfSlEnergy Nudear Operating Company 5501 Norlh Slate Route 2 Oak Harbor. Ohio 43449 Raymond A Ueb 419-321-7676 Vice President, Nuclear Fax: 419-321-7582 February 27, 2013 L-13-076 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington; DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals In accordanceWHh 10 CFR 50.55a, FlrstEnergy Nuclear Operating Company (FENOC) is requesting Nuclear Regulatory Commission (NRC)approvaJ for three proposed; alternatives to certain American Society of Mechanical Engineers Code requirements for the Davis-Besse Nuclear Power Station. Enclosures A through C identify the affected components, applicable code' requirements, reasons for the requests, proposed alternatives, basis for their use., and durations. Enclosure 0 Is a, notification of impracticality related to weld examinations where the required examination coverage of "essentially 100' percent" was not achieved.

The proposed alternatives would be implemented in support of the to-year inserviC8 inspection intervals cited in the individlJal requests. Request RR-A37 requires implementation prior to September2Q, 2013. Requests RR:-A1 and RR..B1 would be implemented In support ofthe winter 2014 refueling outage, which is currently scheduled to begin in February 2014. Therefore, FENOe Is requesting NR.C approval of the alternatives as follows: .

o Request RR-A1 by February 28,. 2014 o Request RR-A37 by September 18,2013 o Request RR-B1by February 28, 2014 The notification of impracticality, Request RR-A36, is in support ofthe third to.;year inservice inspection interval, which expired on September 20, 201.2.

Davis-Besse Nuclear Power Station L-13-076 Page 2 of2 There are no regulatory commitments contained in this submittal. If there are any questions or additional 'information is required; please contact Mr. Thomas A. Lentz, Manager-:- Fleet licenSing, at (330) 315-6810.

st:dCf-!/

Raymond A. Ueb '

Enclosures:

A. Davis-Besse Nuclear Power Station, 10 CFR 50;55a Request RR*A1 B. Davis-Besse Nuclear Power Station, 10 CFR 50 . 55a Request RR-A37 C, Davis~Besse Nuclear Power Station, 10 CFR 50.S5a Request RR-B1 D. Davis-Besse Nuclear Power Station, 10 CFR 50.55a Request RR-A36 cc: NRC ,Regioh III Administrator NRC Resident Inspector NRC Project Manager Utility RadlQlogical Safety Board

Davis-Besse Nuclear Power Station 10 CFR 50.55a Request RR-A 1 Page 1 of4 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety--

1. American Society of Mechanical Engineers (ASME) Code Components Affected Components: Not Applicable Code Class: Class 1, 2, 3, and MC Examination Category: Not Applicable Code Item Number: Not Applicable

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2007 Edition through 2008 Addenda.

3. Applicable Code Requirements ASME Section XI contains the following requirements regarding the use of Form NIS-1, Form NIS-2, and the preservice and inservice inspection summary reports:

IWA-4331(d) Form NIS-2 shall be completed for rerating, except for rerating component supports.

IWA-6210(c) The Owner shall prepare preservice and inservice inspection summary reports for Class 1 and 2 pressure retaining components and their supports.

IWA-6210(d) The Owner shall prepare the Owner's Report for Inservice Inspections, Form NIS-1, for preservice and inservice examination of Class 1 and 2 pressure retaining components and their supports.

IWA-6210(e) The Owner shall prepare the Owner's Report for Repair/Replacement Activity, Form NIS-2, upon completion of all required activities associated with the Repair/Replacement Plan.

IWA-6210(f) The Owner shall submit Forms NIS-1 and NIS-2 to the Inspector and obtain the required signatures.

IWA-6220 The abstract shall include a list or table of examinations and tests containing the following:

a. component examined or tested

b. Code Class

c. Code Examination Category and Item No.

d. examination or test method

e. Code Cases

f. number and percentage of examinations completed when required by IWB-2411, IWC-2411, and IWF-2410

Request RR-A1 Page 2 of4

g. reference to the abstracts of the conditions noted and the corrective actions recommended and taken for flaws detected during examinations or tests performed.

IWA-6230(b) An in service inspection summary report to be prepared following each refueling outage. Examinations, tests, and repair/replacement activities conducted since the preceding summary report shall be included.

IWA-6230(c)(2) references [Mandatory] Appendix II for Form NIS-1.

IWA-6230(c)(3) references [Mandatory] Appendix II for Form NIS-2.

IWA-6230(d) Summary reports shall have a cover sheet providing the following:

1. date of document completion

2. name and address of Owner

3. name and address of plant

4. name or number designation of the unit

5. commercial service date for the unit IWA-6240(b) The inservice inspection summary report shall be submitted within 90 calendar days of the completion of each refueling outage.

IWA-6350(d) requires that Form NIS-2 Form be retained as a record of repair/replacement activities.

Mandatory Appendix II includes both Forms NIS-1 and NIS-2. Also included in the Appendix is the guide for completing both forms.

Mandatory Appendix IX, Article IX-1000(e) Welding shall be documented on an NIS-2 Form.

4. Reason for Request

Code Case N-532-4, which is applicable to ASME Section XI, 1981 Edition with Winter 1983 Addenda through the 2004 Edition with 2005 Addenda, was approved for use in Regulatory Guide 1.147 Revision 16. Per IWA-2441 (b), Code Cases shall be applicable to the ASME Code edition and addenda specified in the inspection plan.

The current inspection plan, which commenced on September 21,2012, specifies ASME Section XI, 2007 Edition through 2008 Addenda as the applicable ASME Code edition and addenda. Therefore, Code Case N-532-4 is not applicable.

5. Proposed Alternative and Basis for Use Proposed Alternative:

In lieu of ASME Section XI requirements, FirstEnergy Nuclear Operating Company (FENOC) requests the use of Code Case N-532-5, as permitted by 10 CFR50 55a(a)(3)(i), in lieu of applicable Code requirements.

Basis for Use:

Code Case N-532-4 was approved for use in Regulatory Guide 1.147, Revision 16.

However, the applicability of Code Case N-532-4 does not extend to ASME Section XI, 2007 Edition through 2008 Addenda.

Request RR-A 1 Page 3 of4 Code Case N-532-5 was published in the 2010 Edition of the Nuclear Code Case Book, Supplement 5, and is applicable through the 2010 Edition of the ASME Code, which includes ASME Section XI, 2007 Edition through 2008 Addenda.

FENOC requests the use of Code Case N-532-5 as a proposed alternative to all cases where completion of Form NIS-1, Form NIS-2, or a preservice and/or inservice inspection summary report is required in ASME Section XI, 2007 Edition through 2008 Addenda, or any other applied Code Cases. Code Case N-352-5 is considered an acceptable alternative to applicable Code requirements based upon the following:

1. The ASME Code requirements of Code Case N-532-4 were not reduced; rather, they were clarified and/or enhanced in Code Case N-532-5.

2. In addition to repair/replacement activities, Code Case N-532-5 includes rerating; Code Case N-352-4 did not include this activity.

3. Code Case N-532-5 added the requirement that Form NIS-2A shall be completed after satisfying all Section XI requirements necessary to place the item in service and prior to inclusion in an Owners Activity Report; Code Case N-352-4 did not include this requirement.

4. Code Case N-532-5, Form NIS-2A and Form OAR-1, were revised to clarify that when listing Code Cases used, the requirement is for "repair/ replacement activities" and "inspection and evaluation," respectively; the forms associated with Code Case N-532-4 did not include this clarification.

6. Duration of Proposed Alternative:

The proposed alternative shall be used during the fourth 10-year inservice inspection interval, which commenced on September 21, 2012. The use of this Code Case is requested until the Nuclear Regulatory Commission (NRC) publishes the Code Case In a future revision of the applicable Regulatory Guide.

7. Precedent The NRC approved a similar request, submitted as Relief Request RR-2, for the Point Beach Nuclear Plant, Units 1 and 2.

NRC letter to NextEra Energy Point Beach, LLC,

Subject:

Point Beach Nuclear Plant, Units 1 and 2 - Evaluation of Relief Requests RR-2 and RR-3 (TAC Nos.

ME7974 and ME7975), November 15, 2012. [Accession No. ML12286A104]

Request RR-A1 Page 4 of4

-'. '

8. References 1.' ASME Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation arid Submission,"

April 19, 2006. '

2.' ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission,"

January 11, 2011.

3. NRC Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision'16, October 2010.

4. 10 CFR 50.55a, "Codes and standards," July 21,2011.

Davis-Besse Nuclear Power Station 10 CFR 50.55a Request RR-A37 Page 1 of 5 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)

--Hardship or Unusual Difficulty without Compensating Increase in level of Quality and Safety--

1. American Society of Mechanical Engineers (ASME) Code Components Affected Components: Reactor Coolant System Cold leg Drain Line 1-2 Dissimilar Metal Weld Overlay Code Class: Class 1 Examination Code Case N-770-1 Category:

Code Item Number: Inspection Item "F" Weld Number Description Size Materials1 RC-40-CCA-18-3-FW9 Cold leg 1-2 Nominal Carbon Steel Nozzle I Alloy Drain Nozzle 2% 82-182 Weld I Stainless To Pipe inch 102 Steel Elbow I Alloy 52M Weld Overlay 1Carbon Steel Nozzle: SA-105 Grade 2 (P-1) internally clad with SA-371 ER 308l stainless steel; Stainless Steel Elbow: SA-403 WP 316 (P-8) 210 Inside Diameter

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1995 Edition through 1996 Addenda.

3. Applicable Code Requirement

Table 1, Inspection Item F of ASME Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities," with the following conditions:

10 CFR 50.55a(g)(6)(ii)(F)(1) Licensees of existing operating pressurized-water reactors as of July 21, 2011 shall implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(10) of this section, by the first refueling outage after August 22, 2011.

10 CFR 50.55a(g)(6)(ii)(F)(4) The axial examination coverage requirements of

-2500(c) may not be considered to be satisfied unless essentially 100 percent coverage is achieved.

Request RR-A37 Page 2 of 5

4. Reason for Request

Code Case N-770-1, with the condition stated in 10 CFR 50.55a(g)(6)(ii)(F)(4), requires an examination coverage of essentially 100 percent. For Weld RC-40-CCA-18-3-FW9, this coverage requirement was not achieved during the initial inservice examination.

Details:

FENOC's Request RR-A33 for the application of full structural weld overlays (FSWOl) on dissimilar metal welds of the reactor coolant piping was approved by the NRC on January 21, 2010 [Accession No. Ml100080573]. Request RR-A33 included the following discussion and figure:

Reactor Coolant System Cold Leg Drain Line Dissimilar Metal Welds The reactor coolant pump inlet (RCP) lines have a drain connection at the low point of the line. Each cold leg drain nozzle is a vertical 2 % inch carbon steel nozzle that is welded to the carbon steel reactor coolant piping, and is internally clad with stainless steel. The dissimilar metal weld is fabricated from .

Alloy 82/182 weld metal.

Weld Overlay LAS Nozzle EI~

.SS CladdIng:

Notes:

1. Elbow - SA403, Grade WP316

2. Carbon Steel Nozzle -A105, Grade 2, internally clad with SA371 ER308l Figure 5-4: Schematic Configuration for FSWOl for RCP Cold leg Drain line Nozzles As authorized by Request RR-A33, FENOC applied a full structural Alloy 52M weld overlay on dissimilar metal weld RC-40-CCA-18-3-FW9 during the spring 2010 refueling outage.

Code Case N-770-1, -2500(a) states welds shall be examined as specified in Table 1, with the volumetric examinations meeting the requirements of Appendix VIII. Per Table 1, Inspection Item F, Figure 2 provides the examination requirements.

Figure 2(a) from the Code Case is provided below:

Request RR-A37 Page 30f5 FIG. 2(a) EXAMINATION VOLUME IN FUll STRUCTURAL WELD OVERLAYS Minimum '/2 In. (13 mm) Mlnrmum 'IJln, 113 mm) (Note 4111

~~+dD* *IlF~T r .

__~~~~~~_1 Examination Volume A-B-C-D GENERAL NOTE: The weld Includes the nozzle or safe end butter, where applied.

NOTE:

(1) For axial and circumferential flaws, the axial extent of the examination volume shall extend at least % Inch beyond the as found flaw and at least % Inch beyond the toes of the original weld, Including weld end butter, where applied, plus any PWSCC-susceptible base material in the nozzle and safe-end.

In accordance with Code Case N-770-1, Table 1, Inspection Item F, an initial inservice volumetric examination was completed during the spring 2012 refueling outage, which

resulted in approximately 70 percent total aggregate coverage. As stated in the condition of 10 CFR 50.55a(g)(6)(ii)(F)(4), essentially 100 percent coverage is required; this examination coverage requirement was not achieved due to limitations imposed by the weld geometry. An image of the FSWOL is provided as Attachment 1 to this request. Details of the examination limitations are presented in Attachment 2 to this request. This request is processed in accordance with 10 CFR 50.55a(a)(3)(ii), as discussed in the J.*W. Collins' memo to T. R. Lupoid, which summarized a public meeting on Code Case N-770-1 (Reference 1).

ASME Code Case N-460 (Reference 2) best describes the "essentially 100 percent" examination requirement as when the entire examination volume cannot be examined due to interference by another component or part geometry, a reduction in examination coverage may be accepted provided the reduction in coverage for that weld is less than 10 percent. ASME Code Case N-460 is unconditionally approved for use in the NRC's Regulatory Guide 1.147; Revision 16 (Reference 3).

Request RR-A37 Page 4 of 5

5. Proposed Alternative and Basis for Use Alternative Examination:

In lieu of the essentially 100 percent coverage requirement, FENOC proposes crediting the aggregate coverage achieved (approximately 70 percent) from the spring 2012 examination. The accessible area was examined with techniques that have been demonstrated and qualified in accordance with Supplement 11 of ASME Section XI, Appendix VIII, for the manual phased array (PA) ultrasonic (UT) examination technique.

