ML20214M546
| ML20214M546 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/13/1987 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20214M386 | List: |
| References | |
| NUDOCS 8706010341 | |
| Download: ML20214M546 (29) | |
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ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 1987 INSERVICE INSPECTION REPORT May 26, 1987 0706010341 070026
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, ADOCK 0D000155 PDR 28 Pages DC0587-0061-NLO4
7 0
FORM NtB 1 OWNER 5 REPORT FOR INSERY1G 94PECTIONS As repaired by the Provisloes of the ASME Code Raise
- 1. Owne, Consumers Power Company, 212 W. Michigan Ave. Jackson, MI h9201 (Name and Address of Owner)
- 2. Plant Big Rock Point Power Plant, US 31 North, Charlevoix, MI h9720 (Name and Address of Plant)
- 3. Plant Unit 1 4. Owner Certificate of Authorization (if required) N/A S. Commercial Service Date 12/b2 6. Nationsl Board Number for Unit ih431
- 7. Components inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
See Big Rock Point Power Plant 1987 Inservi ::e Inspection No. 2 h Outage Plan Reactor Vessel Combustion Engineering 16512 M-06h95h-M 1hh31 Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in.,
(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheetsis recorded at the top of this form.
I12/ sal This Form IE00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017
7 FORM NIS 1 (BedQ
- 8. Exatnination Dates 1-3 87 to 3 6 87 9. Inspection Interval from 1-1 02 to 12-31-91
- 10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.
Cee ISI Report Table 2
- 11. Abstract of Conditions Noted See ISI Report Table 1
- 12. Abstract of Corrective Measures Recommended and Taken See ISI Report Table 1 We certify that the statements made in this report are correct and the examinations and corrective mea.
sures taken conform to the rules of the ASME Code,Section XI.1977 Ed tion, Summer of 1973 Addenda OeriikicEte"oNA'utr a on . a pb able) a zhration Date N/A Date March 11 19 87 Signed Consumers Power Co By b
- b -
Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the Etional Board of Boiler and Pressure Vessel inspectors and the State or Province of Michigan ind employed b> Protection Mutual of Norvood. MASS have inspected the components described in tl$i)YnNs kekoriEENds the penod 1187 to 1 6 87 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures desenbed in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied.
concerning the examinations and corrective r'teasures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be lial,le in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions .B #7 r e fr7 Inspector's fanature National Board, State, Province, and Endorsements Date 3 MM 19 81 (12/sai
, 314 BOCK POINT F14NT Bavisima 1 '
. USERTIG DSFBCT15 0UTAGE FLAN Page 20 of 20 G ..,F USERVIG USPECTION UTERVAL 2 - ISI-4 Inspection Completion Soview and Approval Sheet BIG EDCE POINT EUCLEAR PLANT Signsture/Deto Technical Baview Big Rock Point ISI M / 9-io-sq BRF Engr & Maint Superintendent < 4 /10 / 67 Hydrostatic / Leak Test Review
\ ,, All Equipment Is in a Return-to-Service Status Operations Supervisor bi / 4-I3-94--
I M p proved by**
Plant Superintendent / / P7 pd l
.\
l l
- Sign-off of the hydrostatic / leak test portion of this form indicates that all hydrostatic / leak tests which the plant has identified as testable only during the outage have been performed.
- Approval of this plan indicates a return-to-service status.
s . MIo385-0078A-BI01-BT01
Cover Sheet - Section XI
- 1. Date March 30, 1987
- 2. Headquarters Consumers Power Company 212 W Michigan Avenue Jackson, MI 49720
- 3. Plant Big Rock Point Nuclear Plant 10269 US 31 North Charlevoix, MI 49720
- 4. Unit No. 1
- 5. Commercial Service Date December 8, 1962
- 6. Gross Generating Capacity 75 MW Electric 7-
- 10. See Attached NIS-1 forms and Examination Agencies Final Reports
- 11. Completion Date for Inspections March 6, 1987
- 12. Code Inspector (s) Randall L Riegler
- 13. Authorized Inspection Agency Protection Mutual Insurance Company Factory Mutual Engineering 30150 Telegraph Road, Suite 371 Birmingham, MI 48010
- 14. Abstract See Abstracts and Summaries in Examination Agencies Final Report
- 15. Signature of Inspector (s) A MIO387-1401A-BT01
Consumers Power Company Big Rock Point Plant ,
1 l
1987 INSERVICE INSPECTION NO. 2-4 MIO387-1401A-BT01
1987 INSERVICE INSPECTION NO. 2/4 BIG ROCK POINT PLANT Inservice Inspection No. 2/4 was conducted during the period of January 3, 1987 through March 6, 1987 in accordance with Section 9.0 of the Big Rock Plant Technical Specifications, except so specified by Consumers Power Company letter dated October 15, 1980, which updated the applicable ASME i Boiler and Pressure Vessel Code,Section XI to the 1977 Stamer 1978 Edition. '
Hangers, supports will be examined in accordance with 80W80 Addenda for IWD/IWF only.
