ML021680035

Request for Review and Approval of Relief Request Nos. 15 and 16 for Monticello 3rd 10-Year Interval Inservice Inspection Examination Plan

ML021680035
Person / Time
Site:	Monticello
Issue date:	05/30/2002
From:	Forbes J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021680035 (66)

Text

NMC Monticello Nuclear Generating Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC May 30, 2002 10 CFR Part 50 Section 50.55a US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Request for Review and Approval of Relief Request Nos. 15 and 16 for the Monticello 3rd 10-Year Interval Inservice Inspection Examination Plan On November 28, 2001, Nuclear Management Company, LLC (NMC) submitted Revision 4 to the Monticello Third 10-year Inservice Inspection Examination Plan for Monticello. The purpose of this letter is to request review and approval of Inservice Inspection (ISI) Relief Requests No. 15 and 16 to the third 10-year plan.

Relief Request No. 15 addresses American Society of Mechanical Engineers (ASME),

Section XI, 1986 Edition, No Addenda, Table IWC-2412-1, Inspection Program B, which requires a distribution of welds in an examination category per interval to be 16%-34% for the first period, 50%-67% for the second period, and 100% by the end of the third period. A selection error during development of the Monticello 3 rd 10-Year Interval ISI Examination Plan created a weld inspection distribution different from that required by ASME Code,Section XI, 1986 Edition, No Addenda, Table IWC-2412-1, Inspection Program B. Therefore, Monticello Nuclear Generating Plant is requesting the use of an alternate weld inspection distribution for Category C-F-1 welds for the 3 rd 10-Year Interval ISI Examination Plan.

Relief Request No. 16 addresses Section Xl Inservice Inspections of limited examination coverage. Regulatory Guide (RG) 1.147 endorses ASME Code Case N-460 which allows greater than 90% coverage of Class 1 and 2 welds to be considered "essentially 100%

coverage." Monticello has a number of welds and components for which the essentially 100% inspected coverage as defined in RG 1.147 is not achievable, primarily due to original design and/or construction obstructions, or configuration interferences.

2807 West County Road 75 e Monticello, Minnesota 55362-9637 Telephone: 763.295.5151

• Fax: 763.295.1454

Nuclear Management Company, LLC USNRC Pacge 2 This letter contains no new NRC commitments, nor does it modify any prior commitments.

If you have any questions regarding this submittal please contact Doug Neve, Licensing Manager at (763) 295-1353.

/Jeffrey S.Forbes F Site Vice President Monticello Nuclear Generating Plant cc:

Regional Administrator-III NRC NRR Project Manager, NRC Senior Resident Inspector, NRC Minnesota Department of Commerce

MONTICELLO NUCLEAR GENERATING PLANT ISI Relief Request No. 15

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 RD 10-YEAR INTERVAL EXAMINATION PLAN ISl RELIEF REQUEST NO. 15 Class 2 Austenitic Piping Weld Examination Schedule SYSTEM/COMPONENT(S) FOR WHICH RELIEF REQUEST WILL BE USED Code Class:

Class 2

Reference:

ASME, Section Xl, 1986 Edition, No Addenda Table IWC-2412-1 Inspection Program B and Table IWC-2500-1 Category C-F-1 Note (2)

Examination Category:

C-F-1 Item Number:

C 5.10, C5.1 1 and C5.12.

==

Description:==

Pressure retaining welds in austenitic Stainless Steel Component Numbers:

All CODE REQUIREMENT American Society of Mechanical Engineers (ASME) Code, Section Xl, 1986 Edition, No Addenda Table IWC-2412-1 Inspection Program B requires a distribution of welds in an examination category per interval to be 16%-34% for the first period, 50%-67% for the second period, and 100% by end of 3 rd period.

ASME Section Xl, 1986 Edition, No Addenda, Table IWC-2500-1 for Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel, Note (2), requires the welds selected for examination shall include 7.5%, but not less than 28 welds, of all austenitic stainless steel of high alloy welds not exempted by IWC-1220.

BASIS FOR RELIEF REQUEST During the development of the 3rd IS, interval inspection plan a total of 5 C-F-1 welds were selected for examination out of a total count of 31 C-F-1 welds on the Control Rod Drive (CRD) Discharge System A and B. This initial selection satisfied the required 7.5% selection criteria of Table IWC 2500-1 C-F-1 but did not satisfy the second selection criteria of a minimum of 28 welds that needed to be inspected during the ten-year interval. During development of the Monticello Risk Informed Program and prior to the last scheduled refueling outage of the 3 rd In-service Inspection (ISI) interval, it was identified that the Category C-F-1 weld selection for the 3 rd Interval ISI plan was required to be 28 welds and not just the 5 welds previously selected. The 3 rd Interval ISI plan was immediately corrected and the additional C-F-1 welds were selected and examined during the last 3 rd interval refueling outage in December of 2001 to insure that 28 C-F-1 welds were examined during the 10-year interval. The late discovery of the initial selection error made it impossible to readjust the weld distribution per period to conform to the requirements of Table IWC-2412-1 Inspection Program B.

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 RD 10-YEAR INTERVAL EXAMINATION PLAN ALTERNATIVE EXAMINATION Pursuant to 10 CFR 50.55a(a)(3)(i) relief is requested to allow a weld inspection distribution during the 3 rd 10-Year ISI program interval for Category C-F-1 welds of 10% (1st Period),

14% (2 nd Period) and 100% (3 rd Period). These examinations were performed during the 3 rd 10-Year ISI inspection interval.

JUSTIFICATION FOR GRANTING RELIEF Monticello has a total of 31 Category C-F-1 welds. All of the welds are on the CRD Discharge System A and B. Monticello completed the last refueling outage of the 3 rd 10 Year Interval in December 2001. A total of 28 Category C-F-1 welds were examined during the Interval in accordance with code requirements. Recently, Monticello has submitted to the NRC a Risk Informed ISI Program Plan for Class 1 and Class 2 piping welds for the 4 th 10 Year Interval ISI Plan. The risk ranking and degradation analysis of the risk informed program has identified all these C-F-1 subject welds to be risk category 6 or risk category 7 in accordance with EPRI topical TR-1 12657 Revision B-A. As a result none of these welds have been selected for ISI examination during the 4 th Interval. The inspection results for all 28 welds during the 3rd interval indicated no detectable flaws or degradation on these welds.

Therefore, the proposed alternative examination above provides an acceptable level of quality and safety.

IMPLEMENTATION SCHEDULE Alternative Examination is requested for the 3 rd Ten-Year Interval of the ISI Program for Monticello.

REFERENCE NMC letter to the NRC, "Risk-Informed Inservice Inspection Program Plan for the Monticello Nuclear Generating Plant," dated December 17, 2001.

MONTICELLO NUCLEAR GENERATING PLANT ISI Relief Request No. 16

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 PRD 10-YEAR INTERVAL EXAMINATION PLAN ISI Relief Request No. 16 Limited Examination SYSTEM: Various Class: 1 Category: Various Item: Various Impractical Examination Requirements:

American Society of Mechanical Engineers (ASME) Code, Section Xl (1986 no addenda) requires examination of essentially 100% of weld length for In-service Inspection (ISI) of components per Table IWB-2500-1. Regulatory Guide (RG) 1.147, Revision 12, endorses ASME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds." This code case allows greater than 90% coverage of a weld to meet the "essentially 100%" requirement.

NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) In-service Inspection Requirements," dated December 1, 1998, states "The NRC has adopted and further refined the definition of "essentially 100 percent' to mean greater than 90 percent" in 10 CFR 50.55a(g)(6)(ii)(A)(2) for required examination coverage of reactor pressure vessel welds.

This standard has been applied to all examination of welds or other areas required by ASME Section Xl.

This relief request is submitted in accordance with a commitment made in NSP Letter to the NRC dated March 24, 1997 titled "LER 97-004 'Failure to Submit Relief Requests for Limited In-service Inspections Examinations'." The commitment stated that required relief requests will be submitted for all limited examinations performed in the future.

This facility was designed and constructed with limited accessibility. Due to component configurations and/or physical barriers and interference, essentially 100% inspection coverage as defined in RG 1.147 is not achievable on some ISI components examined for the Third Ten Year Interval.

Basis for Relief:

The following 10 CFR 50.55a paragraphs apply to the in-service inspection of components in accordance with the ASME Section Xl code:

50.55a(g)(1): For a boiling or pressurized water-cooled nuclear power facility whose construction permit was issued prior to January 1, 1971, components (including supports) must meet the requirements of paragraphs (g)

(4) and (5) of this section to the extent practical.

50.55a(g)(4): Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and pre-service examination requirements, set forth in Section Xl of editions of the ASME Boiler and Pressure Vessel Code... to the extent practical within the limitations of design, geometry and materials of construction of the components.

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 RD 10-YEAR INTERVAL EXAMINATION PLAN 50.55a(g)(5)(iv): Where an examination requirement by the code or addenda is determined to be impractical by the licensee and is not included in the revised in-service inspection program as permitted by paragraph (g)(4) of this section, the basis for this determination must be demonstrated.to the satisfaction of the Commission...

Monticello was designed and constructed prior to development of ASME XI, therefore, plant and component design and layout for inspection coverage required by ASME Section Xl Code, in many cases, is not sufficient to permit satisfying the current code requirements.

Inspection limitations are primarily due to obstructions and configuration interference.

The summary of limited examinations is described below and is also included in Table 1 (attached).

Part A: Category B-A, "Pressure Retaining Welds in Reactor Vessel" Category B-A, Item B1.21, Summary Number 102638, Component VCBB-1, Bottom Head to Reactor Vessel Weld: The volumetric examination, as required by Table IWB 2500-1, was limited to approximately 5.9% of total weld area. The volumetric examination is limited by the installation of permanent insulation between reactor vessel wall and biological shield. The only access to the weld is through the biological shield window for reactor vessel nozzle N1 B (and N1A) which have a small area of insulation that is considered as a removable design. This limited access makes just 6 ft 8 inches of weld length available for examination from a single side of the weld only.

Previous examinations from the 1994 Refueling Outage indicate that 5 ft 10 in of weld VCBB 1 was accessible for examination through the N1A Nozzle Window, which equates to approximately 5.1% of the total weld length.

The examination coverage for Weld VCBB-1, combining the two examinations performed during the 3 rd 10-Year Interval, totals approximately 11%.

Category B-A, Item B1.12, Summary Number 102642, Component VLAA-1, Reactor Vessel Longitudinal Weld: The volumetric examination, as required by Table IWB-2500-1, was limited to approximately 80.1% of weld length. The volumetric examination (V-scan) was limited by available technology for in-vessel ultrasonic (UT) delivery tooling, the span distance between re-circulation jet pump diffusers and their proximity to the reactor vessel wall, and the interference of the jet pump instrumentation lines. The UT tool head is 5.5" in width and 9.5" in height. The UT instrument head rotates 90 degrees to obtain a V-scan across the weld. The span distance between re-circulation jet pump diffusers was less than the 9.5" UT instrument head, so the UT scan was not possible from the internal surface of reactor vessel. This longitudinal weld was not accessible from the outside diameter (OD) of the reactor vessel due to biological shielding and no nearby nozzle access windows being available. The reactor vessel has a total of eight longitudinal welds: six of these welds were examined "essentially 100%", while two welds (VLAA-1 and VLAA-2) had greater than 75%

coverage. Cumulatively, (all eight longitudinal welds) greater than 90% of longitudinal weld length was examined.

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 RD 10-YEAR INTERVAL EXAMINATION PLAN Category B-A, Item B1.12, Summary Number 102643, Component VLAA-2, Reactor Vessel Longitudinal Weld: The volumetric examination, as required by Table IWB-2500-1, was limited to approximately 75.8% of weld length. The volumetric examination was limited by available technology for in-vessel UT delivery tooling, the span distance between re circulation jet pump diffusers and their proximity to the reactor vessel wall, and the interference of the jet pump Instrumentation Lines. The UT tool head is 5.5" in width and 9.5" in height. The UT instrument head rotates 90 degrees to obtain a V-scan across the weld.

The span distance between re-circulation jet pump diffusers was less than the 9.5" UT instrument head, so the UT scan was not possible from the internal surface of reactor vessel.

This longitudinal weld was not accessible from the OD of the reactor vessel due to biological shielding and no nearby nozzle access windows being available. The reactor vessel has a total of eight longitudinal welds: six of these welds were examined "essentially 100%", while two welds (VLAA-1 and VLAA-2) had greater than 75% coverage. Cumulatively, (all eight longitudinal welds) greater than 90% of longitudinal weld length was examined.

Part B: Category B-D, "Full Penetration Welds of Nozzles in Vessels" Category B-D, Item B3.90, Summary numbers 102654 (N-1B NV), 102656 (N-2A NV),

102658 (N-2B NV), 102674 (N-2K NV) and 102698 (N-8B NV), Reactor Vessel Nozzle Welds: Each weld was limited to approximately 62.3% volumetric UT coverage due to vessel-to-nozzle weld configuration which physically precludes application of the required scan angles on the nozzle side of the weld. No additional alternative examinations are currently available to achieve the required volumetric coverage.

Part C: Category B-J, "Pressure Retaining Welds in Piping".

Category B-J, Item B9.10, Summary Number 102161, W-22 (LSUD): This weld on Recirculation Manifold B was limited to a single sided examination due to the pipe-to-tee configuration. The material type for this weld is austenitic stainless steel. Performance Demonstration Initiative (PDI) examination techniques are only qualified for the accessible side of the weld on a single side examination of austenitic stainless steel. Regulations included in 10 CFR 50.55a(b)(2)(xv)(A), 10 CFR 50.55a(b)(2)(xv)G and 10 CFR 50.55a(b)(2)(xvi), define new requirements for coverage and qualification demonstration of UT methods. These requirements affect both piping and reactor pressure vessel examinations. The PDI UT methodology is in agreement with the Federal Code regarding single side access for piping. The Federal Code requires that, if access is available, the weld shall be scanned in each of the four directions (parallel and perpendicular to the weld) where required. Additionally, 100% coverage credit may be taken for single side exams on ferritic piping. However, for austenitic piping, a procedure must be qualified with flaws on the inaccessible side of the weld. The final rule requires that single side access examinations must demonstrate "equivalency to two sided examinations." Current technology is not fully capable of reliably detecting or sizing flaws on the inaccessible side of an austenitic weld for configurations common to US Nuclear applications. Instead of a full coverage, single side qualification, PDI offers a best effort approach, which demonstrates that the best available

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN technology is applied. This best effort approach does not meet the requirements of the Federal Code. PDI Performance Demonstration Qualification Summary (PDQS) austenitic piping certificates acknowledges the limitation that single side examination is performed on a best effort basis. This requires the inaccessible side of the weld to be listed as an area of no coverage. It should be noted that the surface examination for this weld had no limitations and was completed with 100% coverage.