Basis for Use:

Code Case N-770-1 and 10 CFR 50.55a(g)(6)(ii)(F)(4) define the required examination volume as essentially 100 percent coverage. The initial inservice examination was completed during the spring 2012 refueling outage. The essentially 100 percent coverage requirement was unattainable due to limitations imposed by the existing nozzle to elbow geometry. Due to these limitations, only 70 percent of the required examination volume was examined with the PA UT technique, which was qualified in accordance with Supplement 11 of ASME Section XI, Appendix XIII. The 70 percent aggregate coverage achieved, which consists of 69 percent axial and 71 percent*

circumferential composite coverage values, represents the maximum practical coverage obtainable within the limitations imposed by the existing geometry. As noted in Attachment 2 to this request, there were no recordable indications identified in this weld that exceeded the acceptance criteria of ASME Section XI. Additionally, a visual VT-2 examination was performed on this weld during the Class 1 pressure test prior to startup from the spring 2012 refueling outage. This visual examination identified no evidence of leakage.

Due to the limitations imposed by the existing nozzle to elbow geometry, similar examination coverage results occurred during the initial 201 0 examinations; no suspected flaws were observed during those examinations.

Due to the configuration/geometry of this nozzle to elbow weld, achieving essentially 100 percent coverage of the examination volume is unattainable without a significant modification to the existing piping. Implementing this type of modification would require a core offload, flushing and draining of the system, and removing/replacing the existing piping with reconfigured piping. Based on radiological survey results from the spring 2012 refueling outage, this work would occur within radiation fields with dose rates up to 500 milli-Rem per hour, resulting in a significant increase in occupational radiation exposure [dose] to personnel.

An image of the FSWOL is provided as Attachment 1 to this request. Details of the examination results, including examination limitations, are presented In Attachment 2 to this request.

Request RR-A37 Page 50f5

6. Duration of Proposed Alternative The proposed alternative shall be utilized for the third 10-year inservice inspection interval, which was scheduled to expire on September 20, 2012. As permitted by IWA-2430(d), the third 10-year inservice inspection interval is extended by one year until September 20, 2013, to allow for NRC review and authorization of the proposed alternative prior to crediting the examination.

7. Precedent Constellation Energy letter to NRC,

Subject:

"Calvert Cliffs Nuclear Power Plant, Unit No.1, Docket No. 50-317, Relief Request for Unit 1 Dissimilar Metal Butt*Welds Baseline (RR-ISI-04-06A)," February 9,2012. [Accession No. ML12044A020]

8. References

1. NRC memorandum, J. W. Collins to T. R. Lupoid,

Subject:

"Summary of Public Meeting Between the Nuclear Regulatory Commission Staff and Industry Representatives on Implementation of Code Case N-770-01," August 12, 2011.

[Accession No. ML112240818]

2. ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds," July 27, 1988. .

3. NRC Regulatory Guide 1.147, "Inservice Inspection Code Case Applicability, ASME Section XI, Division 1," Revision 16, October 2010.

Attachment 1 Request RR-A37 Page 1 of 1 Image of Completed Full Structural Weld Overlay (FSWOL)

[Weld RC-40-CCA-18-3-FW9]

Attachment 2, Request RR-A37 Page 1 of21 Report No.: FW9-SWOL A UT Examination Summary ComponentlD: RC-40-CCA-18-3-FW9 OVERLAY AREVA Summary No.: 809.050.010265 Customer: First Energy Code Category: N/A System: 064*02 (RCS)

Site I Unit: Davis Besse 11 Co do Item: N/A Material: CS I SS Iinconel Outage: 1R17 Coda Class: 1 Configuration: 2.5 Inch Branch Connection to Elbow Weld. MK 9 Drawlng(s): ISIM2-240A, Revision 3 Prol;edure: 54-9077864, Rev. 001 , 54-ISI-864-003 Procedure for Manual Phased Array Ultrasonic Exail1ln~"on of Weld Overlaid Similar and Dlsslmlla.r Metal Welds (64-9077864, Rev. 001-1 EPRI-WOL-PA-1, Rev, 2, 09/17/2009)

Title:

Manual Phased Array Ultrasonic Examination of Weld Overiald'Simllar and Dissimilar Metal Welds (64-ISI-664-003)

Callb;atlon*Sheeta Exam Data Shiata ,Indication DataSheota Supplemental She'eta COS-01(Pages 1-3) EOS-01 N/A CFV-01 CFV-D2 CDS-02 (Pages 1-3) N/A N/A CFV-03 CFV-04 CDS.()3.(Pages 1';3) N/A N/A COV-01 COV-D2 CDS-04*(Pages 1-3) N/A N/A COV-03 N/A Ex.m :Ra.ulta: No Recordable Indications EXa.m Volume Coverage.Obtalned: I 70%

Amanual.lSI phas'ed array ultrasonl~ exam.\natlon of the full structural wfitld Qvetlay QnRC-40*CCA-18-3-FW9 (0Qldleg Drain '1-2) was peiformed duri!19 the:Oavls Besse 1.R17 refueling outagEt. .

The examination ,volume coverage obtaln$d fot this ,full structural weld-overlay Is'doQum$nted on the Coverag$ Data Sheetaln lhlsreportwhlch Is derived from a compilation of thickness and contours taken during this omega and previous dataoblalned during the 1R10'outage.

UTexamlnatlOn Qf the lSI volume was pedotmed using ASME Section XI. Appendix VIII. Supplement 11 qualified procedures, personnel and equipment as amended by the Final Rule; this UT Insp8ctlonsatisfles the* full structural* weld overlay examlnatlon-requirements,of ASME Code CsSe N:-77G-1.

Total, Dosel 32 mR Personnel Name Signature Level Dilte Prepared By: TtoyStelnbauer ~~ /

III 05-16~12

,-~

AREVA Review: Dan Langenfeld 'A ..... ~4~g III 05-15-12 Customer: t).mV~~ ~tf"// ;ar. stzt/hl.

ANII: To (..I\P5 ~~'M -'t,~-,-" ~ $"/24-1,)"

Form Edition: Nov 2011 1 Rev 0 --U Page: 1 0' 21

Attachment 2, Request RR-A37 Page 20f21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA Customor: Flrsi Energy Procedure: 54-9077864 I 54-181-864 Report No.: FW9-SWOl Site: Oaliis Besse, Unit 1 Revision: 001/003 Calibration Sheet No.: CDS-01 (Page 1 of 3)

Outage: 1R17 SOCN:N/A Component 10: RC-40-0CA-18-3-FW9 Overlay focal Law: 72-1.5.LAW INSTRUMeNT INFORMATION SEARCH UNIT INFORMATION CALIBRATION INFORMATION Manufacturer: Zetec Manufacturer: GEIT CliI; Block.IO: 6D39024 Model: OmnlScanMX ModEll: 115*000-485 Cel. Blollk Material: 3048S Serial Number: OMNI*1635 Serial Number: 01PBN8 Cal. Block Reflector: 8eeBeiow

'Software Rev. 1.4R3 Frequency: 2.0 MHz Cal. Reflector Size: 0.090" Frequency: 2.0 MHz CO!1f1gural!on! Dual-SBS Cal, Reflector Depth: See Below PRF: Optimum Numbar of Elementa: 32 Cal. UT Roadll'lg: See'Below ReJact: 0% Element Arrangement: 2x16 Cal. Gain Level: Se8Beiow Angles Generated: 0*- 80* (1" Inc.) Element Shape: Reclangular Cal. Block Temp.: 73° Setup File: 072-1.5 Transducer Size: 1.75x4.00mm Thermometer Serial No.: VH-11842 Delay: 0:08psec t# Eleml;IOls at Cal In: 32 InlllalOal. Dalemme: 5*15*2012/1037 Range: :a,908"@OO t# Elemente at Cal Outl 32 Oal.V8r1f1caUO"n Blbcle 10: N/A WEDGE! INFORMATION Cable Type: Inlegtal cal VerifloaUon RellEleilor: N/A Manufacturer: GEIT Cable '-'ngth: S'Meters Cill Verlna"tlori UTReadl"g~ NIA Part Number: 36D-~52-072 Adaptor Box: Omnl*A-AOP03 Cal VerlnaaOon Gain Level: N/A M~de: longitudinal Cable Adapter Model: NIA Final Cal. Date/TIme: 05116/12/1047 Nom. Angle:- 42' Intermediate Oonnectors: 0 Couplant'Type: Ullragslll Measured Anele: 42' , Channelalnoperlitlve 0/0 Couplant Bat!;h Number: 0932(j Nomlnai Exit PoInt:" -0.747" WEDGE INP-ORMAnON (Cont.) Exam Start; 1038 Me88ured Exit PoInt:; -0.85" ElIlt :polnt to wedge backe 'CUS" Ex,mEndi 1045 Wedge Contour: .6.000" Ndte:, Till 70**MaIe Is peak amplitude for the .108~ *SDH.. The highest angle that can dltaClly Impl'l9S on .19B" SDI-! Is ~7*. Gain Level Is set using tile '70' allO!' 8S raqulred ~ prOC1Qdl!re.

Wedge Orlentatlon: eire Notes: $el Eellen~1I1 Variables UT Calibration Oala SlIeets for' additional calibration Information; High Range Angle Mid ~rig8 Angte LoW Rilnge Angla Functlon Oh,ck and Report file Name (70**86*) (26"- 80') (0"- 26*)

Angle 70',(67°1 40' O* Pre WIWedgu: 072*PRE*W Reflector Depth 0.t9a" SOH .8011" SOH U"SDH Pre WOI Wedgel 072*PRE*WO UT Reading (NIP) 0.947" (.92"' 1.S7" 1.27" Post W I Wedge: 072*PST*W Amplitude' 80%FSH 80%FSH 80%FSH Post WOI Wedga: 072-PST-W Gain Level 36.4 dB 25.4 dB 24.8 dB N/A Examiner: Troy A. Slelnbauer Levell III Reviewer: Dan langerifel~ Level: III A~/

~

slgnature~ ~ Date: 06/16112 Signature: ~~ AI Date: 05115/12 Utlllty'Rovlew: 17?

.~~

ANIIRevlew:

Signature:

Date: I stPlJ,I'l.. Signature: -r.~ A-Al.tt Date: £Ic14( a~

\1 Page 2 ot 21

Attachment 2, Request RR-A37 Page 30f21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES)

Customer: First Energy Procedure: 54*90778641 54*ISI*864 Report No.: FW9*SWOl Slle: Davis Besse, Unit 1 Revlalon: 001 I 003 Calibration Sheet No.: CDS*01 (Page 2 of 3)

Outago: 1R17 SDCN: N/A Component ID: RC-40*CCA.18*3*FW9 Overlay Focal LaW: 72*1.5LAW Major Menu Item Manullem Sub*Menu Item Setting Reading Resull Selector 1 Reading Resull Field 1 A%

Reading Resull Field 2 A" Reading Resull Field 3 SA" Reading Reaull Field" PAA UT PUlser PulSet Imported ftom .LAW file UT Pulser Tx/RlCmode Impprted from .LAW file UT Beam Gain offsel Imported ffom .LAW rde UT Beam Angle Imported from .lAW file UT Beam BsamDeliiy Imported'from .LAW file UT AdVance!! 'd~'reference 0;'

UT AdVanced PolntaQty (Scale Factoi) 8 UT AdVanced SUII)~aln ImJ!(lrted flom .LAW file Dlaplay SelliCUilri Display A-S'lC)

Display SeI8CUon ~n1 Off DIsplay SelecHlln Group Curren1 DISplay SelecUon Projection On Dlspiay RUlerll UTU!llt TNeDepth DlaPlay Rlilers ~.Ruler tlnear ("4)'

Dlaplay Rulers DACITGC .Off Display Rulera Gale On Display Rulers Cursor Off Display Color Select AmpIqude Display Color 518".% O.Q Displa), Color End % 100 Plspiay ProperUes Display A-scan DISplay ProperUas 'Soutee Normal ProbelPaIt SeJecl Select Selecl Tl!IRx Probe/Pall Saillel AlilODeleel Off Probe/Part PoalHon scan Offael Ii Examiner: Troy A. Stelnb~ Level: III _ewer: Dan lang.nfe/~ Level: "I Signatu~ Date: 05/16/12 Signature: APMI ~ Date: 05/15/12 Utility Review: \).M\lN,&~ ANII Review:

~ -~ Date: Sh1/1t... \..~. A-~ Date~.Jr'-

Signature: Signature:

,

" PQge 3 'Of 21

Attachment 2, Request RR-A37 Page 4 of21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VA~IABLES)

Cuelomor: FlralEnergy Proceduro:54*90778641 54.151*864 Roport No.: fWg*5WOL Site: Davis Besse. Unit 1 Revlelon: 0011 003 Calibration Shoet No.: CD8*01 (Page 3 of 3) autago: 1R17 SDCN:NiA Componant ID: RC*40*CCA*18*3*FW9 OVerlay Focal Law: 72*1.5LAW Major Menu 110m Manu 110m Sub*Manu Item SaltIng Probe/PoIt Position Indl)x Offset. o Probe/Part Parts* Geomell)' PI!\te Probe/Part Paris Thlcknesa 10.000 PGMProbe ConfigilraUon SOCIorisl PGMProbe COilliguraUon Connecuon P:

PGMProbe Laws Auto Program Off Gate I AI~lfm OtIte . Gale setect GaleA Gale/Alann Gale Gale A SyIlCluq Pulse UT General Gain Sea Calibration Sheet UT General Slert 0.000 UT General See CaQbta1lOn Sheet iJT General Sea CalibrQUonShtet (peley) ur Geileial Imported frorri.LAWfil8 (;2272)

UT ~ulaer Flag UT Pula81 Voltage ut Pulset UT PuI88l *PRF 'Opllmum U1". Flliar ur ReceIver Rectiliet FW ur ReciI!lver ur .Receiver UT Reject o UT Beam bOWsel Imported trom .tAW*flle*

ur Beil.m Imported (rom',tAWiua UT .Skew Imporled*from* *.tAWrda Examiner: Troy A. Steinbauer Level: III Reviewer: Oanlangenfeld ""AI Level:.1II Signature:~ ~-=----~. ~-~;;;;;--~_.-'_-I-~~te~:~O~5~/1~611~2~kSI~g~na=-tu_re-:-:_A~_'IIH_. _"L-

_:Z;_.' .T-J..-~~refII'_~~~~!:!~~

4' V Dale:, 06/151.* 2 Utility ReView: b~.(V\II"'~dN

..."""\ ANII Review! ~ll Signature:

Date: I II.