Areas examined during this inspection included various components of the portions of the nuclear steam system and portions of various support systems piping as itemized in the attached Table 2 - Inservice Inspection No. 2/4 Examination Table.
The examinations were performed using Radiographic (RT) Ultrasonic (UT),
Liquid Penetrant (PT) and Visual (VT) techniques. The various examinations were conducted in s.ccordance with Consumers Power Company Laboratory and Field Technical Services Department (L&FTS) or vendor Combustion Engineering (CE) approved procedures. Examinations were performed by personnel qualified in the NDT process utilized in accordance with the requirements of Section XI IWA-2300, 1977 ASME Boiler and Pressure Vessel Code. Instances of reportable indications are itemized in the attached Table 1 - Resolution of Reportable Indications.
All records detailing procedures, personnel and equipment certifications, examination data, and disposition of reportable indications are on file at the Big Rock Point Plant and also in General Office,1945 West Parnall Road, Jackson, Michigan 49201.
i l
MIO387-1401A-BT01
- . . - . - - . _ . - . - _ - . - _ - - _ - _ _ . . - . - - - - . _ - - ._-_- - - ---- ~
TABLE I Resolution of Reportable Indications I
MIO387-1401A-BT01
Page 1 of 2 TABM #1 RESOLUTION TO REPORTABLE INDICATIONS
! Exam Eva Reporting
- No. Component Method Condition Reported Mechanism Disposition Re-Exas Disposition 1-3 Vessel Support PT Indications DN#DMZO20387-2 Analysis, None Acceptable T2-1 South Side DN#DMZO13087-1 Resolved in Place Steam Drum D-BRP-87-42 1-4 Vessel Support PT Indications D-BRP-87-41 Analysis, None Acceptable T2-4 South Side DN#DMZO20387-01 Resolved in Place Steam Drum DN#DMZ013087-2 1-8 1.5-MSS-113-4 PT Indications DN#DMZO13087-3 Removed Indications PT Acceptable Pipe-to-Tee D-BRP-87-43 by Crinding i
1-9 1.5-MSS-116-1 PT Indications DN#DMZ013087-5 Removed Indications PT Acceptable Tee-to-Pipe D-BRP-87-44 by Crinding 2-20 2-CRD-111-19 PT Rounded Indications DN#DMZO12187-2 Removed Indications PT Acceptable Pipe-to-Elbow D-BRP-87-26 by Grinding 2-21 2-CRD-111-23 FI Rounded Indications DN#DMZ012187-1 Removed Indications PT Acceptable Pipe-to-Elbow D-BRP-87-27 by Crinding 2-25 24-tetS-122-1 PT Indications DN#DMZ011987-2 Removed Indications PT Acceptable l Reducer-to-Tee D-BRP-87-18 by Crinding (ICSCC) 2-26 17-MRS-111-7 PT Indications DN#bMZO12487-1 Removed Indications PT Acceptable Elbow-to-Reducer D-BRP-87-25 by Crinding (ICSCC) DN#DMZO12187-3 2-28 17-letS-111-7-LD-1 PT Indications DN#DMZ012087-3 Removed Indications PT Acceptable Longitudinal D-BRP-87-22 by Crinding Downstream-North Side (ICSCC) 2-30 17-tetS-114-7-LD-1 PT Indications DN#DMZ012087-2 Removed Indications PT Acceptable Longitudinal D-BRP-87-21 by Grinding Downstream-North Side (ICSCC) 2-33 6-SCS-102-23 PT Rounded Indications DN#DMZO12087-1 Removed Indications PT Acceptable Elbow-to-Pipe D-BRP-87-23 by Crinding (ICSCC) 2-34 6-SCS-102-24 PT Rounded Indications DN#DMZO11987-1 Removed Indications PT Acceptable Pipe-to-Tee D-BRP-87-19 by Crinding (ICSCC) i MIO387-1402A-BT01 2