Table 1.

Code System ISO Component / Method Limitation Category / Item #

Summary Coverage No.

B-A B1.21 Reactor ISI Fig 4 VCBB-1 UT 5.85%

Weld Covered Vessel by permanent (102638) insulation. See attached report 2001 U312 B-A B1.12 Reactor ISI Fig 4 VLAA-1 UT 80.1%

Access to weld Vessel restricted by Jet (102642) pump Diffuser and available tooling. See attached report 2001VE301 B-A B13.12 Reactor ISI Fig 4 VLAA-2 UT 75.8%

Access to Weld Vessel restricted by Jet (102643)

Pump Diffusers and available tooling. See attached report 2001VE302 B-D B3.90 Reactor ISI Fig N-i B NV UT 62.32%

Limited due to Vessel

5.

(102654) nozzle configuration.

See attached report 2001U329

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN Code System ISO Component / Method Limitation Category / Item #

Summary Coverage No.

B-D B3.90 Reactor ISI Fig N-2A NV UT 62.32%

Limited due to Vessel

5.

(102656) nozzle configuration.

See attached report 2001 U331 B-D B3.90 Reactor ISI Fig N-2B NV UT 62.32%

Limited due to Vessel

5.

(102658) nozzle configuration.

See attached report 2001U332 B-D B3.90 Reactor ISI Fig N-2K NV UT 62.32%

Limited due to Vessel

5.

(102674) nozzle configuration.

See attached report 2001 U330 B-D B3.90 Reactor ISl Fig N-8B NV UT 62.32%

Limited due to Vessel

5.

(102698) nozzle configuration.

See attached report 2001 U328 B-J B9.10 Recirc ISI-W-22 LS UD UT 50%

Single Side Manifold 97006-B Examination-PDI B

(102161) procedure not qualified for flaw detection on far side of weld.

Configuration limited exam.

See attached report 2001 U321

NUCLEAR MANAGEMENT COMPANY, LLC INSERVICE INSPECTION MONTICELLO, 3 RD 10-YEAR INTERVAL EXAMINATION PLAN Additional Means of Establishing Integrity:

In addition, functional pressure tests and visual examinations (VT-2) are performed during regular inspection intervals to ensure the piping system and vessel is capable of maintaining pressure integrity. Where required by code surface examinations have been performed.

System integrity is monitored continuously during normal operation by routine operator rounds during shift and remote monitoring methods (e.g., containment radiation monitoring, containment air monitoring, containment leakage detection and monitoring, and containment temperature monitoring, etc.).

Alternate Examination:

All in-service inspections on these components have been done to the greatest extent practical. No further alternative methods are proposed or recommended beyond the techniques already applied.

The Monticello In-Service Inspection Program Plan will continue to document the limitations.

Attachments:

1) UT Vessel examination report 2001 U312, Summary No. 102638

2) UT Pipe Weld examination report 2001U321, Summary No. 102161

3) UT Vessel examination report 2001 U329, Summary No. 102654

4) UT Vessel examination report 2001 U331, Summary No. 102656

5) UT Vessel examination report 2001 U332, Summary No. 102658

6) UT Vessel examination report 2001 U330, Summary No. 102674

7) UT Vessel examination report 2001 U328, Summary No. 102698

8) Reactor Vessel Longitudinal Weld VLAA-1 report 2001VE301, Summary No. 102642

9) Reactor Vessel Longitudinal Weld VLAA-2 report 2001 VE302, Summary No. 102643

10) Support diagrams / sketches for attachments 9 and 10

References:

NRC Letter 8-4-99 "MNGP-Evaluation of Relief 10 for 3 rd 10 year ISI Program Plan. (TAC No. MA3397).

NRC Letter 10-25-2000 "MNGP-Evaluation of Relief 11 for 3 rd 10 year ISI Program Plan. (TAC No. MA9914).

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 1 REPORT 2001U312 Summary No. 102638

I1-p Site/Unit:

NSP I

Summary No.:

1 Examination For:

UT Vessel Examination Procedure:

ISI-UT-3B Procedure Revision/FC:

0

/

Work" Orrder HM- %

nCAMi-*N MI 02638 Report No.:

2001 U312 Page:

I of 181 Applicable Code: 1986 ISO Drawing No.:

1S1 Fig 4 Location:

Reactor Vessel

==

Description:==

B. HeadNessel System ID: Reactor Vessel Component ID: VCBB-1 Size/Length:

6' 8" Thickness/Diameter:

6.25" Limitations: See Comments Start Time:

14:48 Finish Time:

15:35 Examination Surface:

Inside []

Outside []

Surface Condition: Blended Lo Location:

180 Degree Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 95243 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 144 Surface Temp.:

95

'F Cal. Sheet No.:

2001CA313 Angle Used 0

45 45T 60 60T Scanning dB Indication(s):

Yes -]

No [

Scan Coverage:

Upstream []

Downstream []

CW.]

CCW W Comments:

• Scanned at 20 - 30% noise level. Examined 6' 8" at NIB window access. Upstream scan performed In 4 directions, shell side from centerline. No scan head side due to permanent insulation. Total examination area = 50% of required(F,i.-&,

Acc*s,-L*

Results:

NAD F]

IND F]

GEO -]

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level,,,-PD, Signatur Date Reviewer nature Date Davis, Layn R.

/

11/1212001 Clay, Sean P.

/

1/- 17-0 (

Examiner Level

-Date Site Review Date Newgard, Jerry W.

1111212001 Deopere, Richard A.

/

7--if/(O Other Level N/A Si ghature Date ANII Review igpture Date N/A

/

Clow, Ron A/

-1

Supplemental Report Report No.:

2001U312 Page:

2 of

-243 0`

Summary No.: 102638 Examiner: Davis, Layn R.

Examiner: Newgard, Jerry W.

Other:

NIA Level: III-PDI Reviewer: Clay, Sean P.

Level: I1.PWt Site Review: Deopere, Richard A.

Level:

NIA ANII Review: Clow, Ron Date:.i-/LL*

Date: I. iz, 01 Date:,.e,,/,

Comments:

None Sketch or Photo:

G:\\IDDEAL50\\MNGPRFO2001\\MNGP SUPPL UT\\2001U312_1.bmp 3' lii

H-I-

,I'

$d I P)S U L W-T 10 A3

&W UIS 1

LA L.

]:M SLAL.