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Page 4 of 2~

Attachment 2. Request RR-A37 Page 50f21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA Customor: First Energy Procedure: 54*90778641 54*181*864 Report No.: FW9*SWOL Slto: Oavl8Bes80. Unit 1 Revlelon: 001/003 Calibration Sheet No.: C08*02 (Page 1 of 3)

Outege: lR17 SOCN:NlA Component 10: RC*40*CCA.18*3*FW9 Overlay Focal Law: 72*1.125.LAW iNSTRUMeNT'lNFORMATION SEAROH UNIT INFORMATION OAIdBRATION;INFORMATION Manufacturer: Zetec Manufaoturer: GEIT Cal. Blook 10: 8039024 Model: OmnlScanMX Model: 115*000*485 Cal. Blook Material: 3165S Serial Number: OMNI*1635 8erlal Number: 01PBN8 Cill; Block Reflector: SeeDlililw Software Rev. 1.4R3 Frequency: 2.0 MHz Cal. Reflector SIze: 0.090' Frequency: 2.0 MHz Configuration: Oual-SDS Cal. RDflector Depth: See Below

'PRF: Optimum Number of Elementa: 32 Cal. UT Reading: See Below Reject: 0% Element Arrangement: 21(16 Cal. Gain Level: See Below Anglea,Generated: 0** 80* (1* Inc.) Elelhent Shape: Rectangular Cal. Block Temp.: 74° Setup File: 072*1.126 Transducer Size: 1.75X 4.00 mm Thatmomater Sarlal No.: VH,11842 Delay: 1.SlJsec II Elements at Cal In: 32 Inlllal Cal. Datumme: 5*15-2012/1022 Range: 2.908"@OO tI Eilements at Cal out: 32 Cal. Verification Block io: NlA

'WEiDGE:INFORMATtaN OlibleType: Integral ' Cal Vlrlflcatlon Reflector:' NIA Manufacturer: GEIT Cable Lenglh: 5 Meter8 Cai Verification UT 'Readlng: NlA Part NumbGl': 360-162-072 Adaptor Box: OmIiI-A-ADP03 ClilVertftcaUon Gain Level:, N/A Mode: Longitudinal Cable Adapter Model: N/A Final Cal; Dateinme: 0511611211031 Nom. Angle: 42* Il'Itermedlate Connectorsl 0 Couplant Type: Ullragelll MeaaurodAngle: 42" tJ ChannelslnoperaUve 0/0 CouplantBatch NUmbGr: 09320 Nominal ExitPolnl: ..0.747" WBOOE'INFORMATlON,(COlit,) ElClim Start: 1024 Measured'Exlt Point: *0.7" Exit point to wedge back: 0.7" 'ExemEnd: 1031 Wedge Contour: 5;000" Note: Tha 70* Angle Is peak'amplltuda for tite,O.19&~SDH, the hlgheatangla that can dlraclly Impinge on 0.198" SDHls 67*. Gain Level 18 set ualng.'he 70* angle as rsqulred by procedure.

Wedge Orientation: Clre Notes: See essential Variables UT Oallbratlon* Data Sheets for addlllonal cailbratlon Informallon.

High Range Angla Mid Range Angle Low Range Angle Functlon'Check,and Report File Name (70** 86°) 126*~GO*) JO** 26*)

Anala 70' (67") 40* O* Pre W IWedgel 072*PRE*W ReDactor Depth 0.198" SOH 0.598" SOH 598'" SOH Pro wot Wedge: 072*PRE*WO UT Readlna (MP) 0.910' ( .83") o.e* 0.605" Post W I Wedge: 072*PST-W Amplituda 8O%FSH 8O%FSH 80%FSH Post wal Wedge: 072*PST*WO Gain Level 33;8 dB 24.9 dB 28.3 dB NlA Examiner: Troy A. Steinbauer Leval: III Reviewer: Dan L8ngen~ Level: III Signature: ~ -----=- Date: OSn 5/12 Signaturel,/)~ IN/. ~A. L . ... Date: 05115/12 Utility Rfilew:

D~J ANIIRevlew: ",

Signature: Date: 5121/),1.. Signature: T.h A~n: oal~I!}.4-L~

'1 Page 5 ' of

21

Attachment 2, Request RR-A37 Page 6 of21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES, Customer: First Energy Proceduro:' 64-90778641 64-151*864 Report No.: FWD*SWOl Site: Davis Bosse, Unit 1 Rovlslon: 001 1003 Calibration Sheot No.: CDS*02 (Page 2 of 3)

Outage! tRt7 SDCN: N/A Component 10: RC*40*PCA-t8"3*FW!l Overlay Focal Law: 72-1.t26LAW Major Menu Item Monultem Sub*Menu Itom Setting Reading Rosult Selector 1 Reading Resull Flekl1 A%

Reading Rasull Field 2 A" Reading Result Field 3 SA" Readlno Result Field 4 PAlo ur Pulser Pulse, Imported from .lAW Nil ur Pulser TxlRxmode Imported from .lAW ftle UT Beam GalnoflBet Imparted from .lAW filii UT Beam Angle ImP,Orted 110m .lAW fde ur Beam 8eamDeIay Importedfrom.lAW nre ur AdVanQed dB reference *0';

ur Advanced Points QIy (scale FIiCIol') 6 ur Advanced Sum Gain l,"por1~rrom ..I:AW ~Ie OIspI"y Selection DISplay Aos,ICI*

Display 8eIecIIon C-Scan 1 Off Display SeteciJon Group Currant Dlajltay SekicIIon' PrOjection '0" Dlaplay Ru1er8 UTUnll TrueDeplh Dlaplay Rulers % Ruler L/ilelir'('III)

DlaplllY Rulelil DAclTGC oir Display Ruiara Gate Oil Display Rulers c~rr8or Off Dlaplay Color Select Ainplitllde DIsplay Color Slart% 0.0 DIsplay Color EiId% 100 Display Prop""es Display A*Scan Display PRlpartial Source Normal ProbelPart Select Select S,!lect 'tXlRx PRlbelParl Selecl AuloDelaci Off PRlbeJPa" Position $canOlfset 0 Examiner: Troy A. Steinbauer Level: III _ _: OanUmgenf~ Level:. III

~~ ~

Signature:~, ~~

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Utility Review:

- -

~.mll"'>>1 Date: 05/16/12 5P,"/1t-Signature:

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Date: 06/15112

,,12.4-",..

Sinnalure: CWtl- ~ Date: Signature: --"h~ \I

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,

Page 6 of 21

Attachment 2. Request RR-A37 Page 7 of 21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIASLES, Cuatqmer: First Energy Procedure: 64*9077864 154*ISI*864 Report No.: FW9*SWOL Slle: Davis Besse. Unit 1 Revision: 001 I 003 Calibration Sheet No.: C08*02 (Page 3 of 3)

Outage: 1R17 SOeN: N/A ComponenllO: RC*40*CCA*18-3*FW9 Overlay Focal Law: 72*1.125LAW Major Menu lIem Menu Item Sub-Menu Item SeHlng Probe/Part POSition IndexOHsel 0:

Probe/Part P,arts Geomelly Plllie Probe/Part Parts Tlilckness 10.000 POMProbe Conllgurallon Scan Type Sedorial PGMProbe Configuration Connection P: 1 PGMPlObe Laws AlitoP'rogram Olf Gate/Alarm Gele Gate Select GaleA Gate/Alarm Gale Gale A Synchro Pulse ur General Gain See CalibraUon Silael U1 General SI8II: o.Qj)Cj U1 'General Range See Calibration Sheet ur 'Oeneral 'Wedge Delay See CilibiaUon'8h~1 (~!iIy) ur Ganeral VeiocIIy Imported froll) .i.AWrde (.2272) ur Pulser FiIiq 2 UT Pulser VOltage High ur Pulser PW liilporled froni ,lAW fite ur PUiser PRF OpUnIum U1 Receiver Filler, None ur Receiver ~I!dlfier Fw ur --

Recelvei Video FBI" 0If ut Receive, Averaging' 1 ur Receiver Reilid 0 U1 lleam 'Sj:anolfaei Imported from .LAW file ur Beam Ifidex'Offsel' Imported ftom ,lAW tlli ur lIeam Skew ImllOl1ed rrom .lAW file Examiner: Troy A. SteInbauer Level: III Reviewer: Dan Langenfeld LU L.~vel: II!

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C\ir;L J Date: 05/16112 Date: 5tz.11iL Signature:

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Date: 05/16/12

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Page 7 ()f 21

Attachment 2, Request RR-A37 Page 80f21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA Customer: Fltst Energy Procedure: 54-9077864 I 64-ISI-864 Report No.: FW9-SWOL Slto: Davis Besse, Unll1 Rovlslon: 0011 003 Calibration Sheot No.: CDS-03 (Page 1 of 3)

Outage: 1Rt7 SDCN: NlA ComponentlD: RC-40-CCA*18*3-FW9 Overlay Focal Law: 73-1.5.LAW INSTRUMENT INFORMATION SEARCH UNIT INFORMATION CALIBRATION INFORMATION Manufacturer: Zelec Manufacturer: GEIT Cal. Block ID: 6039022 Model: OmniScanMX Model: 115-000-485 Cal. Block MaterIal: 316SS Serial Number: OMNI-1635 Serial Number: 01PSN9 Cal. Block Reflector: Seegelow Software Rev. I.4R3 Frequency: 2.0 MHz Cal. Reflector Size: 0.090' Frequency: 2.0 MHz Configuration: Dual-SaS Cal. Reflector Depth: Sao Balow

.PRF: Optimum Number of Elamint8: 32 Cal. UT Reading: See* Balow Reject: 0% Element Arrangement:* ht6 Cal. Gain Levtl: See Below Angle8 Geniratedi 0°_ 85° W IhC.) Element Shape: Rectangular Cal. Block Temp.: 74° SatupFlIe: 073-1;6 Tral18dllcer Size: 1.76X4.00mm Thermometer SorIa. No.: VH-11842 Delay: 0.2* ...seo II Elements afCalln: 32 Inlllal 001. Da~trJine: 5-'15*2012/1008 Range: 2.908"@OO #I Elementa at Cal Out: 32 Cal. Verlllcation Block 10: NIA weDae INFORMATION OableType: Intagral Cal VerlfJcaUon Reflector: NlA

Manufacturer: GEIT Cable Length: 6 Maiers Cal Verification ur Reading: NlA Part Number: 360-152-073 Adaptor Box: Omnl-A*ADP03 Cal Verification Gain Level: NlA Mode: LOngitudinal Cable Adapter Model: NlA Final Cal. DatalTlme: 05/.1511211019 Nom. Angle: 63° IntermedIate Co",wctore: 0 Couplant Type: Ullfagelll Measured Angle: 63* II ChannalslnoperaUve 0/0 Couplant Bakl... NUm~rl 09326 Nominal ExIt Point: *0,720* WEDGE INFORMATION (Cont., Exam Start: .1011 Measured exit Point: -0.05- Exit point to wedge backl o.e" Exam End: 1018 Wedge Oontourl. 6.000' N/A Wedge Orientation: AxIal Notea!Sefj Es88nUal Variables UT CallbtliUon Data SheetS.for addlJlqnsl calibration Information.

Hlbh Range Angla Mid Ranga AnIJ.le Low Range Angle Function Ch"ck and Report File Name 170°-8&°) 1260 .80.) 10°.2&°)

Angle 70* 63" 26" Pre W' Wedge: 073-PRE-W Reflactor Depth 0.10" SOH U"SOH(l.O) 1.2" SOH (1.0) Pre WOI Wedge: 073-PRE*WO UT Reading (MP) 0.32" 1.99" (1.GO) 1.45" Post W I Wedge: 073-PST-W AmJ)lItude GO%FSH 80%FSH 80%FSH Post WOI Wedge: 073-PST*WO Gain Level 50.0dS 32.2 dB 21J.OdB NfA Examiner: Troy A. Steinbauer Levell III Reviewer: Dan Langenfe~ /,J~ Level: III Signature: ~ -.~ Date: 05/16112 Slgnature:,iJt/4I ~..f!#--- Date: 05116112 UtllltYR~:

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ANIIRevlew:

Signature: Date:

r-."/~:0(.rJ;tt. Signature: ,-:~ A+m: Dat~/'l4 f\l.

U Page 8 ' of

21

Attachment 2, Request RR-A37 Page 9 of 21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES)

Customer: First Energy Procedure: 54*9077864/54*151*864 Report No.: FW9*SWOL Slle: Davia Besse, Unit I Revision: 001/003 Calibration Sheet No.: CD5*03 (Page 2 of 3)

Outage: 1R17 SDCH:NJA componontlD: RC-40*CCA*18*3*FW9 Overlay Focal Low: 73*1.5LAW Major Monu Item Menu Item Sub*Mellu Item Settlno Reading Result 8electoi 1 Reading Result Field 1 A%

Reading Result Field 2. AA Reading Result Field 3 SA" Readlll9 Result Fleid" PA" UT PUI", ~r Imported irom .lAW iii, UT pulse; TlIIRxmOde Imported from .lAW lile UT Beam GBlnoffse\ Imported from .lAW liIe UT Beam Angle Importild fiDriI .lAW nlii UT Beam Beam Delay Imported from .lAW file Ut: Advanced dB:rererence' Off UT Advanced Palnl8Qiy (Scale Factor) It UT .AdVanced Sum Gain Imported rrom .LAW Ole DiSplay S8lecu~ QlsPI.QY* MHC)

Display Sel8c:tlon C*Scan1 au D!jpJay seteclton. ~IOuP C;_t Display 8eI8cuon' PlO)i!cIIon On DJ8pJay RiiJeri ",Unit TIU8Df!p1h O/Bplily ,Rulers .w. Ruler* Unear (%)

DIajII8y Ruleni Df\ClrGC Off

. Display RUlers Gate On DIsp!aV Rulirs CurtiOi' Off Display ColOr se/eci AmplitUde Olaplay Color s.Wrt.* 0:0 Display Color t;nci% 100 Dlaplay ptopenJea Display Ml~

Dlaplay Ptopertles ~I!f~ Normal Ptobe/Part Select Select Sated TxIRx Probe/Part Select AuIoDelect oli Probe/Part PosIUon Scan Offset 0 Examiner: Troy A. Steinbauer Level: III RevIewer: Dan Lang~ Level: III J44'J .

Slgnatu~

Utility Review:

-- ",.