TABLE #1 RESO11fflON TO REP 0itIABLE INDICATIONS Exas Exas Reporting No. Component Method Condition Reported Mechanise Disposition Re-Exas _ Disposition 6-3 VFW-9 W-1 Corrosion DN#DMZ013087-4 Analysis, None Acceptable 10-FWS-101 D-BRP-87-45 Resolved in Place 12-4 T-40 PT Indications DN#DMZO11387-2 Removed Indications PT Acceptable Transfer Line D-BRP-87-11 by Grinding 13-3 6-SCS-201-13 PT Linear Indication DN#DMZO11687-1 Removed Indication PT Acceptable Pipe-to-Elbow D-BRP-87-16 by Crinding 13-6 6-SCS-203-8 PT Linear Indication DN#DMZO11787-2 Removed Indication PT Acceptable Elbow-to-Pipe D-BRP-87-08 by Grinding DN#DMZO11287-1 13-7 6-SCS-203-26 PT Indications M#DWO11687-2 Removed Indications PT Acceptable, Elbow-to-Pipe D-BRP-87-14 by Grinding 13-8 6-SCS-204-14 IT Round Indications DN#DMZO11687-3 Analysis, Mone Acceptable Valve SC-300-to DN#DMZO11287-2 Resolved in Place Valve SC-2 D-BRP-87-05 17-1 6-WS-204-3 PT Round Indications DN#DMZO11787-1 Analysis, None Acceptable Pipe-to-Valve DN#DMZ011487-1 Resolved in Place FW-6 D-BRP-87-13 18-2 6-RCW-302-8-PR VI-3 Loose Nut D-BRP-87-06 Tightened Nut VT-3 Acceptable Pipe Restraint 18-3 6-RCW-302-10-PR W-3 loose Nuts D-BRP-87-07 Tightened Nuts VI-3 Acceptable Pipe Restraint 21-1 6-CSS-201-24 PT Indications DN#DMZO12287-1 Removed Indications PT Acceptable Pipe-to-Elbow D-BRP-87-29 by Crinding 21-3 6-CSS-201-34 PT Indications DN#DMZO12287-2 Removed Indications PI Acceptable Pipe-to-Elbow D-BRP-87-28 by Grinding 21-4 6-CSS-201-36 PT Rounded Indications DN#DMZO12687-1 Indications Ground- PT Acceptable Penetration-to-Pipe DN#DMZO12387-1 pipe Repair Welded and Re-examined D-BRP-87-32 OfDIER EXAMS 12-RDS-101 Functional liigh Drag Force DN# DAD 020387-2 Replaced with Spare None Acceptable PS-103B Snubber E-BRP-87-05 Snubber 10-RDS-103D Functional liigli Drag Force DN# DAD 12787-1 Replaced with Spare None Acceptable PS-109-B Snubber E-BRP-87-05 Snubber MIO387-1402A-BT01
TABLE 2 Examination Summary MIO387-1403A-BT01
Page 1 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component
- Acty. Item No. Cat. No. Method (s) Identification Examination Results 1-1 B-D B3.130 UT Safety Relief Deferred (3 in) F-1 1-2 B-G-1 B6.90 UT A-1-BT Acceptable Manway Bolting Studs (in Place) 1-3 B-H B8.30 PT Vessel Support D-BRP-87-42 T2-1 South Side (See Table 1) 1-4 B-H B8.30 PT Vessel Support D-BRP-87-41 T2-4 South Side (See Table 1) 1-5 B-F B5.50 PT 3-MSS-107-6. Acceptable RT Nozzle-to-Flange Dissimular Metal Weld 1-6 B-K-2 Bil.10 VT-3 1.5 MSS-111-13-PR Acceptable VT-4 Pipe Restraint 1-7 B-J 89.21 PT 1.5-MSS-113-3 Acceptable Level Sensor-to-Pipe 1-8 B-J B9.21 PT 1.5-MSS-113-4 D-BRP-87-43 Pipe-to-Tee (See Table 1) 1-9 B-J B9.21 -PT 1.5-MSS-Il6-1 D-BRP-87-44 Tee-to-Pipe (See Table 1) 1-10 B-G-2 B7.70 VT-1 1.5-MSS-111 Acceptable i MSS-3-BT l
l 1
MIO387-1403A-BT01
Page 2 of 18
' TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 1-11 B-G-2 B7.70 VT-1 1.5-MSS-111 Acceptable MSS-4-BT l-12 Augmented ---