I

't 80o"

-pDetermination of Percent Coverage for UT Examinations - Vessels Site/Unit:

NSP I

MI Summary No.:

102638 Examination For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001U312 ISI-UT-3B Page:

3 of 3

0

/

0105401 0 den Planar

% Length X

% volume of length / 100 =

% Length X

% volume of length / 100 =

% Length X

% volume of length / 100 =

% Length X

% volume of length / 100 =

% Length X

% volume of length / 100 =

"% total for 0 deg

"% total for Scan 1

% total for Scan 2

% total for Scan 3

% total for Scan 4

% total for 45 deg Scan 1 11.730

% Length X Scan 2 0.000

% Length X Scan 3 11.730

% Length X Scan 4 11.730

% Length X Add totals and divide by # scans =

100.000

% volume of length / 100 =

0.000

% volume of length / 100 =

50.000

% volume of length / 100 =

50.000

%-volume of length / 100 =

5.865

% total for 60 deg 11.730 0.000 5.865 5.865

"% total for Scan I

"% total for Scan 2

% total for Scan 3

% total for Scan 4 Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 5.865

% Total for complete exam (BASE.D ON ENIRE CkRMMFFENE4kL LE tj ck1 T"AF.- "e:rr*,.c* V¥A-TO- \\)CF-L ~Miq*

)__,Z Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:

Date:

l 25i O

Scan 45 deg Scan 1 Scan 2 Scan 3 Scan 4 Add totals and divide by # scans =

Other decq 60 Date:

• t2C/)

Site Field Supervisor:

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 2 REPORT 2001U321 Summary No. 102161

IUP Site/Unit:

NSP

/

M1 Summary No.:

102161 Examination For:

ISI UT Pipe Weld Examination Procedure:

Procedure Revision/FC:

Work Order No.:

IS I-UT-16A 0105396 Report No.:

2001 U321 Page:

1 of 4

Applicable Code: 1986 ISO Drawing No.:

ISI-97006-B Location:

Drywell

==

Description:==

Tee-to-Pipe System ID: Recirc Manifold B Component ID: W-22 LS-U&rD "ai Size/Length:

1.2"742.0" Thickness/Diameter:

.688"112.0" Limitations: Single sided due to Tee-Pipe configuration Start Time:

17:00 Finish Time:

18:00 Examination Surface:

Inside E]

Outside i3 Surface Condition: Blended Lo Location:

Outside of Tee Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 144 Surface Temp.:

80

'F Cal. Sheet No.:

2001CA325, 2001CA326 Angle Used 0

45 F45T 60 45RL Scanning dB N/A 50.0 44.0 56.0 Indication(s):

Yes [ j No [

Scan Coverage:

Upstream []

Downstream R]

CW []

CCW [l Comments:

No scans axial or circ on the upstream side of weld due to Tee configuration. Examination performed from the weld and the downstream side of the weld only.

Results:

NAD 1 IND 7]

Percent Of Coverage Obtained > 90%:

GEO -

No Reviewed Previous Data:

Yes Examiner Level II-PDI

)

Sjgnt*r Date Reviewer

,Signature Date Griebel, David M.

/

11/812001 Clay, Sean P.

I

- /9-c /

Examiner Level NIA Signature Date Site Review Signature Date N/A

/

Deopere, Richard A.

/3-

/-./o I

Other Level NIA Signature Date ANII Review Si nature Date N/A I

/ e,,

4 -2j._

4'.

l'3/V

&W Site/Unit:

NSP

/

MI Summary No.:

102161 Examination For ISI Limitation Record Procedure:

ISI-UT-1 6A Procedure RevisionlFC:

1

/

Work Order No.:

0105396 Report No.:

2001U321 Page:

2 of 4

Description of Limitation:

Single sided exam - Procedure ISI.UT.16A is not qualified for the detection of flaws on the far side of single side access exams.

The techniques provided by this procedure were used for a BEST EFFORT EXAMINATION for flaws on the far side of the weld.

Sketch of Limitation:

G:\\IDDEAL50\\MNGPRFO2001W¶NGP SUPPL UT\\2001 U321.bmp E1X414 7V 72":9, VI-2?.1 Limitations removal requirements:

None Radiation field:

300 mr Examiner Level 11-PDI fS ngnaie ate Reviewer ture Date Griebel, David M.

/

1f 1/8/2001 Clay, Sean P.

/

Examiner NIA Signature Date Site Review Signature Date N/A I

Deopere, Richard A.

Iý "/61 Other Level N/A Signature Date ANII Review Sign t

i1/,

D te NIA 7",;

4I7-,

'j)

Supplemental Report Report No.:

2001 U321 Page:

3 of 4

Summary No.: 102161 Examiner: Griebel, David M.

6 Examiner:

N/A Other: N/A Level: II-PDI Reviewer: Clay, Sean P.

Level:

N/A Site Review: Deopere, Richard A.

Level:

N/A ANII Review:

Date: I-19-O(

Date: __/_____

Date:,l___'_0/

Comments:

50% coverage achieved Sketch or Photo:

G:\\IDDEAL50\\MNGPRFO2001WINGP SUPPL U1\\2001U321_1.bmp aLzO W/

T-EE J -I

\\A'ELD."

RRif R-s

-p P/Ph ir EO VEII* KPLOD 7--

KU Determination of Percent Coverage for UT Examinations - Pipe Site/Unit:

NSP

/

M1 Summary No.:

102161 Examination For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001 U321 ISI-UT-16A Page:

4 of 4

0105396 0.000

% Length X 100.000

% Length X 50.000

% Length X 50.000

% Length X 100.000 100.000 100.000 100.000

% volume of length / 100 =

% volume of length / 100 =

% volume of length /100 =

% volume of length / 100 =

0.000 100.000 50.000 50.000

% total for Scan 1

% total for Scan 2

% total for Scan 3

% total for Scan 4 Add totals and divide by # scans =

50.000

% total for 45 deg Other deg -

45 (to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans.

0.000

% Length X 100.000 0.000

% Length X 100.000 0.000

% Length X 0.000 0.000

% Length X 0.000

"% volume of length / 100 =

"% volume of length / 100 =

"% volume of length / 100 =

"% volume of length / 100 =

0.000

% total for Scan 1 0.000

% total for Scan 2 0.000

% total for Scan 3 0.000

% total for Scan 4 Percent complete coverage Add totals for each scan required and divide by # of scans to determine; 50.000

% Total for complete exam Site Field Supervisor:

-ZŽ Date:

ti "ZI 45 deg Scan 1 Scan 2 Scan 3 Scan 4 Scan 1 Scan 2 Scan 3 Scan 4

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 3 REPORT 2001 U329 Summary No. 102654

F" Site/Unit:

NSP

/

M1 Summary No.:

102654 Examination For:

ISI UT Vessel Examination Procedure:

ISI-UT-3A Procedure Revision/FC:

8

/

Work Order No.:

0105401 Report No.:

2001U329 Page:

1 of 4

Applicable Code: 1986 ISO Drawing No.:

ISI Fig 5 Location: Reactor Vessel

==

Description:==

N-1 B Vsl/Noz Weld System ID: Reactor Vessel Component ID: N-1B NV Size/Length:

28.0" /100.0" Thickness/Diameter:

5.55" / 28.0" Limitations: Nozzle Configuration Start Time:

14:01 Finish Time:

15:30 Examination Surface:

Inside []

Outside []

Surface Condition: Ground Flush Lo Location:

Top Dead Center Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 176 Surface Temp.:

85

°F Cal. Sheet No.:

2001 CA336, 2001CA337, 2001CA338 Angle Used 0145 45T 60 60T Scanning dB 45.2 51.0 51.0 58.3 58.3 Indication(s):

Yes []

No []

Scan Coverage:

Upstream []

Downstream []

CW []

CCW ov Comments:

See attached coverage plots.