Date: 05/15/12 Signature:

ANI! Review:

Date: 05115112 SIgnature: ~ Date: Slz,-I/,L. Signature:

,

T-~ A'-\'IT D~~I "141,").-

I I Page 9 of 21

Attachment 2, Request RR-A37 Page 10 of21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES)

Customer: First Energy Procedure: 64*9077864 , 64*181*864 Report No.:FW9*SWOl Site: Davis Basse. Unil l' Revision: 001 r003 Calibration Sheet No.: CDS*03 (Page 3 of 3)

Outage: 1R17 SDCN:NlA Component 10: RC*40*CCA-18*3*fWg Overlay Focal Law: 73*1.5LAW Major Menu Item Monullem Sub*Menu Item 8eHIno Probe/Part PosiUon IndexOlfsel 0 Probe/Part Parte G80molly Plate Probe/Part Parts Thickness 10.000 POMProbe ConliguraUon Scan Type Sectorial PGMProbe Configurallon Conneclion P: 1 PGMProbe Laws AU!Q Program orr Gate/Alainl Gale GaleSelecl GoieA Gate/Alarm Gale Gate A Synchro PUle UT General Gain Sie CalibraUon Sheet UT General Slart 0.000 UT General Range See CaUbrallan Sheet General Wildga Delay Sali Cilnbratlon Shaat (Delay)

UT General VeloCIty IMported floM .LAWn.. (.2272)

Vi' puIS8/' Fleq 2 UT Pulser VoItege High Pulsar PW linpOrted flom .lAW file UT Pillser PRF optlmum I,I.T Receiver FUter None ReceIVer Reclifier FW UT Recelv8t Video FUt8t orr UT ReoeIver AV8I8IJ1ng 1 UT Recetver R8ject 0 UT Baam Scan 0If88\ Imported flom ~LAW PIe ur BOlim 'ndexOrr$et lniported from .LAW liIe UT Boam Skew Imported flom .lAW liIo Examiner: Troy A. Slelnbauer Level: III Reviewer: Dan Langenfeld. .All LeVel: III Slgn8ture~~ --:'Date: 05115/12 Signature: ~"" ;?fe,.,...-. Date: 06i15112 Utility Review: b. M"~ ANti Review:

tMfL~~ To ~.~"'t1: S-ID.JV'i.

Slgnature: Date: t;,.1?1}1'l. Signature:'

, Page Date:

Attachment 2, Request RR-A37 Page 11 of21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA Customer: First Energy Procedure: 54*9077664 154-ISI-664 Report No.: FW9*SWOL Site: Davis Besse, Unit 1 RevisIon: 0011 003 Calibration Sheet No.: CD8*04 (Page 1*of 3)

Outage: 1R17 SDCN: NIA Component ID: RC.40*CCA-18-3-FW9 Overlay Focal Law: 73-1.125.LAW INSTRUMENT INFORMATION SBARCH UNIT INFORMATION CALIBRATION INFORMATION Manufacturer: Zetac Manufacturer: GEIT Cal. Blook 10: 6039022 Model: OmnlScanMX Model; 115*000-485 Cal. Block Material: 31685 8arlal NlImber: OMNI-1535 8erlal Number: 01PBN9 Cal. Blook Refleotor: See Below 80ftware Rev. 1.4R3 Frequency: 2.0 MHz ~al. Reflector Size: 0.090' Frequencv: 2.0 MHz <<:onflgiJratlon: DUElI-SeS Cal. Reflector Depth: SeltBelow PRF; Opllmum Number of Elemente; 32 Cal. UT ReadIng: Sell BIllow Reject: 0% Element Arrangement: 2x16 Cal. Gain Level: See Below Ang/es*Generated: 0'* 85' W Inc.) Element Shape: Rectangular Cal. Block Temp.: 7411 Se.upFlle: 073*1.126 Transducer SIIII: 1.1h 4.00 mm Thermomllter Serlal.No.: VH-11842 Dalay: oi1Sec' i Elements at Cal In: 32 1"IUal Cal. DatelTlme: 6*15*2012/0947 Rang~:. 2.908"@00 II EleMents at Cal Out: 32 Cili. VerlflcllUon BIC)Ck ID: N/A WEDGE IN"OAMATION CltbleType: Integral Cal Verification Reflector: NfA Manufacturer: GEIT Cable Length: 6 MetalS Cill Verification UT Readl!'g: NlA Part Number: 380-162-073 Adaptor Box: Dmnl-A-ADP03 Cal VOrifloatlon GaIn -...v~I: NlA Mode: longitudInal Cable Adapter Model: NlA Final Cal. DateITlme: 06l;611?11006 Nom.ARgla: 53' IntermedIate Conneotors: *0 COMpla"t Typa: Urtraglllll Measured Angle: 63' " Ohannelslnoperatlve 0/0 *COuplant Batch Number: 09325 Nominal Elilt Point: -0.720" WEDGE INFORMATtQN (Cont.) Exam8tart: 0954 M..aaured Exit PoInt: .0.86" EIIII point to wedge baok: 0.8" EXam Ehd: 1004 Wedge,Contour: 5.000' NlA Wedge Orientation: Aldal Notes: See Essential Variabloa UTCalibratlon Dala Sheeta/or addlllQnll1 Cl8libratlon Information.

HIgh Range Angle MId Range Angle Lo\Y*Rar\ge Angle Famctlon*Cheok alUl Rtp~rt File Name

'70'- 86') (260

80') (0"- 26')

Anale 70' 53' Pre W I-Wedge: 073-PRt:*W Reflector Depth 0.10*SDH 1.0' SOH 10'SDH PreWOI Wedge: 073-PRE*WO UT Reading (MPt 0.45" 1.00" 1.215" PostW/Wedge: 073-PST-W Amplitude 80%FSH 80%FSH BO%FSH POst WOI Wedget 073*PST-WO Gain Level 52.0 dB 30.3dS 23.6 dB NIA E~amlner: Hoy A. Stelnbausr Leval: III RevIewer: Dan Langenfeld../ .... L// Level: III SIgnature: ~ ~~ :::::-- --Date: 05115/12 SIgnature: JAIl ,?~ r"'"'

-

Date: 05115112 Utility Review: b,~,.- ANIIRev/ew:

Signatura: ~ k~ SIgnature: Date: s-Ic1+ I" Page 11 Jf 1

Attachment 2, Request RR-A37 Page 12 of 21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES)

Customer: Firsl Energy Procedure: 64-9077864' 54-181*864 Report No.: FW9*SWOL Site: Davis Besse, Unit 1 Revision: 001 1003 Calibration Shset No.: CDS-04 (Pags 2 of 3)

Outage: 1R17 SDeN: N/A Component 10: RC-40*CCA*18*3*FW9 Overlay Focal Law: 73*1.126LAW Major Manu Item Menu Item Sub*Menu Item Setting ReadIng Resull Selector 1 Reading Resull Field 1 A%

Readlno Result Field 2 AA Reading Re$ult Field 3 SAA Reading R8$ult Fleld;j PAA UT Pulser Pulser iMportlid from .LAW fife UT Pulser TxlRxmoda Imporied from .LAW fde UT Beam Gain offael Imported from .LAW file UT Beam Angle Imported from .LAW (de UT Beam Beam Delay Imported from .LAW fila UT Advanced dB reterence Off UT AllvanCBd PofntaQly (Scala FacIof) f UT MvlinCC!d SUm Gilln Imported from .LAW lila

.Display* se~Uon Display A~S*(C)

Display- 6elealfon C*8canl on Display Sell!Clion Group Current Display SalacUon PIOjaciU6n On Display Rut!)ra, ",TUnlt TlI,IsDeplll DlsjlIiIy Rulars: % Rul81 LInear (%)

Display Rulers: DAClrGC orr Dlaplay, Rul81i: Gale On DlaplllY Rlliera Cursor olf Display COlor Select 'Amplitude DIsplay CC!1or Slert% 0.0 PlsPlay Color End % 100 Clsplay Properties DIsplay A*Scan Display Properties SOurce Normal Probe/Part Select Select Select TxlRlI ProblllParl Select AUla Delect on PlOblllParl POsition scanOrJs&1 0 Examiner: Troy A. Slttlnbauer Level: III Reviewer: Dan Langonfeld. L/) Level: III

~tI41 ~r"

..-

Utility Review: --t).~~

Slgnatur8:~----: ---~ Date: 05/16112 Date: 5)z1J~

Signature:

ANII Review:

SIgnature: ,,~

Date: 06/15/12 slMIIA Signature:

. ,- At.\lt Date:

, .

Page 12 of 21

Attachment 2, Request RR-A37 Page 13 of 21 A PHASED ARRAY UT CALIBRATION DATA SHEET AREVA (ESSENTIAL VARIABLES)

Custom~r: First Energy Procedure: 54*9077864 I 54*151-864 Report No.: FW9,5WOL Silol Davis Besse. Unit 1 Rovlslon: 0011 003 Calibration Shoet No.: CDS*OII (Pogo 3 of 3)

Outage: lR17 SDCN: N/A Component ID: RC-40-CCA-18-3-FWO Overlay Focal Law: 73*1.6LAW Major Menu Item Manu Item Sub*Mimu lIem SilHlng ProbaiPart PoslUOn lildexO"ael o ProbaiPart Parl& Geometry Plilla PlobaiPart Parta ThIckI\e8s lC).OOO PGMProba ConliguraUOn ScanTypa Se~rlal POMProba ConnguraUon PGMProba Laws AlitoPR1IIrem 0" Gate I Alarm Oalo Gate SeleCt 08teA Oala/Alarm Gale ~a~ A 5yncllro UT General Gain See CallbraUon Sheat ur General ur Goneral See Calibration Sheel ur General -80e CalibratlonS,,"1 (DelaY) ur Genaral Velocity Imj)Or1ed 'rom 1AW file (.2272) ur Pulser Freq ur Pidser VoIhi(Ja ur Pulier PW ImpOrted from ~lAW'~

UT Pulaer PRF Optimum UT Receiver .FOter ur ReceIver RecIlfter UT R8cetver VlifeoFl1ier ur Receiver ur Receiver o ur --

Beam ur 808m In~8ii 0"8el ImlJOlted 'rom .lAW filii ur Beam Skew Imported'ftcin,,-.lAWfila examiner: Troy A. Steinbauer Level: III Reviewer: Dan Langenfeld Livel: III f1A~~ -/ - ,Lat),

Signature: ~ --..,r Date: 05/16112 Signature: If;'~f ii(~7"~--. Dat&:- 05115112 Utility Review: ANn Review:

Sianature: Date: slat/",. Signature: T..£. .ft... At..nT Date: s/~:t.

Page 1~ of 21

Attachment 2, Request RR-A37 Page 14 of 21 RepOrt Number: FW9-SWOL AREVA A PHASED ARRAY WELD OVERLAY EXAMINAnON DATA SHEET ~i~on Data Sheet Number: EOS-01 ApJ)1i~ble calibration Sheet Numbers: Cos.o1 through CDS-04 Customer lmonnation Component Information Utility: First Energy Plant Davis Besse IUnit: 1 CompO~nt rD:

RC-40-CCA-18-3-F'tN9 Overlay Original Pipe Weld 10: NlA Outage: 1R17 Examination Surface: 00 Surface Condition: Ground Smooth Procedure Information Original Weld Nom. Diameter: 3.4" Original Weld Thickness: See Note-1 Procedure:. 54-9077864. Rev. 001/54-1S~ Weld.~ Diameter: 4.5" Weld Overlay Thiclcness: 0.53" - 0.89" Title: Procedure for Manual Phased Array UItrasoi1ic &arnination Of Weld Overlaid Sinillar and Dissimilar Metal Welds (S+e077864, Rev. 0(1)

Overlay Type: Non-Standard Weld Overlay Materi",l: AUoy 52M Manual Phased Array Ultrasonic ~nation ofW~d Overlaid Sirni18r and DiSsimilar Metal Welds (S4.Is1-864-003)

Examination Information Examination Start Data: 0511.5112 Examination Start Tune: 0947 Component Temperature: 73°F Thermometer Serial Number: VH-11842 Examination End Date: 05115112 Examination End Time: 1045 Couplant Type: Ultragel 1\ Couplant Batch Number: 09325 Exam Examination Focal Search Unit Wedp Scan Direction Se~ Recordable Indications Umitations Notes:

Angles La'!' (ds) 01PBNS 360-152-072 O~ "SOO 72-1.1.25 !6! LKUS b!LKDS 30.9 No See Note 1

~ LKCW 181 LKCCW Q1PBNS ~152-O72 0°-80" !::! LKUS yLKDS 39.6 No See Note 1 72-1.5 mI.LKCW a:a LKCCW 01PBN9 360-152-073 0" -85" 1301.125 ~~~ 36.3 No See Note 1 01PBN9 360-152-073 O* - 85" 73-1.5 ~~~~ccw 38.2 No See Note 1 Comments: Notes:

Sensitivity adjusted during examination to maintain average baseline 1. See coverage data sheets for*1he examination coverage obtained. Umitation noise level between 5% and 20% FSH for the eo degree beam angIe. due to compon~nt and FSWOL configuration.

&aminer: Troy A. Steinbauer Level: JII Revfenr. Dan~ ~ Level: III S'~gnatu*

. ~~

. ~

Date: 0SI15112 Signature: . ~~ ~. Date: 05/15112 Utility Review: D. m~ AND *Review:

Date:

~~

Date:

Signature:

sft."" fZ.

Signature: ~Ji.~At4tt s):t4h,,-

II Page 14 of 21

Attachment 2, Request RR-A37 Page 15 of21 A

AREVA OMNISCAN 32/128 ULTRASONIC PHASED ARRAY INSTRUMENT CHANNEL FUNCTIONAL VERIFICATION IMAGES Customer: First Energy Site: Davis Besse Unit 1 Outage: 1R17 Report Number: FW9-SWOL Channel Functional Verification System: 064-02 (RCS) Component: RC-40-CCA-18-3-FW9 Overlay Sheet No.: CFV-01 CHANNEL FUNCTIONAL VERIFICATION IMAGES Transducor Serial Number: 01PBN8 Pre With Wedge rl\1'""'r--~----r--r---------.-.-.-----~ ~!!~ ab: A:OQ.O 6K:090 L:001 Post With Wedge i

. It, '" 'I.' ~. !', ~ I ~.' '1', ;' .' !. ,! ", I Date: 05/16/12 Date: 05115112 Page 15 of 21

Attachment 2, Request RR-A37 Page 16 of 21 A OMNISCAN 321128 ULTRASONIC PHASED ARRAY INSTRUMENT CHANNEL FUNCTIONAL VERIFICATION IMAGES AREVA Customer: First Energy Site: Davis Besse Unit 1 Outage: 1R17 Report Number: FW9-SWOL Channel Functional Verification System: 064-02 (RCS) Component: RC-40-CCA-18-3-FW9 Overlay Sheet No.: CFV-02 CHANNEL FUNCTIONAL VERIFICATION IMAGES Transducer Serial Number: 01 PBN8 Pre Without Wedge Post Without Wedge Prepared By: Troy A. Steinbauer Date: 05/15/12 Date: 05115112 Page 16 of 21

Attachment 2, Request RR-A37 Page 170f21 A OMNISCAN 32/128 ULTRASONIC PHASED ARRAY INSTRUMENT CHANNEL FUNCTIONAL VERIFICATION IMAGES AREVA Customer: First Energy Site: Davis Besse Unit 1 Outage: 1R17 Report Number: FW9-SWOl Channel Functional Verification System: 064"()2 (RCS) Component: RC-40-CCA-1~-3-FW9 Overlay Sheet No.: CFV-03 CHANNEL FUNCTIONAL VERIFICATION IMAGES Transducer Serial Number: 01 PBN9 Pre With Wedge Post With Wedge Date: 05/15/12 Date: 05/15/12 21

Attachment 2, Request RR-A37 Page 18of21 A OMNISCAN 32/128 ULTRASONIC PHASED ARRAY INSTRUMENT CHANNEL FUNCTIONAL VERIFICATION IMAGES AREVA Customer: First Energy Site: Davis Besse Unll1 Outage: 1R17 Report Number: FW9*SWOL

--~---~~--~--~~~=-~----~

Channel Functional Verification System: 064-02 (RCS) Component: RC-40-CCA-18-3-FW9 Overlay Sheet No.: CFV-04 CHANNEL FUNCTIONAL VERIFICATION IMAGES Transducer Ssrlal Number: 01 PBN9 Pre Without Wedge

.-

Post Without Wedge Date: 05/15/12 Date: 05/15112 Page 18 of 21

Attachment 2, Request RR-A37 Page 19 of21 Report No.: FW9-SWOL A UT Coverage Work Sheet Component 10: RC-40-CCA-18-3-FW9 Overlay AREVA Sheet No.: COV-01 Customer: First Energy Site I Unit: Davis Besse 11 Outage: 1R17 1-2 RCS COLD LEG DRAIN NOZZLE RC40-CCA-18-3-FW9 OVERLAY AXIAL COVERAGE US-TOTAL

....... 0.83- 100,.

0.114 -501(,

(.64 x .5) + .81 a 1.15/1.55 ~ .74 74%

ElCTRAOOSE .. 74,.

INTRADOSE a 80%

OC!de9.aG~

270 deg.... Jill Ald.1 Compolile'; ~

1.&1-TOTAL 0.60*~

0.68-100W0 II. .11).* .88" .88"11.81 "

eo'16

".: ......

' ... -, ." -.. --

. . .- 1,M*nnAL 0i7:H~

0.10 -1iOl4

(;10'" ,&) *.*711" t.07*' U4;, ,6it4 1IQ!6-10.* GO"

,.. ~

..*. -..... ..

" .

1.lI7TOTAl 0.16- 100,.

0.19-50" lo1i!it.lli t .14" I, iO~/I.o; ~ .135 13" 210de(/.

Form Edition: Nov 20111 Rev 0 Page: 19 of 21

Attachment 2, Request RR-A37 Page 200f21 Report No.: FW9-SWOL A UT Coverage Work Sheet Component ID: RC-40-CCA-18-3-FW9 Overlay AREVA Sheet No.: COV-02 Customer: First Energy Site I Unit: Davis Besse 11 Outage: 1R17 1-2 ReS COLD LEG DRAIN NOZZLE RC*40*CCA*18-3*FWD OVERLAY eiRe. COVERAGE US* TOTAL 1.18*100""

1.1811.5S-.781 78" p

IlXTRAOOSE a 76.

INTRADOSe - 70.

270daQ.-n..

Clio. Compoll .... 71 ..

I.GI*TOTAL 1.14*100" 1.1411.81 D

70" U4.TOTAL 1.08* '0Ml 1.081 U4 D.68 66" 1.!i7TOTAL 1.16*1~

~--~_1lT 1.1611.67* .73 7;'~

2l0dag. -+__,,_

Form Edition: Nov 2011 , Rev 0 Page: 20 of 21

Attachment 2, Request RR-A37 Paae 21 of21 Report No.: FW9-SWOL A UT Coverage. Work Sheet Component ID: RC-40-CCA-18-3~FW9 Overlay AREVA Sheet No.: COV-03 Customer: FIrst Energy Site I Unit: DavIs Besse 11 Outage: 1R17 .

SCAN VOLUME % COVERAGE AXIAL SCAN COVERAGE EXTRADOSE RE(310N 74%

INTRADOSE REGION 60%

90 DEGREE REGION 69%

270 DEGREE REGION 73%

AXIAL COMPOSITE COVERAGE = 89%

CIRC SCAN COVERAGE EXTRADOSE REGION 76%

INTRADOSE REGION 70%

90 DEGREE REGION 68%

270 DEGREE REGION 73%

CIRCUMFERENTIAL *COMPOSITE cOVERAGE == 71%

COMBINED COVERAGE AXIAL COMPOSITE..COVERAGE = 69%

CIRCUMFERENTIAL COMPOSITE COVERAGE =:71'%

Total OOY8tage..Qbtained.: 70% -- .-

Form EdItion: Nov 2011 I Rev 0 Page: 21 :0' 21

Davis-Besse Nuclear Power Station 10 CFR 50.55a Request RR-B1 Page 1 of6 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)

--Alternative Provides Acceptable Level of Quality and Safety--

1. American Society of Mechanical Engineers (ASME) Code Components Affected Components: Various piping welds presented in Tables 1 and 2 Code Class: Class 2 .

Examination Categories: C-F-1 and C-F-2 Item Numbers: C5.11, C5.21 , C5.51, and C5.61

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 2007 Edition through 2008 Addenda.

3. Applicable Code Requirement

Table IWC-2500-1, Examination Category C-F-1, Item C5.11 requires surface and volumetric examinations for piping welds greater than or equal to 3/8 inch nominal wall thickness for pipe sizes greater than nominal pipe size (NPS) 4 inch.

Table IWC-2500-1, Examination Category C-F-1, Item C5.21 requires surface and volumetric examinations for piping welds greater than 1/5 inch nominal wall thickness for pipe sizes greater than or equal to NPS 2 inch and less than or equal to NPS 4 inch.

Per Note 1 of Examination Category C-F-1, requirements for examination of welds in piping less than or equal to NPS 4 apply to high pressure safety injection and auxiliary feedwater systems in accordance with the exemption criteria of IWC-1220.

Per Note 2 of Examination Category C-F-1, welds selected for examination shall include 7.5 percent, but not less than 28 welds, of all dissimilar metal, austenitic stainless steel or high alloy welds not exempted by IWC-1220. (Some welds do not meet the IWC-1220 exemption criteria. However, these welds are not required to be nondestructively examined per Examination Category C-F-1. These welds shall be included in the total weld count to which the 7.5 percent sampling rate is applied.)

Table IWC-2500-1, Examination Category C-F-2, Item C5.51 requires surface and volumetric examinations for piping welds greater than or equal to 3/8 inch nominal wall thickness for pipe sizes greater than NPS 4 inch.

Table IWC-2500-1, Examination Category C-F-2, Item C5.61 requires surface and volumetric examinations for piping welds greater than 1/5 inch nominal wall thickness for pipe sizes greater than or equal to NPS 2 inch and less than or equal to NPS 4 inch.

Per Note 1 of Examination Category C-F-2, requirements for examination of welds in piping less than or equal to NPS 4 apply to high pressure safety injection and auxiliary feedwater systems in accordance with the exemption criteria of IWC-1220.

Request RR-B1 Page 20f6 Per Note 2 of Examination Category C-F-2, welds selected for examination shall include 7.5 percent, but not less than 28 welds, of all carbon and low alloy steel welds not exempted by IWC-1220. (Some welds do not meet the IWC-1220 exemption criteria.

However, these welds are not required to be nondestructively examined per Examination Category C-F-2. These welds shall be included in the total weld count to which the 7.5 percent sampling rate is applied.)

4. Reason for Request

The piping in the containment spray discharge, the decay heat discharge, the decay heat suction from the reactor coolant system Class 1 boundary, and the main steam supply for the auxiliary feedwater pumps from the main steam lines to the first isolation valve have wall thicknesses less than 3/8 inch and greater than 1/5 inch. The piping in the containment spray suction, the high pressure injection suction, the high pressure injection recirculation line, the decay heat suction from the borated water storage tank, and the decay heat suction from the emergency sump all have wall thicknesses less than 1/5 inch. In accordance with Examination Categories C-F-1 and C-F-2, this piping does not require any nondestructive examination.

When the selection criteria of Table IWC-2500-1, Examination Categories C-F-1 and C-F-2, Note 2, is applied to these systems, approximately 93 percent of the decay heat discharge welds past the containment isolation valves, approximately 26 percent of the high pressure injection discharge, and approximately 11 percent of the main steam system welds receive a nondestructive examination per Examination Categories C-F-1 and C-F-2. These sampling rates exceed the 7.5 percent sampling rate established in ASME Section XI. When the same selection criteria is applied to the emergency core cooling systems (ECCS), the ECCS welds requiring examination total approximately 1/3 of the entire nonexempt weld population for all these systems. This is due to the large number of nonexempt ECCS welds that do not meet the Examination Categories C-F-1 and C-F-2 minimum thickness requirements, and therefore can not be selected for examination. This disproportionate distribution does not align with Note 2(a) of Examination Categories C-F-1 and C-F-2, which requires examinations to be distributed among Class 2 systems prorated, to the degree practicable, on the number of nonexempt welds in each system.

Volumetric examinations are not appropriate for all piping wall thicknesses. An example of this acknowledgement is contained in Code Case N-435-1. This Code Case, which was incorporated into the 1995 Addenda, provided an alternative ASME Section XI examination requirement. This Code Case stated that for welds in vessels with a nominal wall thickness less than or equal to 1/5 inch, surface examination may be applied in lieu of volumetric examination. With its approval, ASME acknowledged the impracticality of examining welds with a wall thickness of 1/5 inch or less to the ASME Section XI volumetric examination requirements.

5. Proposed Alternative and Basis for Use Proposed Alternative:

The minimum nominal wall thickness specified in Examination Categories C-F-1 and C-F-2 will not be used to exclude welds from examination in the containment spray, decay heat, high pressure injection, or main steam systems. Instead, the following requirements will be used to establish examination requirements for Examination Category C-F-1 or C-F-2 welds in these systems.

Request RR-B1 Page 30f6 A 7.5 percent sampling rate will be applied to all welds not exempted by IWC-1220 using the following selection criteria.

Selected welds that meet the nominal wall thickness requirements of Examination Categories C-F-1 and C-F-2 will receive a surface and volumetric examination.

Selected welds in piping greater than NPS 4 inch with wall thicknesses greater than 1/5 inch and less than 3/8 inch will receive an augmented surface and volumetric examination.

Selected welds in piping with wall thicknesses less than or equal to 1/5 inch will receive an augmented surface examination.

Pipe sizes with wall thickness less than 3/8 inch (including the group with wall thickness less than 1/5 inch) range from NPS 6 inch to NPS 18 inch. The current numbers of welds are identified in this request's Tables 1 and 2 for Examination Categories C-F-1 and C-F-2, respectively.

Basis for Use:

Volumetric examinations are used to determine if unanticipated degradation of piping is occurring due to such phenomena as erosion, corrosion, or cracking. ASME Section XI only requires volumetric examination of those welds with a wall thickness greater than or equal to 3/8 inch for pipe sizes greater than NPS 4 inch and those welds in high pressure injection and auxiliary feedwater systems with greater than 1/5 inch nominal wall thickness for pipe sizes greater than or equal to NPS 2 inch and less than or equal to NPS 4 inch.

In lieu of the Code requirements, all welds in these systems, except those exempted by IWC-1220, will be included in the Code required 7.5 percent population. Those welds with a wall thickness greater than 1/5 inch are subjected to volumetric and surface examination, while those with a weld thickness less than or equal to 1/5 inch are subjected to a surface examination. Application of these criteria to the entire population will provide assurance of the integrity of these Class 2 systems for piping of all wall thicknesses.

The weld examinations will be scheduled per the requirements of Table IWC-2411-1.

This alternative will provide an acceptable level of quality and safety as the examinations will be performed throughout the entirety of these Class 2 systems, rather than on only a portion of those systems.

6. Duration of Proposed Alternative The proposed alternative shall be utilized during the fourth 10-year inservice inspection interval, which commenced on September 21, 2012.

Request RR-B1 Page 4 of6

7. Precedent The Nuclear Regulatory Commission (NRC) approved a similar alternative, submitted as Relief Request RR-B2, for the Davis-Besse Nuclear Power Station.

NRC letter to FirstEnergy Nuclear Operating Company,

Subject:

Davis-Besse Nuclear Power Station, Unit 1, Requests for Relief for Third 10-Year Interval Inservice Inspection Program Plan TAC No. MB1607, September 30,2002 ..

[Accession No. ML022700279]

8. References

1. ASME Code Case N-435-1, Alternative Examination Requirements for Vessels With Wall Thickness 2 in. or Less," July 30,1986.

Request RR-B1 Page 50f6 TABLE 1: Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping(:.!)

Category Item No. System Descrtptlon Exam Method Number of ExamInation Frequenqo Scheduled for Components In Percentage(4) Examlnatlon(4)

Item No.