Results:

NAD []

IND 7]

GEO [

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level II-PDI Signature Date Reviewer "nre Date Loredo, Quirino

/

1111012001 Clay, Sean P.

/

Examiner Level IIR S!29.ture Date Site Review "Signature Date Thompson, Lee i

4*A

.A.4. /

4 11110/2001 Deopere, Richard A.

I A;0/0(

Other Level N/A Signature Date ANII Review nafure Date N/A I Clow, Ron

/

111?d1/, /

Supplemental Report

&p Summary No.: 102654 Examiner: Loredo, Quirino 4zz Examiner: Thompson, Lee Other:

NIA Level: I1-PDI Reviewer: Clay, Sean P.

Level:

IIR Site Review: Deopere, Richard A.

Level:

NIA ANII Review: Clow, Ron 2001 U329 2

of 4

Date: I7-2o-o Date:

Date:,/t J Comments:

None Sketch or Photo:

G:\\IDDEAL50\\MNGPRFO2001\\MNGP SUPPL UT\\2001U3291.bmp Report No.:

Page:

Limitation Record Site/Unit:

NSP

/

MI mary No.:

102654 ation For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 8

/

0105401 Report No.:

2001 U329 Page:

3 of 4

Description of Limitation:

Nozzle Configuration.

Sketch of Limitation:

GAIDDEAL50OINGPRFO20011 MNGP SUPPL UTW2001 U329_2.bmp eo vcgA'/6 PLO r Limitations removal requirements:

NIA Radiation field:

Examiner Level I1-PDI Sign re Date Reviewer 5., nS tyre Date Loredo, Quirino

/

11110/2001 Clay, Sean P.

/

) 1-10-0-o I Examiner Level IIR Z

S3gnature Date Site Review

( Signat Date Thompson, Lee

/,&'E'.

0',* '11/1012001 Deopere, Richard A.

ii/.9 O)

Other Level N/A Signature" Date ANII Review Date NIA

/

Clow, Ron

/

//,,

Sum Examin MP

Determination of Percent Coverage for UT Examinations - Vessels Site/Unit:

NSP I

MI Summary No.:

102654 Examination For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001U329 ISI-UT-3A Page:

4 of 4

8

/

0105401 0 deg Planar Scan 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for 0 deg 45 deg Scan 1 100.000

% Length X 90.500

% volume of length / 100 =

90.500

% total for Scan 1 Scan 2 100.000

% Length X 27.800

% volume of length /100 =

27.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

62.075

% total for 45 deg Other deg 60 Scan 1 100.000

% Length X 92.800

% volume of length / 100 =

92.800

% total for Scan 1 Scan 2 100.000

% Length X 16.800

% volume of length / 100 =

16.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

59.900

% total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 62.325

% Total for complete exam Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:

Date:Date:

Site Field Supervisor:

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 4 REPORT 2001 U331 Summary No. 102656

MP" Site/Unit:

NSP

/

M1 Summary No.:

102656 Examination For:

ISI UT Vessel Examination Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 8

I 0105401 Report No.:

2001U331 Page:

1 of 4

Applicable Code: 1986 ISO Drawing No.:

ISI Fig 5 Location:

Reactor Vessel

==

Description:==

N-2A Noz1Vsl Weld System ID: Reactor Vessel Component ID: N-2A NV Size/Length:

12.0" 150.26" Thickness/Diameter:

5.55" / 12.0" Limitations: Nozzle Configuration Start Time:

12:31 Finish Time:

13:30 Examination Surface:

Inside LJ Outside W Surface Condition: Ground Flush Lo Location:

Top Dead Center Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 176 Surface Temp.:

85

'F Cal. Sheet No.:

2001 CA342, 2001CA343, 2001CA344 Angle Used 0

45 45T 60 60T Scanning dB 45.2 61.0 51.0 58.3 58.3 Indication(s):

Yes L-No []

Scan Coverage:

Upstream J] Downstream []

CWW[

CCWI[]

Comments:

See attached coverage plots.

Results:

NAD -]

IND7J GEO Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level 1I-PDI Signature Date Reviewer ature Date Loredo, Quirino

/

1111112001 Clay, Sean P.

a z

11--a -6 (

Examiner Level II-PDI

• r.

Date Site Review Date Griebel, David M.

/11/11/2001 Deopere, Richard A.

I 1J 1 Other Level NIA Signate Date ANII Review re D

N/A I Clow, Ron 11I'

/

7101

Supplemental Report Report No.:

2001 U331 Page:

2 of 4

Summary No.: 102656 Examiner: Loredo, Quirino Examiner: Griebel, David M.

01W&,

Other:

N/A Level: Il.PDI Reviewer: Clay, Sean P.

Level: 11-PDI Site Review: Deopere, Richard A.

Level:

N/A ANII Review: Clow, Ron Date: U -Of Date:,t/'Z &/of Date: _///_7__/

Comments:

None Sketch or Photo:

G:\\IDDEAL50WINGPRFO2001\\MNGP SUPPL UT\\2001U331_1.bmp

.1' Ip

MI Site/Unit:

NSP

/

M1 Summary No.:

102656 Examination For:

ISI Limitation Record Procedure:

ISI-UT-3A Procedure Revision/FC:

Work Order No.:

Report No.:

2001 U331 Page:

3 of 4

0 /

0105401 Description of Limitation:

Nozzle Configuration Sketch of Limitation:

G:\\IDDEAL50VMNGPRFO2001\\MNGP SUPPL UT\\2001 U331_2.bmp

¢.

FLow L*V',*&6A PLO 7 tsj2 0

D N

.K P

'/z SCALE Limitations removal requirements:

N/A Radiation field:

Examiner Level lI-PD!

Signature Date Reviewer SignaDate Loredo, Quirino

/

11/1112001 Clay, Sean P.

I1-20-011 Examiner Level I.I.pDj S

j Date Site Review Signature Date Griebel, David M.

I

//

11/2001 Deopere, Richard A.

I Other Level N/A Signature Date ANII Review

,-ý ure%

Date N/A

/

Clow, Ron

/

/12 7_1,

e Determination of Percent Coverage for UT Examinations -Vessels Report No.:

2001U331 Site/Unit:

NSP I

M1 Procedure:

ISI-UT-3A Page:

4 of 4

Summary No.:

102656 Procedure Revision/FC:

8 I

Examination For:

ISI Work Order No.:

0105401 0 deg Planar Scan 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for 0 deg 45 deg Scan 1 100.000

% Length X 90.500

% volume of length / 100 =

90.500

% total for Scan 1 Scan 2 100.000

% Length X 27.800

% volume of length / 100 =

27.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

62.075

% total for 45 deg Other deg 60 Scan 1 100.000

% Length X 92.800

% volume of length / 100 =

92.800

% total for Scan 1 Scan 2 100.000

% Length X 16.800

% volume of length / 100 =

16.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

59.900

% total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 62.325

% Total for complete exam Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:

_Date:

i__(/24a Ot

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 5 REPORT 2001 U332 Summary No. 102658

Site/Unit:

NSP

/

M1 Summary No.:

102658 Examination For:

ISl UT Vessel Examination Procedure:

Procedure RevisionlFC:

Work Order No.:

ISI-UT-3A 0105401 Report No.:

2001U332 Page:

1 of 4

Applicable Code: 1986 ISO Drawing No.:

ISI Fig 5 Location:

Reactor Vessel

==

Description:==

N-2B Noz I Vs] Weld System ID: Reactor Vessel Component ID: N-2B NV Size/Length:

12.0" 1 50.26" Thickness/Diameter:

5.55" / 12.0" Limitations: Nozzle Confliguration Start Time:

13:46 Finish Time:

14:45 Examination Surface:

Inside D-Outside []

Surface Condition: Ground Flush Lo Location:

Top Dead Center Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Sedal No.:

NSP 176 Surface Temp.:

85 oF Cal. Sheet No.:

2001 CA345, 2001 CA346, 2001CA347 Angle Used 0

45 45T 60 60T Scanning dB 45.2 51.0 51.0 58.3 58.3 Indication(s):

Yes [j No Rj Scan Coverage:

Upstream W Downstream *j CW L.]

CCW RI Comments:

See attached coverage plots.

Results:

NAD []

IND []

GEO E]

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level I-PDI--

Signature Date Reviewer Sg Qj Date Loredo, Quirino I/

1111112001 Clay, Sean P.

1 5.

I Examiner Level II-PDI Sign e

Date Site Review

.Signature Date Griebel, David M.

/

11/11/2001 Deopere, Richard A.

/

0..,11,/

Other Level N/A Signatur Date A NR IISgnatre Date NIA T

ASiRvi

Supplemental Report Mp Summary No.: 102658 Examiner: Loredo, Quirino Examiner: Griebel, David M.

Other:

NIA Level: Il-PDI Reviewer: Clay, Sean P.

Level: II-PDl Site Review: Deopere Richard A.

Level:

NIA ANII Review: =":

U______

2001U332 2

of 4

Date:

Date: _t/_'z___

Date:

)2 Comments:

None Sketch or Photo:

G:\\IDDEAL50W1NGPRFO2001MNGP SUPPL UT'r201U332..1.bmp

• 1 A I I'

-co B C Report No.:

Page:

D

hkpý Site/Unit:

NSP

/

MI Summary No.:

102658 Examination For:

ISI Limitation Record Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 8

/1--4 0105401 Report No.:

20011U332 Page:

3 of 4

Description of Limitation:

Nozzle Configuration Sketch of Limitation:

G:\\IDDEAL50WMNGPRFO2001\\MNGP SUPPL UT\\2001 U332_2.bmp e6 LO L£aV("AR'*-

PL.n F 0

N K

P ts/2 YZ SCALE Limitations removal requirements:

N/A Radiation field:

Examiner Level II-PDI Signature Date Reviewer Vinature Date Loredo, Quirino 11/1112001 Clay, Sean P.

N'?

"OD Examiner Level Il-PD Sigte Date Site Review Signatur Date Griebel, David M.

I a

11/1112001 Deopere, Richard A.

/

Other Level N/A Signature Date ANII Re'ew,,

Signat re 1 Dat1 N /A

/

I /

ihy

W Determination of Percent Coverage for UT Examinations - Vessels Site/Unit:

NSP

/

MI Summary No.:

102658 Examination For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001U332 ISI-UT-3A Page:

4 of 4

8 1

0105401 0 deg Planar Scan 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for 0 deg 45 deg Scan 1 100.000

% Length X 90.500

% volume of length / 100 =

90.500

% total for Scan 1 Scan 2 100.000

% Length X 27.800

% volume of length /100 =

27.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length /100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

62.075

% total for 45 deg Other deg 60 Scan 1 100.000

% Length X 92.800

% volume of length 1100 =

92.800

% total for Scan I Scan 2 100.000

% Length X 16.800

% volume of length / 100 =

16.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length /100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

59.900

% total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 62.325

% Total for complete exam Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:

Date: __________

,A,ý

//)3, /,,)

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 6 REPORT 2001 U330 Summary No. 102674

Site/Unit:

NSP

/

Summary No.: ;

Examination For:

MI 02674 ISI UT Vessel Examination Procedure:

Procedure Revision/FC:

8 Work Order No.:

Report No.:

2001U330 Page:

1 of 4

ISI-UT-3A

/

0105401 Applicable Code: 1986 ISO Drawing No.:

ISl Fig 5 Location:

Reactor Vessel

==

Description:==

N-2K Noz/Vsl Weld System ID: Reactor Vessel Component ID: N-2K NV Size/Length:

12.0" 1 50.26" Thickness/Diameter:

5.55" 112.0" Limitations: Nozzle Configuration Start Time:

12:31 Finish Time:

13:20 Examination Surface:

Inside Outside []

Surface Condition: Ground Flush Lo Location:

Top Dead Center Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 176 Surface Temp.:

85 0F Cal. Sheet No.:

2001 CA339, 2001 CA340, 2001 CA341 Angle Used 0

45 45T 60 1 60T Scanning dB 45.2 51.0 51.0 58.3 58.3 Indication(s):

Yes [

No []

Scan Coverage:

Upstream [

Downstream [

CWV CCW [

Comments:

See attached coverage plots.

Results:

NAD []

IND [

GEO [7 Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes__ _

Examiner Level II-PDI Signature Date Reviewer 5_

Sgnature Date Loredo, Quirino

/

11/1012001 Clay, Sean P.

/

Examiner Level I Signature Date Site Review Signature Date VanRuler, Christopher

/

11/10/2001 Deopere, Richard A.

0-.j

)

j

/,/

/o(

Other Level NIA Signature Date ANII Review Signature Date N/A

/

Clow, Ron

/4_/

r"

Supplemental Report W

I7T Summary No.: 102674 Examiner: Loredo, Quirino Examiner: VanRuler, Christopher D.

Other:

NIA Level: II-PDI Reviewer: Clay, Sean P.

Level:

I Site Review: Deopere, Richard A.

Level:

NIA ANII Review: Clow, Ron 2001 U330 2

of 4

Date: )--20'-C(

Date: I'/h Wo (

Date:

___27__

Comments:

None Sketch or Photo:

G:\\IDDEAL50\\MNGPRFO2001'.MNGP SUPPL UT\\2001U330_1.bmp Report No.:

Page:

LW Site/Unit:

NSP

/

MI Summary No.:

102674 Examination For:

ISI Limitation Record Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 8

/

0105401 Report No.:

2001U330 Page:

3 of 4

Description of Limitation:

Nozzle Configuration Sketch of Limitation:

G:\\IDDEAL50\\MNGPRFO2001 \\MNGP SUPPL UT\\2001U330_2.bmp Cý V

WX65PO7 t.s 2 0

N P

AEyA" V04.

Limitations removal requirements:

N/A Radiation field:

Examiner Level lI-PDI Signature Date Reviewer Signature Date LoredoQuirino

/,111102 Clay, Sean P.

/(

Examiner Level I Signalure Date Site Review

(

Signature Date VanRuler, Christopher

/

-1,L21.

11/1012001 Deopere, Richard A.