C-F-1 C5.11 04~2 Piping WeldS :it 3/8 inch Surface and 42 4 Nominal WaD Thickness for volumetric Piping> NPS 4 Circumferential Weld Item Number Total 42 7.5 percent Each inspection interval 4 C-F-1 CS.11A 04~2 Piping Welds> 1/5 inch and Surface and 283 21 061-01 < 3/8 inch Nominal WaD volumetric 88 7 Thickness for Piping> NPS 4 Circumferential Weld Item Number Total 371 7.5 percent Each inspection interval 28 C-F-1 C5.11B 04~2 Piping Welds s 115 Inch Surface 122 9 052-01 Nominal wall Thickness for 32 3 Piping> NPS 4 061-01 Circumferential Weld 12 1 Otherl') 11 0 Item Number Total 1IT 7.5 percent Each inspection interval 13 C-F-1 C5.21 052-01 Piping Welds> 1/5 inch Surface and 301 24 Nominal Wall Thickness for volumetric Piping :it NPS 2 and s NPS 4 Circumferential Weld Item Number Total 301 7.5 percent Each inspection interval 24 C-F-1 C5.21A 04~2 Piping Welds s 1/5 inch Surface 21 2 052-01 Nominal WaD Thickness for 142 11 Piping :it NPS 2 and s NPS 4 Circumferential Weld Item Number Total 163 7.5 percent Each inspection interval 13

. 1054(3)

I Category Total 7.5 percent Each inspection interval 82 System Definitions: 049-42 .. Decay Heat and Low Pressure Injection (Includes Borated Wster Storege)

OS2"()1 .. High Pressure Injection 061-01" ContalnmentSprey Note 1: These systems Included for weld count only. Welds are not required to be examined per examination Category C~-1 orthls request for altematlve.

Note 2: This table does not Include C5.30 and CS.41 welds. A 7.5 percent sample of these welda will alBo receive a surface examination, as required by Examination Category C~-1.

Nota 3: Total number of welda requiring examination for ExamInation Category c.F-1 and this request for alternative, excluding Items CS.30 and CS.41.

Note 4: examinations are prorated, to the extent practicaJ, among code Item numbere and systems.

Request RR-B1 Page 60f6 TABLE 2: Category C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping(2)

Category Item No. System Descrtptlon Exam Method Number of EumlnatIon Frequency Scheduled for Components In Percentage(4) Examlnatlon(4)

Item No.

C-F-2 C5.51 036-01 Piping Welds ;t 3/8 inch Surface and 77 6 050-03 Nominal wall Thickness for volumetrtc 69 6 Piping> NPS 4 083-01 Circumferential Weld 99 7 Other 4 0 Item Number Total 249 7.5 percent Each inspection interval 19 C-F-2. C5.51A 083-01 Piping Welds> 1/5 inch and Surface and 80 10 Other") < 318 inch Nominal Wall Volumetric 42 0 Thickness for Piping> NPS 4 Circumferential Weld Item Number Total 122 7.5 percent Each inspection interval 10 C-F-2 CS.61 050"()3 Piping Welds> 1/5 inch Surface and 49 4 Nominal Wall Thickness for Volumetric Piping ;t NPS 2 and s NPS 4 Circumferential Weld Item Number Total 49 7.5 percent Each inspection interval 4 420(3)

I category Total 7.5 percent Each inspection interval 33 System Definitions: 036-01" MaIn Feedwater 050-03 = Auxiliary Feedwater 083"()1 .. Main Steam Note 1: These systems Included for weld count only. Welds are not required to be examined per Examination category C-F-2 or this request for alternative.

Note 2: This table does not Include C5.70 and CS.81 welds. A 7.5 percent sample of these welds will also receive a surface examination, as required by examination Category C-F-2.

Note 3: Total number of welds requlrtng examination for EumlnatIon Category C-F-2 and thIs request for alternative, excluding Items CS.70 and CS.81.

Nota 4: examinations are prorated, to the extent practical, among code Item numbers and systems.

Davis-Besse Nuclear Power Station 10 CFR 50.55a Request RR-A36 Page 1 of 12 Notification of Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii)

--Inservice Inspection Impracticality--

1. American Society of Mechanical Engineers (ASMEl Code Components Affected ASME Class 1 welds in the Reactor Pressure Vessel (Figure 1 depicts locations):

Reactor Vessel Lower Shell to Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-34)

Reactor Vessel Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-35)

ASME Class 1 components in the Reactor Pressure Vessel (Figure 1 depicts locations):

Core Flood Nozzle Inner Radius Sections (Component Number RC-RPV-WR-54/55-W-IR)

(Component Number RC-RPV-WR-54/55-Y-IR)

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1995 Edition through 1996 Addenda.

3. Applicable Code Requirement

Table IWB-2500-1, Examination Category B-A, Item B1.11 requires a volumetric examination of essentially 100 percent of the shell weld length, as defined by Figure IWB-2500-1. Code Case N-460 states that a reduction in*examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10 percent.

Table IWB-2500-1, Examination Category B-A, Item B1.21 for reactor vessel circumferential head welds, requires a volumetric examination of essentially 100 percent of the weld length, as defined by Figure IWB-2500-3. Code Case N-460 states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10 percent.

Table IWB-2500-1, Examination Category B-O, Item B3.100 for reactor vessel nozzle inside radius sections, requires a volumetric examination of essentially 100 percent of the area of Interest, as defined by Figure IWB-2500-7. As an approved alternative to the Item B3.100 requirements, Code Case N-648-1, with conditions defined in Regulatory Guide 1.147, allows a visual examination with enhanced magnification of the external surfaces of the examination volume to be performed in lieu of the volumetric examination requirements. Code Case N-460 states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10 percent.

Request RR-A36 Page 2 of 12

4. Impracticality of Compliance Examining essentially 100 percent of the weld volume or areas of interest for the affected components, as required by the ASME Code, is impractical. Examination limitations exist due to reactor pressure vessel (RPV) internal obstructions inherent to the Babcock & Wilcox reactor design. A discussion on the examination details is provided below. Specific examination interferences and actual examination capabilities are discussed for each of the affected components in Section 6.

Examination Details:

The RPV welds are examined from the inside surface of the RPV using the AREVA Trans-World System (TWS) inspection manipulator in conjunction with the AREVA ACCUSONEX data acquisition and analysis system. TWS is a computer controlled, remotely operated manipulator that uses a contact ultrasonic (UT) head to obtain ultrasonic data for the detection and sizing of indications. The contact head is fitted with an array of transducers in direct contact with the RPV surface. With the ACCUSONEX data acquisition system, multiple channels of ultrasonic data are amplified, filtered, digitized, and processed, and then integrated with the transducer position to provide computer generated images of the examination volume. The RPV welds have been examined with techniques which have been demonstrated and qualified in accordance with Supplements 4 and 6 of ASME Section XI, 1995 Edition through 1996 Addenda, Appendix VIII, using the Electric Power Research'*** i .

Institute (EPRI) performance demonstration initiative (POI) protocol.

5. Burden Caused by Compliance The bottom of the RPV was designed and fabricated such that core guide lugs and incore instrument nozzles obstruct portions of the RPV's lower circumferential welds, causing a limitation in scanning coverage for the welds in this request. Additionally, flow restrictors (venturi inserts) are welded into the two core flood nozzles, also causing a limitation in scanning coverage for the components in this request. Removing the obstructions would require the RPV and the core flood nozzles to be redesigned and modified, which is impractical.

Although theoretically feasible, it is estimated that performing these examinations from the outside surface of the RPV would require several hundred man-hours to stage, erect and remove scaffolding, to remove and reinstall RPV insulation, and to perform the examinations. Based on radiological survey results from the spring 2012 refueling outage, this work would occur within 500 milli-Rem (mR) to 1160 mR per hour radiation fields adjacent to the RPV, resulting in a significant increase in cumulative occupational radiation exposure [dose] to personnel without a compensating increase in quality and safety.

Request RR-A36 Page 3 of 12

6. Proposed Alternative and Basis for Use Reactor Vessel Lower Shell to Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-34)

Alternative Examination:

The accessible areas of the weld have been examined using the TWS and ACCUSONEX system. These examinations have been performed from the inside surface of the reactor vessel by scanning the weld and adjacent base material areas above and below the weld. Examination scanning directions were both parallel and perpendicular to the weld axis. The aggregate examination coverage of the weld and base metal areas was approximately 58 percent of the required examination volume. In addition, a VT-3 visual examination of the reactor vessel interior was performed in accordance with the requirements of Examination Category B-N-1, Item B13.10.

Basis for Relief:

Figures 2A and 2B in this request depict the Reactor Vessel Lower Shell to Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-34).

Figure IWB-2500-1 defines the required examination volume. Ultrasonic interrogation of greater than 90 percent of this volume cannot be obtained due to interferences caused by the core guide lugs. The core guide lugs are welded to the reactor vessel shell just above the lower shell to bottom head weld and extend approximately 2 inches below the centerline of the weld. These lugs restrict the TWS manipulator's ability to move to areas necessary to fully examine the required volume. Access to approximately 42 percent of the examination volume is restricted.

The remaining 58 percent of the examination volume has been examined using the TWS and ACCUSONEX system. This examination has been performed from the inside surface of the reactor vessel by scanning the weld and adjacent base material areas above and below the weld. Examination scanning directions were both parallel and perpendicular to the weld axis. In addition to the required ultrasonic examination, the welds attaching the core guide lugs have received a VT-3 visual examination in accordance with Table IWB-2500-1, Examination Category B-N-2, Item B13.30, "Interior Attachment Welds Beyond Beltline Region." This VT-3 examination confirmed the lack of relevant conditions for the core guide lug welds, which would have indicated if the area of the lower shell to bottom head weld had been subjected to any excessive loads.

This weld was last examined during the third interval 10-year reactor vessel examination (October 2011). The examination volume achieved during this examination (approximately 58 percent) was similar to that achieved during the second interval 10-year reactor vessel examination. There have been no indications identified in this weld that exceed the acceptance criteria of ASME Section XI. The UT data sheet, flaw evaluation summary sheets, and UT scan plan for this weld are provided in the attachment to this request.

Due to the existing configuration of the reactor vessel, the examination requirements of ASME Section XI, 1995 Edition through 1996 Addenda are impractical.

Request RR-A36 Page 4 of 12 Reactor Vessel Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-35)

Alternative Examination:

The accessible areas of the weld have been examined using the TWS and ACCUSONEX system. These examinations have been performed from the inside surface of the reactor vessel by scanning the weld and adjacent base material areas above and below the weld. Examination scanning directions were both parallel and perpendicular to the weld axis. The aggregate examination coverage of the weld and base metal areas was approximately 46 percent of the required examination volume. In addition, a VT-3 visual examination of the reactor vessel interior was performed in accordance with the requirements of Examination Category B-N-1, Item B13.10.

Basis for Relief:

Figures 3a and 3b in this request depict the Reactor Vessel Bottom Head Circumferential Weld (Weld Number RC-RPV-WR-35).

Figure IWB-2500-3 defines the required examination volume. Ultrasonic .

interrogation of greater than 90 percent of this volume cannot be obtained due to interferences caused by reactor vessel incore instrument nozzles and core guide lugs. These instrument nozzles protrude through the bottom head of the reactor vessel to a height of approximately 1 foot from the inside surface of the bottom head.

Access to approximately 54 percent of the examination volume is restricted. The remaining 46 percent of the examination volume has been examined using the TWS and ACCUSONEX system. These examinations have been performed from the Inside surface of the reactor vessel by scanning the weld and adjacent base material areas above and below the weld. Examination scanning directions were both parallel and perpendicular to the weld axis.

This weld was last examined during the third interval 10-year reactor vessel examination (October 2011). The examination volume achieved during this examination (approximately 46 percent) was less than the examination volume achieved during the second interval 10-year reactor vessel examination, which was approximately 72 percent. This reduction in examination volume is directly attributable to the TWS equipment's design and operation, including a larger transducer sled, which limits accessibility. There have been no indications identified in this weld that exceed the acceptance criteria of ASME Section XI. The UT data sheet, flaw evaluation summary sheets, and UT scan plan for this weld are provided in the attachment to this request.

Due to the existing configuration of the reactor vessel, the examination requirements of ASME Section XI, 1995 Edition through 1996 Addenda are impractical.

Request RR-A36 Page 5 of 12 Core Flood Nozzle Inner Radius Sections (Component Number RC-RPV-WR-54155-W-IR)

(Component Number RC-RPV-WR-54155-Y-IR)

Alternative Examination:

The accessible areas of the examination surfaces have been visually examined utilizing the EVT-1 technique. The coverage obtained was 360 degrees around the nozzle, from the nozzle to vessel weld, to a distance approximately 3 inches deep inside each nozzle's bore. For each nozzle weld, this resulted in approximately 25 percent of the inside radius area of interest, as defined by the condition in Regulatory Guide 1.147, being examined.

Basis for Relief:

Figure 4 in this request depicts the Core Flood Nozzle Inside Radius Sections (Component Numbers RC-RPV-WR-54/55-W-IR and RC-RPV-WR-54/55-Y-IR).

Table IWB-2500-1, Examination Category B-D, Item B3.100 requires a volumetric examination as depicted in Figure IWB-2500-7. As an alternative to this requirement, Code Case N-648-1 (approved for use in Regulatory Guide 1.147, with conditions) allows performance of an enhanced visual examination (EVT-1) to satisfy this requirement. The area of interest for the EVT-1 is the external surface of Figure IWB-2500-7(b), as defined by the condition in Regulatory Guide 1.147.

Due to flow restrictors located inside the bores of the core flood nozzles, neither the UT nor the EVT-1 visual examinations could achieve the required examination coverage of greater than 90 percent. Because these flow restrictors are welded into the nozzles, their removal is not practical. The flow restrictors prohibit all UT examinations from the nozzle inside diameter. As a result, a limited EVT-1 visual examination was performed in lieu of the UT examination. The coverage obtained by the EVT-1 examination was 360 degrees around the nozzle, from the nozzle to vessel weld, to a distance approximately 3 inches deep inside each nozzle's bore.

For each nozzle this resulted in approximately 25 percent of the inside radius area of interest receiving a visual examination.

These areas were last examined during the third interval 10-year reactor vessel examination (October 2011). Because of the UT limitations described above, UT examinations were not performed. As an alternative, the EVT-1 examination requirements of Code Case N-648-1 were invoked, as approved for use in Regulatory Guide 1.147. Summaries of the visual examinations are as follows:

Component Number RC-RPV-WR-54/55-W-IR Examination Coverage Examination Comments/Remarks Type Achieved Results EVT-1 25 percent No Recordable Examined the accessible surfaces of the Indications (NRI) nozzle inner radius for cracking, for a full 360 degrees, from the nozzle to vessel weld a distance of 12.5 inches Inside the nozzle bore (12.5 Inches Includes the flow restrictor). Total coverage: 25 percent.

The flow restrictor covered 75 percent of the inside radius examination surface.

Request RR-A36 Page 6 of 12 Com~onent Number RC-RPV-WR-54155-Y -IR Examination Coverage Examination Comments/Remarks Type Achieved Results EVT-1 25 percent No Recordable Examined the accessible surfaces of the Indications (NRI) nozzle inner radius for cracking, for a full 360 degrees, from the nozzle to vessel weld a distance of 12.5 inches inside the nozzle bore (12.5 inches includes the flow restrictor). Totalcoverage: 25 percent.

The flow restrictor covered 75 percent of the inside radius examination surface.

>

Due to the existing configuration of the core flood nozzles, the examination requirements of ASME Section XI, 1995 Edition through 1996 Addenda are impractical.

7. Durati*on of Proposed Alternative The proposed request shall be utilized for the third 10-year inservice inspection interval, which expired on September 20, 2012. .

8. Precedent*

The Nuclear Regulatory Commission (NRC) approved similar requests for the Millstone, North Anna, and Davis-Besse Nuclear Power Stations:

NRC letter to Dominion Nuclear Connecticut, Inc.,

Subject:

"Millstone Power Station, Unit No. 3- Issuance of Relief Requests IR-2-51 Through IR-2-60 Regarding Second 10-Year Intervallnservice Inspection Program Plan (TAC Nos. ME3809 Through ME3818)," April 26, 2011. [Accession No. ML110691154 NRC letter to Virginia Electric and Power Company,

Subject:

North Anna Power Station, Unit No.1, Third 10-Year Inservice Inspection Interval Program, Relief Request N 1-13-PRT-004, Part A through G (TAC Nos. ME3333, ME5136, ME5137, ME5138, ME5139, ME5140 AND ME5141)," January 7,2011

[Accession No. ML110060011]

NRC letter to FirstEnergy Nuclear Operating Company,

Subject:

Davis-Besse Nuclear Power Station, Unit 1 - Relief Request Nos. RR-A18, RR-A19, and RR-A20 for the Second 10-Year Inservice Inspection Interval (TAC No. MA7210),

June 4, 2001. [Accession No.: ML011570068]

9. References

1. ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds," July 27,1988.

2. ASME Code Case N-648-1, "Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles," September 7, 2001.

3. NRC Regulatory Guide 1.147, "Inservice Inspection Code Case Applicability, ASME Section XI, Division 1," Revision 16, October 2010.

Request RR-A36 Page 7 of 12 Reactor Vessel Weld Layout W*Axl8 Core Flood IIollle I*Axll X-AxIS OVIleI NoIII.1H--HliI=----t------tlHliil-l+l Oullet Houl, Components In this Request ~ Rc.RPV*W............RInIIde IIItIIUI

'.1'"

L..--_.,...,.....---------yJ ICoIIPV""""S-YoIR r-*--* -**-cr Radin

. I

--t-----.

I i

~t--t-.-.- .-

.

Weld In this Request -+

Weld In this Request ~

Figure 1

Request RR-A36 Page 8 of 12 Weld RC-RPV~WR-34

... ALL "'(" VAI.JJES TAICE)j FRaU IlATIXC ,SURFACE ...

'117U[II BASE IID'Al8:" (IIMTi>+

0.19, t!OW'T l' 94.41' (IIJP) 0170.113' (R8S.3)I-_ _ _ r----;

...

Z~-~I~

leer "I.f'HA !ELTA .. : 13..6Y (WN1fUM)

" .... ,~I.61

, BlofTI/2 - 4.22

".,.<~~.af.=====rf

~ ----;mni"iiii~-

waD W04 i z ~J08.J8 NOli!

I

)' (AS-BUILT -307.50)

~ Ml41

~

TCJTAL CIIIYERAGE OF' 'II£l.I)

IS UIIlIED DUE 10 WEl..O WIOni - 1.98 CCRE we OBSJRUrIICNS

~;~ '-7)

I'/IS ID: 11104 COIIf'OI\ENT ID: RC-"RPIH'IR-J+

,t,SME Imt NO.: 81.11 IISME CliTEGCRV: 8-A FlGURE~ 1WB-2:;QO-1 Figure 2A

Request RR-A36 Page 9 of 12 Weld RC-RPV-WR-34 DaTA - 15~

7.07 MAP/MAN SCANS M1P SCANS SCANNING BETWEEN CORE LUGS Figure 28

Request RR-A36 Page 10 of 12 Weld RC-RPV-WR-35

--- ----~z = -291.94 Core Guide Lug ~

TWS 10: W05 COIIPONENT 10: RC-RPll-WR-35 ASII£ ITBI NO.: Bl.l1 ASME CATEGORY: B-A ACUR£.: 1\fIB-2S00-1 0.81 (15'S1)

Instrument Nozzles ~

I I

I 0.19 i

~iL--

t(81m)

--- 'lOTAL SCAN COVERAGE OF WElD Y/05 IS ullnm DUE TO 1'oIS lNTERfIRENCE W1TH INSTRUIIENTA!DI N02ZLES AND CORE LUGS Figure 3A

Request RR-A36 Page 11 of 12 Weld RC-RPV-WR-35 IV-AXIS 18 18 40

Ie

35 41

*

J4 4Z

Jl

Incore Instrument

st

"* '*" Nozzles

Z-::IS~&m3BI--.- ____ ~ _____ +__ _____""'___

~

31

iHE:fIISo'l~*t:"

1270')

~

*~ T***

15 10 ffi "

I i~ ~

3 D i :

a 190'1

1* *

~ I ~

Core Guide Lug -+ ~ ~1 V ~

49 1

. (typical)

I I

Y-AXIS 180'

[180']

Section Through Reactor Vessel (Looking Down)

Figure 38

Request RR-A36 Page 12 of 12 Inside Radius RC-RPV*WR-54/55 .. W*IR and ..Y-IR r---Inslde Radius Section (Typ)

Approx 3" +- Core Flood Nozzle with welded Flow Restrlctor Flow Restrlctor Top View Figure 4

, ! II AttaChment' ,!! I Request RR-A36 Document No.: 51*9170868-000 Page 1 of 15 Davis Besse lO-year (17M) Reactor Vessel Weld Ultrasonic Examination Report A

A.,U.!VA RPV Weld UT Data Sheet Uliilly: FIrst Energy Plnnl: DovlsB0880 Unll: Illn 0111°0 0 : 17M I TWe Wold'Numbor: W04 CompunonllO: RC~RPV*WR.34 IISlImmo!), No.: B01,011.052200 DOBer/pilon: lower 8hoilio Bollom Hond Clrcum/orenllal Weld MK 17110 MK i8' Examlnallon I>roc~uro: ~*ISI*801*02, Automated UT of PWR Vessel SII!)II Welds. (wilh SDeN 1130-9170231,000)

Essential Equipment Description Monufaclurer Modol VHf 80rlol Numb"r Co,. Duo Dato Zoloo IITomoscon 7366 18'21*06, 81612012 lotoc IO*ChPIR 7970 RSCT10Q99110 nln UT Coble Type I Lenglh: Monlroao CBL*9847 I 28' RO-174 1.176' No. of Conlloclore: 4 UT Callbratlon/Acqulsilion Software Vorslon: AccU80~Ox* 6.6 I UJ Dala AnalysiS I Version: IAccusilnax. 3.18 Calibration Information Cal. Shoot: cos-, I Cal Block ID: Vonel RPV-95001 Equipment Settings PUI8et Source: Elllarnal Oaln80081: Nona Vollaqu: 300 D'9111101l011 RalO: 12;1; MHz Flllor,: I'MHz RF'Storo: No OalnAdJ.: SlIllJ/O Tljroahold (RO,: ,5%

Pulae Wldlh: IiOO PRModel Dual Delay: 0 TIIftIahold (CGJ: 0%

Oa/8'8Iall: *. 2rl-.16° 0&1e810p: '4.3°/9.7' ISyno. InlalVal: 0.Q8* Recl.Modo: FW 801111 8peod: 10 Ips Colncldonoe: 1 8eo attaclled dale,acqulsillon pagoa for addilionallnformdllon, ICouplenl: Wele, IVal8el Tamp: 88'F Transducers Tranedllc;er M~ufaelurar: stOml!lOEIT UT,Heed: Bluo~

~=J Ohllnb.l "'-glO Modlt Beam DlreCllolI Freq. Galfal NUmbor MOdel 811e BIIII

, 45" S ~8r/CiIC. 1.0 MHz ,08010 SfAllle:' 5508 FIa' '.rlL'~' (lQ1 POIIII 1.23" 10 ;41\" 'S Axial '-are. 1.0 MHz 08012 81g;na: 5508 FlaI' '.II'..r~I021 1;26° 3 '7'" L ,AlIBI I arc. 1.3 MHz OIMH&I GEIT: 389-042-010 .6" 1.1... 316"11121. U'da' Cal' 0.95" 4 70' l AIIIaI/.arc. 1.3 MHz OlMN8K GEIT: ~2.o10 .6' 1.6*.r..316'(1121. I.II-"WIII, O.8r 6 48' l AliIal/arc. 2.7 MHz 01MN8C' GEIT:,38~038.010 4" 1.1'ir.16'tll2, 1.02" 8 46" L Mall arc. 2.7 MHz OlT3F8 GEIT; :J89.038:OIO 4" ,,'-"'6"102, 0.&&0

.. - - .

.-

.

. .- .- .- -

- - - -

eXamInatiOn coverage I:Xamln8 .Jon R8eUl18 SOli 8e1in Plan II405tl78iJ Examlnallon 8Urf8~: ID D No RG-dablv Indk:atlons II ~'aI~fllo 1n(I1.... 'ona

,Exanilnallon Covorogai '58 % II Ewfllu,U!in ACco~,.1I16 IJ 'E,aluatlon Unaci:aplablo

~xtiinlilatlon' Liriillallolll Coro Lugs II ,8~ Atlached Flew Evalualion 8ummpry,8hlHllls)

~8mlns"on Dalolall IOIt7120'U Nilmos ofdato olllilWSIs forlllis Wotdllrolncludod on ilio allachod aMaia.

Remarks:

I . Attachment Request RR-A36 Document No.: 51-9170868-000 Page 2 of 15 Davis Besse IO-year (17M) Reactor Vessel Weld Ultrasonic Examination Report AUlIVA NP I Flaw Evaluation SummalJl Shout .1 1 Component: RC*RPV*WR*34 I Summary No.: 801.011.052200 Customer: First Energy Plant: Dallis-8esse Unit: n/a TWSWeld: W04 Flaw No.: 1 Outage: 17 M Detection Flies: B1290_19.39.07 Sizing Flies: B1290 20.33.24 Transducer Beam FlfJw Leng'" (Til eta) Flaw Deplh

AtmfelMode D/r. Min. (deg) Max.~ea} Totalfdea} Min. fin.} Max. (In) rotalllh.}

70'!. L Alpha* -72.59 -73.46 .{J,B7 0.40 0.52 0.13 Estimate of Flaw Length: (CalcuI81~ !ht;t average of all lenglh values which are considered credible)

Length: 1.31 In. *0.8.7 deg.

Estimate of Flaw Depth: (Calculate the average of all depth values which are* considered credible)

Depth (naw height); 0.12710, Radius of Curvature@ Indication: 8S.90 In.

Depth of Flaw at Max. Amp.: 0,40 In, Max.Amp.: 102 %

Max, Location: Alpha = 101.66 0 Theta = -13.25 ;

Nominal Wall Thickness: 6.1)7 In.

Nominal Clad Thickness:. 0.19 In.

Evaluation: S::: 0.2 2a::l 0;10 a= 0;10 y= 1.00 L:; 1.30 aJl= 0.05 a/t= 1.2%

MallllTiulTi Allowable alt: 2.2%

Acceptance Standard: IW8~3510*1 Code Year: 199& wi.h 96 Addenda DlsJW~l\Ion: SUBSURFACE FLAW ACCEPTABLE Comments: Values used for eVilluatlon are rounde(lln accordance with Section XI IWA*3200.

This Indication was ~rded during the previous 81Ca"mlnation This scan 19 I>arallello the weld on the veas!!1 shell.

This Indication Is located within the weld and Is Indicative of a fabrication naw typical of slag Inclusions.

Performed by: Mlohael W Key Level: III Date: 10/11111 Reviewed by: Michael G Hacker Level: III Date: 10/20/11

I, i* Attachment' !

i Request RR-A36 Document No.: 51-9170868-000 Page 3 of 15 Davis Besse 10-year (17M) Reactor Vessel Weld Ultraspnlc EXamination Report A RPV Weld UT Data Sheet Anp.VA

-- -

IJlilllv: First Energy Plan.: Davia Besso Unll: "/a Ou'ago: 17M TWS Wold Numbor: W05 Compononl 10: RC-RPV-WR-35 8I1mma",No.: 801.021.052300 Desor/pllon: Oollom tlead clrcumroronlln/*(Olool Wold MK 110 to MK 111 EXllm'n811l1n Proceduro: 54*ISI*801*02*. AlIlomaled UT of PWR Vessel Sholl Welds. (wllh SDCN 1130*91io231-000)

Essential Equipment Description Manufacluror Modal VKII Sorlol Numbar Cal. Duo Dalo Zoloc "Tornoscan 7366 18121-06 8/5120.2 Zeloa '6*CbPIR 7970 RSCTlOO99 110 nla Ur Cab/o Typo I Longlh: Mpnll'!lso COL*9847 I 28' RO*t74 I 176' I No. 01 Connoclors: 4 UTCalibrallonlAcqulslllon Soltwara Varalolll IAccusonex- 6.0 I ur Da.aAnalyBIB I Varelolll IAccusollox - 3.18 Calibration *Informatlon Cal.8bBOI: CDS*' I Cal BIocll ID: Vessel Rpv*9500t Equipment Settings Pulsar Sourco: External ODIn Bo081: NOIIa Voltago: 300 Dlglllzallon Ralo: '2.5 MHz PlllOr.: 1 MHz RFSlore: No OalnAdJ,: SInlIIa Threshold (RO): 6%

Pulso Wldlh: 600 PRModo: Dual Dolav: 0 Thillshold (CO): 0'lIt Oale8l8rt: *.2r1*.16" 0010 Slop: 14.3"/9.7" Syno. 11I101Yal: O.oa" ~c'.Modo: FW SCan Bpoed: Sips ColncldellCO:* 1 8eo IIlIlIeh.II dala acqulalllon pagal lor addillonal Information. ICOup'anl: Waiar IYessei Tamp: 881' Transduaers transducar Manufacturar: SlgmalBEiT UTHliad: Slua.1I3 MIHI,I** .Paaili. SlIIi Channal Angla MOdo Beam Dlillallo.. '~aq. Sodal Numlier Slia

, . Dept". '1!4i~'

1 45'* S MoI/Clro, toMHi O8Oto . SIgma: 6508. Flal 1.2'0.16' 1M31 '.23" 10 48" S MaUClRl; u:MHz 08012 Slomo:'6508 Flal l.r-.16*(Jia1 1.28"

'3 7\' L AIIIn,' ClIO. t3MHz D1MN8J GEIT: ~Q42-010 .6' 1.5'11.31&' (021. u*... ,6'C.., 0.95" 4 10' L AUai/eiro. t.3MHz DIMMlIK OEIT; 389-042-010 :5- 1,$'d'6'(Jia~ U""6'ldl O.8r

5. 48~ L AUal/CIrc. .U*MHz QIMNBC OEIT: :J89.038.I)10 4~ 1.1-'.76*11i2I Ul2" 8 48' l AUaI I Clrl!. .2.7 MHz Ofr3F8 .OEIT: 38M38-0IO 4" 1.1'6' (IQ) 0.88'

. - -. .- - .. - -

_.