'((-)o(

Other Level N/A Signature Date ANII Review

,i, ure N/A I

Clow, Ron

/ t7I t~2 Vz SCFALE

SWDetermination of Percent Coverage for UT Examinations - Vessels Site/Unit:

NSP

/

MI Summary No.:

102674 Examination For:

ISl Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001U330 ISI-UT-3A Page:

4 of 4

8

/

0105401 0 deg Planar Scan 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for 0 deg 45 deg Scan 1 100.000

% Length X 90.500

% volume of length / 100 =

90.500

% total for Scan 1 Scan 2 100.000

% Length X 27.800

% volume of length 1100 =

27.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

62.075

% total for 45 deg Other deg 60 Scan 1 100.000

% Length X 92.800

% volume of length / 100 =

92.800

% total for Scan 1 Scan 2 100.000

% Length X 16.800

% volume of length / 100 =

16.800

% total for Scan 2 Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 3 Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for Scan 4 Add totals and divide by # scans =

59.900

% total for 60 deg Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 62.325

% Total for complete exam Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:D Date:

ý (/"-Z'ýet I

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 7 REPORT 2001 U328 Summary No. 102698

Site/Unit:

NSP

/

M1 Summary No.:

102698 Examination For:

ISI UT Vessel Examination Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 8

/

0105401 Report No.:

2001U328 Page:

1 of 4

Applicable Code: 1986 ISO Drawing No.:

ISl Fig 5 Location:

Reactor Vessel

==

Description:==

N-8B VsIl/Noz Weld System ID: Reactor Vessel Component ID: N-8B NV Size/Length:

6.0" 31.40" Thickness/Diameter:

5.55" 16.0" Limitations: Nozzle Configuration Start Time:

12:41 Finish Time:

14:00 Examination Surface:

Inside H]

Outside 1.7/

Surface Condition: Ground Flush Lo Location:

Top Dead Center Wo Location:

Centerline of Weld Couplant:

Sonotrace 40 Batch No.:

1. 00143 Temp. Tool Mfg.:

Telatemp Serial No.:

NSP 176 Surface Temp.:

85

°F Cal. Sheet No.:

2001 CA333, 2001 CA334, 2001 CA335 Angle Used 0

45 45T 60 60T Scanning dB 45.2 51.0 51.0 58.3 58.3 Indication(s):

Yes H No [

Scan Coverage:

Upstream [

Downstream W CW [S6 CCW W Comments:

See attached coverage plots.

Results:

NAD Fj IND H GEO Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes q)

Supplemental Report Report No.:

2001 U328 Page:

2 of 4

Summary No.: 102698 Examiner: Loredo, Quirino ZZ Examiner: Griebel, David M. 07V Other: N/A Level: iI-PDI Level: ll-PDI Level:

NIA Reviewer: Clay, Sean P.

Site Review: Deopere, Richard A.

ANII Review: Clow, Ron Date: /P 0I Date:

t IA C36 Date:

11136161 Comments:

None Sketch or Photo:

G:\\IDDEAL50\\MNGPRFO200I\\MNGP SUPPL UT\\2001U328_1.bmp

,.1*'

&W

-p Site/Unit:

NSP

/

Mt Summary No.:

102698 Examination For:

ISI Limitation Record Procedure:

Procedure Revision/FC:

Work Order No.:

ISI-UT-3A 0105401 Report No.:

2001U328 Page:

3 of 4

Description of Limitation:

Nozzle Configuration.

Sketch of Limitation:

G:\\IDDEAL50\\MNGPRFO2001\\MNGP SUPPL UT12001 U328_2.bmp

-/LOW*

Z6V-4Xe PL-O, V

-N P

D SS SCALE Limitations removal requirements:

N/A Radiation field: Z 5 00) i'n CNTAhT" Examiner Level 11-PDI Sign re Date Reviewer S

Date Loredo, Quirino I

Cý 11112/2001 Clay, Sean P.

I

/.9,0 1

Examiner Level 11-PDI Date Site Review Signature Date Griebel, David M.

/,

1111212001 Deopere, Richard A.

I

[ /2.0I Other Level N/A Signature Date ANII Review

,-$)

re Date NIA

/

Clow, Ron i

Determination of Percent Coverage for UT Examinations - Vessels Site/Unit:

NSP

/

M1 Summary No.:

102698 Examination For:

ISI Procedure:

Procedure Revision/FC:

Work Order No.:

Report No.:

2001U328 ISI-UT-3A Page:

4 of 4

8 I

0105401 0 deg Planar Scan 100.000

% Length X 65.000

% volume of length / 100 =

65.000

% total for 0 deg 45 deg Scan 1 100.000

% Length X 90.500

% volume of length / 100 =

Scan 2 100.000

% Length X 27.800

% volume of length / 100 =

Scan 3 100.000

% Length X 65.000

% volume of length /100 =

Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

Add totals and divide by # scans =

62.075

% total for 45 deg Other deg 60 Scan 1 100.000

% Length X 92.800

% volume of length / 100 =

Scan 2 100.000

% Length X 16.800

% volume of length / 100 =

Scan 3 100.000

% Length X 65.000

% volume of length / 100 =

Scan 4 100.000

% Length X 65.000

% volume of length / 100 =

Add totals and divide by # scans =

59.900

% total for 60 deg 90.500

% total for Scan 1 27.800

% total for Scan 2 65.000

% total for Scan 3 65.000

% total for Scan 4 92.800

% total for Scan 1 16.800

% total for Scan 2 65.000

% total for Scan 3 65.000

% total for Scan 4 Percent complete coverage Add totals for each angle and scan required and divide by # of angles to determine; 62.325

% Total for complete exam Note:

Supplemental coverage may be achieved by use of other angles / methods. When used, the coverage for volume not obtained with angles as noted above shall be calculated and added to the total to provide the percent total for the complete examination.

Site Field Supervisor:

Date:

1/(2 Lo C

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 8 REPORT 2001 VE301 Summary No. 102642

Site/Unit:

Summary No.:

Workscope:

Vendor Exam For Ultrasonic NSP

/

102642 ISI Ml Procedure:

PDI-ISI-254 Procedure ReviFC:

4

/

Work Order No.:

0003968 Outage No.:

MNGPRF22 Report No.:

2001VE301 Page:

1 of 1

Code:

1986 Code Cat.:

B-A Location:

Reactor Vessel Drawing No.:

IS] Fig 4

==

Description:==

Long Seam System ID:

Reactor Vessel Component ID: VLAA-1 Size/Length:

Thickness/Diameter:

Limitations:

Jet Pump diffusers restricts access to lower portion of Weld.

Comments:

See Wesdyne Report," Monticello Nuclear Generating Plant 10 Year Reactor Vessel Inservice Examination for NMC.

Report 2001 interval 3, period3, Outage RFO20". Coverage of VLAA-1= 80.1%

Limitation is documented in Wesdyne Report Results:

NAD V1 IND 7I GEO 0

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes Examiner Level III-PDI

\\.

Sig-gature Date Reviewer Clay, Sean t

)

11119/2001 Whitcomb,Daniel Examiner Level

"------&cature Date Site Review

/

Deopere, Richard A.

Other Level Signature Date ANII Review

/

Suleski, Kurt A.

WesDyne International Reactor Vessel Weld Results Summary MONTICELLO WELD NO.