- - . - -. - . -

Examlnatlon Ooverage Examination Results Soo*8Oan Pion 00519790 .EJcllltllnallon 8urlallO: ID CI H61DcOr1hllllO IndlbllClllt &I. Roeordablo'n4111l!\k!11e

..

Elamlnailon Cov:orago: 40% &I ~YIIIIN!i'on "",,,,abIO i:i EvaluatIon U~ID Examl""'lioil Llmllallon: Instrumontollon Nozdoo'and Core:wg8 iii 880 AllaChedFlaw Evalua1lon 8umma", Shaet(e) 8xamlnallon orllo(sl: 1011712,,11 . Namaa 0' dl!l8.a~)5la ;., thIs wBld are Includod on Iho allacllod sheela.

Remarks:

Attachment .I I Request RR-A36 Document No.: 51-9170868-000 Page 4 of 15 Davis Besse 10-year (17M) Reactor Vessel Weld Ultrasonic Examination Report AUEVA Nil I Haw Eva/llatloll Summarv Shoot I I Component: RC-RPV-WR*35 I Summary No.: 801.021.052300 Customer: First Energy Plant: Davis-Besse Unit: nla TWSWeld: W05 Flaw No.: 1 Outage: 17 M Detection Flies: 81290_03.29.57 Sizing Flies: 81290 04.33.25 Transducer 8eam Flaw Length (The to) PlowOep'h Angle/Mode 01,. Min. (deg) MaK. (den) Totol (den) Min. fin.) MIIK.J/n} To'al (In.J 45':.8 Alpha + 165.64 166.03 0.39 3.57 3.73 0.16 Estimate of Flaw Length: (Calculate the average of all length values which are considered credible)

Length: 0.64 in. 0.39 deg.

Estimate of Flaw Depth: (Calculate tlllil aVlilrageof all depth values which are considered credible)

Depth (flaw height): 0.1631".

Rf,ldluB 9'CUi'Vsture@ lildlcallon: 75.02 In.

D~th 0' FlaYtal Max, Amp,: 3.71 In.

Mill(. Amp.: 41 %

Max. Location: Alpha = 128.02 0 Theta = 1d5.64 ..

Nominal Wall Thickness: 5.57 In.

Nominal Clad Thickness, 0.19 In.

Evaluation:' 's= 1.8 28= 0.15 a= 0.10 y= 1.00 L= 0.55 s/L= 0.16 aft =I 1.5%

MalClmum Alto,WEible all: 2.9%

Acceplance,StllildiUd: IWB*351 0*1 CQdeYear: 1995 with ,06 Addends Disposition' SUBSURFACE FLAW ACCEPTABLE Comments: Vaiu~ used for evaluallon are rounded In accordanca with Section XI. IIiVA*3200.

This IndloaUon waB not recorded dUring the prBViouS eXlul1lnallon This scan Is parallel to tlie Yield oil the \laSsel sh$lI.

This Indication Is located within t~e weld and Is indica live of a fabrlcallon flaw Iyplcal 0' slag IncluslQns.

Performed by: Michael W Key Level: III Date: 10/17/11 Reviewed by: Michael G Hacker Level: III Date: 10120/11

, :: .I\Uachment' "I h *.

Request RR-A36 Document No.: 51-9170868-000 Page 5 of 15 Davis Besse lO-year (17M) Reactor Vessel Weld Ultrasonic Examination Report AREVA NP I F/ltw F.vaillfltion Summary SI,oo, I I Comp_onont: RC*RPV*WR-35 I Summary No.: 801.021.052300 Customor: Fl,rsl Energy Plant: Davis* Besse Unit: nla TWSWold: W06 Flaw No.: 2 Outago.: 17 M Detection Flies: 81290_06.16.03 Sizing Fllos: 81290 10.64.49 Transducer 8eam Flaw Length (Theta) tJlaw DfllJtlt Angle/Mode Dlr. Mln.Cdogl Malt. (degJ Totsl (dog) Mln.lln.J Malt.llnJ Totsilln.)

46'!. L Alpha" 282;93 283.49 0.56 2.10 2.20 0.10 45°- L Aipha '" 282.93 283.65 0.62 1.98 2.08 0.10 I=stlmale of Flaw Lenglh: (Calculate Ihe aver~ge of alliengih va,lues whIch are consIdered credible) lenglh: Q.7011). 0.59 deg.

E~tlma'e of Flaw Depth; (Calculate the average of all depth valuesWhIc~ are CQnsldered credible)

Oepth (naw helghl): 0.101 lit.

Radius of Curvalure@ Indication: 73.43Ih.

Depth of Flaw al. MaX, .AmP.: 2.1210.

Max. Amp.: 27;,%*

Max. Location: Alpha = 127.85*, Thola = ~~,29"o Nominal Wall Thickness; 5.57 In.

Nominal Clad Thickness: 0-19'1".

Evaluallon: S:= 1.8 2s=' 0.10 s;:: 0.00 y'-: 1.00

i.= 0.00

~~ 0.05 a~::: 1.0% I' Maximum Allowable,a1I: 2.3%

Acceptance Sland8~d:' IWB-3610-1 I 1f195*wllh l)6 Addenda eOdeYear:

DlsposlUon: SUBSURFACE FLAW ACCEPTABLE

!

Commenls: Values ..used forevalualloo.are rounded In,accordancewllh Section XI IWA-320D.

ThllUndlcslioo WasitOl'i'ecordBd during Ihe,preVloua examination This scan Is parallel 10 ttie wald,on the vessel shell.

This Indication Is localed within Iha weld and Is Indicativa of a fabrlcaUo".flaw Iyplcal of slag Inclusions.

No measureablo Ihrough-wall Oldel'll. Mlnvaluo assigned Is 0.10";

Performed by: Michael W Key Level: Dale! 10/17/11 Reviewed by: MI¢hael G Hacker Leilel:

'" Dala: 10/20/11

'"

'! . '. Attachment, I:: I Request RR-A36 Document No.: 51-9170868-000 Page 6 of 15 Davis Besse 10-year (17M) Reactor Vessel Weld Ultrasonic Examination Report AREVANP I Plliw Evalllatlo" S.lIlltUlllY Slmor I I Componont: RC-RPV*WR-35 I Summary No.: 801.021.052300 Customor: firslEnargy Plant: Davis-Besse Unit: nla TWSWold: WOil Flaw No.: 3 Outogo: 17 M Detecllon Flies: B1290_06.51.16 Sizing Fllos: B1290 10;34.08 Transducer Beam Flaw LeIJDth (TI,eta) FI&WOepth Angle/Mode Dlr. MIn. (dellJ Malt. (claD) Total (dell' Min. (In.J Max. (lnl To,ol lin.'

45'!.S Alpha + 346.99 349.30 2.31 3.29 3.40 0.11 Estimate of 'Flaw length: (Calculate the average of all length values which are considered credible) length: 3.14 In. 2.31 deg.

Estimate of FI,aw Depth: (C81culaie tha'average of all depth values whlch'ara considered C!'~ible)

Depth (Daw height): 0.112 In.

Radius of Curvature@ Indlcailon: 74.6!> In.

, Depth of Flaw at Mall, Amp.: 3.34 In.

Mtiii:. Alt!pi: 49%

Mint Location: Alpha = 125.54 0 Theta = 349;15 ~

NOn!lna! Wall Thickness; 5.57 In.

N'ilillil c;:ta~ Ttll~n~: 0.19 In; EvaluatIOn: S= 2.2, 2a= 0;10 a'" 0.00 V= 1.00.

l= 3.10 a/L= 0 81.t= 1%

Maximum Allowablea/t: 2.1% , '

AccepianceStandard: IW8-3511>-1 Coda'vear: 1995 with '96 Addenda Disposlllon: SUBSURFACE FLAW ACCEP,TABlE Comments: Values used for evallJaUiJn*are rounde(fin accordancewJth Sectlc,,"XI IWA*3200.

this Indlcatlonwas*not recorded during the Pfm/lOus examlnallon This scan Is parallei to ihe weldon the V8Sselshell.

Thls'lndication Is located within the weld and Is Indicative of.a fabrication naw,tYQlcal ofaleg InclusionS.

. PerfprRJed by: Michael W Key level: III Date: 10J.17111

~evla,,!ed by: MlchaelG Hacker level: III Date: 10/20/11

? .. 4 3 1 RR~36r---~------~~--~~~~~~~

Page 7 of 15 SCAN PENlIHCATION NUMBER Z

SZP .(Shltl) II SZN (Sholl)

WELD' ~il-DD!>!'~3 90' 270' (NUMERICAl. 01-99)

[270'] [90'1 RESERVED fOR SIZING SCANS SIP (5),,,)

P(~..!RtCAL 01-99)

SI'N(Sfiall) rtRST L£TTER IS SCAN* TY?E SECOND L£l[R !S SCAN DIRECTION 0' THIRD L£.TllH IS N..... OR C (NEGA11IIE.

I POSTIfNE, OR CUSTOM; IN THtS CASt SHCU' THrTA NtCA-rvE I

,...

1WS TOOL HEAD DESICNATION Y [ IN THIS CASE HEAD CONFlGURAnON ,3

['811'] BASED ON THE fIRST SCAN UHE OF THE PA7CH erne; StANO. If THE CONTACT HEAD DIRECTIONAL ARROW IS PaNTED IN JWS SCAN PLAN VESSEL LAYOUT THE OIRECTJON OF' THE FlRST SCAN UH£ TH[ SCAN IS CONSlO[R(J TO ae POSITM.

NOMENCLAtURE LECEND IN n-IS CASE NECATJVE. THE ARROW POINTS (USE THROUGItOUT SCAN PIA.) IN floE OPPOSITE DlRECTlON OF" THe FlRS'"

- SIlt AlaS. EITHER ** I. Y. or Z $CAN UH£

[~ : ~ ~ t:~ Igw~) '80' SCA,.'111'rP[;

L TOOL HEAD OR,ENTATION KEY S*SNU ARRmrHCADS SHOWN ARE

~ESOOATIVE or COKTAC'T HEAD ~ : ~:~~:1I01 IlREcnONAI. ARROW F

Pil)8 twtIS BESSE 1 - REEEREnq ORAWINGS EPA SCAN PI AN gpng't SCAN QIREC"nON 1041110 REV. 3 !filLET NOZZLE FORCINC 1041760 REV. , UPPER SHELL FORCING Z

ELEVATION FROU MATiNC SURFACE 1041800 REV. 3 YESSIl. F1>>ICE FORCING ('llEGATlVE DOWN INTO VESSEL) 1041840 REV. 0 . LOWER HEAD FORGING 10S292C REV. 0 0UTl.EJ NOZZlE F'ORCINC T

THETA ANeLE tROu VESSEL rr 105294(: REV.* 1 CORE FLOODING NOmE FORGING AROUND V(S5tl AXIS (NCGATM 109$210 REV. 1 LOWER SHEll. f'ORGING IS CLOCKWISE LOOKING INTO VESSEL) lQ9~22D REV. , LOWER SHEll FORGINC R _ DISTANCE FROu VE$S(l AXIS (POSITIVE 1097110 REV. 2 UIXIIFlED INSTRUIIENTATION NOZZLE DETAIL AWAY F"ROW YEssn. AXIS)

'20582C REV** LIST OF DRM'IHGS R£ACTOR YESSIl. _ OUTUHE - SIEI I TWS TOOL HEAD DESIGNATIONS B

BETA AMGIl: F"ROU NOZZLE ZERO 1499llE REV. , (TOP 000 CENTER ARO<JNO NOZZLE AXIS) 1499J.4E REV. 6 mJ) PREPS - SIEI 1 HEAD No. HAIlE usc. POSIM IS a.cannsc LOOKING INTO 152055£ 152056[

REV. 7 REV**

REACTOR COCII.ANT PFING ASSDlBLY - FUN*\tEW R£ACTOR COIIIN'T Pf'IHC ASSDISLY " El.EVATION VIEW

, fL01r SICIRT IOOL eEHlND F\.OW Stem NOZZLE FROU VESSEL.

W

DISTANCE F"ROIII NOZZLE AXIS to HOZZLE 154613£ REV. 6 ARl!AltGDlOO _ YESSIl. LONe S£CTIOII 2 lx4 TOOt H90 NOZZLES - oocello.. 1.0. SURF"AC£ OR SHEll* SCAN LIMit.

1S4614£ REV.

ARRANGEUENT REACTOR VESSEL SECTIONS (F'OSITM: IS AWAY rROW NOZZLE eENrtRUNO IMaI.5[ REV.* MATERIAL LIST HEAD a: vtssu. . l 2x3 TOOL tOO SHru - D(T[C11ON a: SIZING

--- .. A

A.LAUt. ANClE fROu TANC;(NT PaNT OF 1$4616£ 1~617[

1~61BE 1S461!JE REV.

REV. ,

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v t e Letter Sequence Other
TAC:MF0750, (Open)
Initiation Request Acceptance Administration Questions 15 November 2013 Answers 14 November 2013 Results Approval... Other: L-13-076, 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals
MONTHYEAR2013-11-15 [Table View]

L-13-076, 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals: Difference between revisions

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4. Reason for Request

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