VLAA-1 DESCRIPTION Long Seam

@ 750 LIMITATIONS NO l

YESj x See Coverage Estimate Sheet RESULTS NI X

RI NO. OF INDICATIONS STATUS N/A EXAM DOCUMENTATION ANALYSIS LOG ACQUISITION LOG SCAN PRINTOUT INDICATION DOCUMENTATION ASSESSMENT SKEET l] JPARAGON HARD COPY OTHER ( specify )

COVERAGE BREAKDOWN WESDYNE ANALYST 0

Exl xl xl

MONTICELLO DIRECTION / ORIENTATION RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS UP / DN PERP. SCANS CCW / CW ITEM / AREA Long Seam @ 750 WELD NO.

BEAM DIRECTION CCW CW UP DOWN 450 L Dual WELD VOLUME 76.1 76.1 76.1 76.1 86.8 82.9 86.8 82.9 81.5 79.5 L

BEAM ANGLES 450 L Single 450 Shear WELD VOLUME WELD VOLUME 76.1 73.5 76.1 73.2 76.1 73.5 76.1 73.2 86.8 82.9 86.8 82.9 86.8 82.9 86.8 82.9 81.5 78.2 81.5 78.1 WELD VOLUME WELD VOLUME COMPOSITE COVERAGE ANALYST VLAAI 11, -- zv- -

.e VLAA1 80.1%

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 10-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 9 REPORT 2001 VE302 Summary No. 102643

Vendor Exam For Ultrasonic N MI)

Site/Unit:

NSP

/

M1 Summary No.:

102643 Workscope:

IS[

Procedure:

Procedure Rev/FC:

Work Order No.:

PDI-1SI-254 4

/

0003968 Outage No.:

MNGPRF22 Report No.:

2001VE302 Page:

1 of I

Code:

1986 Code Cat.:

B-A Location:

Reactor Vessel Drawing No.:

ISl Fig 4

==

Description:==

Long Seam System ID:

Reactor Vessel Component ID: VLAA-2 Size/Length:

Thickness/Diameter:

Limitations:

Jet Pump diffusers restricts access to lower portion of Weld.

Comments:

See Wesdyne Report," Monticello Nuclear Generating Plant 10 Year Reactor Vessel inservice Examination.fNMC.

Report 2001 interval 3, period3, Outage RFO20." Coverage of VLAA-2= 75.8%

Limitation is documented in Wesdyne Report.

Results:

NAD F IND

-j GEO Z--_

Percent Of Coverage Obtained > 90%:

No Reviewed Previous Data:

Yes

I__-

WesDyne International Reactor Vessel Weld Results Summary "MO NTI C LL WELD NO.

LIMITATIONS RESULTS VLAA-2 NOZZ NI F-x DESCRIPTION YES XI]

Long Seam

@ 2550 See Coverage Estimate Sheet RI I-NO. OF I-NDICATIONS 0

STATUS N/A EXAM DOCUMENTATION W ]ANALYSIS LOG W ]ACQUISITION LOG W 1SCAN PRINTOUT INDICATION DOCUMENTATION ASSESSMENT SHEET PARAGON HARD COPY OTHER ( specify )

W ICOVERAGE BREAKDOWN WESDYNE ANALYST

MONTICELLO DIRECTION / ORIENTATION RPV COVERAGE ESTIMATE BREAKDOWNS PARALLEL SCANS PERP. SCANS UP/DN CCW / CW ITEM / AREA Long Seam @ 2550 WELD NO.

BEAM ANGLES BEAM 450 L Dual 450 L Single 450 Shear DIRECTION DIRECTION WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME WELD VOLUME CC\\W 76.5 76.5 76.5 74.7 76.5 74.4 CW 76.5 76.5 76.5 73.6 76.5 72.9 UP 83.7 68.0 83.7 68.0 83.7 68.0 DOWN 83.7 68.0 83.7 68.0 83.7 68.0 80.1 72.3 80.1 71.1 80.1 70.8 75.8%

ANALYST VLAA2 COMPOSITE COVERAGE

NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO, 3 RD 1 0-YEAR INTERVAL INSERVICE INSPECTION EXAMINATION PLAN ATTACHMENT 10 SUPPORTING DIAGRAMS / SKETCHES FOR ATTACHMENTS 8 AND 9

Westinghouse Proprietary Class 2C R 103,0 -to CMad 19 EXP.CTED S C÷(N L i m,T-Iow Pr o DcD 1 x,

(

CAe" N RPV 2DR~w'J* S?*.-L*c6Tmc~q&

VLAA1 255&

420,6 to 551,46 41374 to 55,32 VLAA2 750 420,6 -to 551F46-413,74 -to 55032 PERPENDICULAR SCAN LIMITS PARALLEL INDEX LIMITS BOTH SIDES OF LONG SEAM WELDS 1,798' per Degree Monticello RV, ISI 20MO WesDyne Interncttionol LONG SEAMS EXAMINATION PREOGRAM PLAN ALL DIMENSIONS IN INCHES SI OiL' UNLESS OT11MR WSE NOTED SET 0--

TOl 1TOP OlF VESSEL VIEW/:

FROIM VESSEL CLNIERI INE

~~C W~J v

REIIATIUN. PERPENDICULARSCN LJ



IEIDSDYNE. INTERNAIO~FINAL HDNTIOELI-FJ PEJI EXA~M SHEILL SLED UT R~N~c FýXTURE

77 I

F F

71



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XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX E JET PUMP TOP ASSEMBLY AND BRACES FIGURE 1 JET PUMP INSPECTION ANNUl 1800 -

NORTH-

-Page 23 of 70 I

XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-40 Revision 5 APPENDIX E JET PUMP TOP ASSEMBLY AND BRACES FIGURE 2 00 JET PUMP 4 RISER BRACE PAIR (Typical)

JET PUMP (Typical)

Page 24 of 70

XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX E JET PUMP TOP ASSEMBLY AND BRACES FIGURE 3 2

See FIGURE 5 3 For Details HOLDDOQ'NS 4

5 imLET TmROAT WEDGE AND RESTRAINER (FIGURE-6)

Page 25 of 70

XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE I

TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX E JET PUMP TOP ASSEMBLY AND BRACES FIGURE 6 DcaLta aof Veda* &resa fTYPlCA. OF Il Page 28 of 70

XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX E JET PUMP TOP ASSEMBLY AND BRACES FIGURE 7 169P0ULM Page 29 of 70 JET PUMP SENSING LINES AID SUPfORT ZlACC? SCRE'TIC

e XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX F SHROUD SHELF AND WELDS FIGURE 1 Reactor Vessel Section View CORE SUjPPRCT MN$TRUMENTATIOff OIFFUSER (ITEM No. 1)

SHROUD SUPPORT TO SHROUD WELD r

(ITEM No. 2) /

SHROUD SHELF 1 SHROUD SUPPO1'T \\tEMl Page 31 of 70

XCEL ENERGY METALS & MATERIALS RESOURCES NORTH INSERVICE INSPECTION - NONDESTRUCTIVE EXAMINATION PROCEDURE TITLE:

VISUAL EXAMINATION OF MONTICELLO REACTOR VESSEL INTERIOR NUMBER:

ISI-VT-4.0 Revision 5 APPENDIX F SHROUD SHELF AND WELDS FIGURE 2 It-Page 32 of 70