PT 3-MSS-107-1 Acceptable VT-1 RV-5002(F-1) 1-13 B-K-2 Bil.10 VT-3 12-RDS-101 Acceptable VT-4 PS-103A Snubber 1-14 B-K-2 B11.10 VT-3 12-RDS-101 Acceptable VT-4 PS-103B Snubber 2-1 B-J B9.21 PT 3-LPS-102-33 Acceptable Elbow-to-Pipe Dissimular Metal Weld 2-2 B-J B9.21 PT 3-RCS-122-5 Acceptable j
Elbow-to-Pipe 2-3 B-J B9.21 PT 3-RCS-122-8 Acceptable Pipe-to-Elbow 2-4 B-J B9.21 PT 3-RCS-122-1 Acceptable Tee-to-Pipe 2-5 B-J B9.40 PT 1.5-MSS-122-9 Acceptable Elbow-to-Pipe i 2-6 B-J B9.40 PT 1.5-MSS-122-10 Acceptable Pipe-to-Reducer i
i i'
M10387-1403A-BT01 1
Page 3 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-7 B-J B9.40 PT 1.5-MSS-124-13 Acceptable Pipe-to-Tee 2-8 B-J B9.40 PT 1.5-MSS-124-14 Acceptable Tee-to-Cap i
2-9 B-J B9.40 PT 1.5-MSS-124-15 Acceptable Tee-to-Pipe 2-10 B-J B9.40 PT 1.5-MSS-124-15A Acceptable Pipe-to-Reducer 2-11 B-K-2 B11.10 VT-3 20-MRS-121-13-PR Acceptable VT-4 Pipe Restraint 2-13 B-K-2 B11.10 VT-3 24-MRS-122-6-PR Acceptable VT-4 Pipe Restraint i 2-14 B-K-2 B11,10 VT-3 24-MRS-122-8-PR Acceptable VT-4 Pipe Restraint
- 2-15 B-K-2 B11.10 VT-3 20-MRS-122-11-PR Acceptable VT-4 Pipe Restraint 4
{ ,
2-16 B-K-2 B11.10 VT-3 4-CSS-101-5-PR-1 Acceptable j VT-4 Pipe Restraint i
2-17 B-K-2 B11.10 VT-3 4-CSS-101-5-PR-2 Acceptable VT-4 Pipe Restraint MIO387-1403A-IIT01
Page 4 of 18-TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-18 B-F B5.50 PT 3-CSS-101-16 Acceptable Reducer-to-Pipe Dissimular Metal Weld 2-19 B-J B9.40 PT 2-CRD-111-18 Acceptable Elbow-to-Pipe 2-20 B-J B9.40 PT 2-CRD-111-19 D-BRP-87-26 Pipe-to-Elbow (See Table 1)
( -
l 2-21 B-J B9.40 PT 2-CRD-111-23 D-BRP-87-27 l Pipe-to-Elbow (See Table 1) 2-22 B-K-2 B11.20 VT-3 Main Recirc Pump No. 2 Acceptable VT-4 2-12 Pump Support 2-23 B-K-2 Bil.20 VT-3 Main Recire Pump No. 2 Acceptable VT-4 2-13 Pump Support 2-24 B-J B9.I1 PT 24-MRS-121-1 Acceptable UT Reducer-to-Tee (ICSCC) 2-25 B-J B9.I1 PT 24-MRS-122-1 D-BRP-87-18 UT Reducer-to-Tee (See Table 1)
(ICSCC) 2-26 B-J 89.I1 PT 17-MRS-111-7 D-BRP-87-25 UT Elbow-to-Reducer (See Table 1)
(IGSCC) l MIO387-1403A-BT01
Page 5 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-27 B-J B9.11 PT 17-MRS-114-7 Acceptable UT Elbow-to-Reducer (IGSCC)
I 2-28 B -J B9.12 PT 17-MRS-111-7-LD-1 D-BRP-87-22 UT Longitudinal (See Table 1)
{ Downstream-North Side i
(ICSCC) 2-29 B-J B9.12 PT 17-MRS-111-7-LD-2 Acceptable
! UT Longitudinal Downstream-South Side (IGSCC) 2-30 B-J B9.12 PT 17-MRS-114-7-LD-1 D-BRP-87-21 UT Longitudinal (See Table 1)
Downstream-North Side (IGSCC) ,
2-31 B-J B9.12 PT 17-MRS-114-7-LD-2 Acceptable IIT Longitudinal Downstream-South Side (IGSCC) 2-32 B-F BS.50 PT 6-SCS-102-22 Acceptable UT Pipe-to-Elbow Dissimular Metal Weld l (IGSCC)
! 2-33 B-J B9.I1 PT 6-SCS-102-23 'D-BRP-87-23 UT Elbow-to-Pipe (See Table 1)
(IGSCC)
MIO387-1403A-BT01
Page 6 of 18 TABLE #2 i BIG ROCK NUCLEAR PLANT In. service Inspection No. 2/4 1
Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results i
2-34 B-J B9.I1 PT 6-SCS-102-24 D-BRP-87-19 UT Pipe-to-Tee (See Table 1)
(IGSCC) i 2-35 B-J B9.11 PT 6-SCS-102-25 Acceptable UT Tee-to-Pipe (ICSCC) 2-36 B-J B9.I1 PT 5-MRS-132-2 Acceptable UT Pipe-to-Elbow (IGSCC)
~
2-37 B-J B9.11 PT 5-MRS-132-3 Acceptable UT Elbow-to-Pipe i (ICSCC) 2-38 B-J B9.11 PT 5-MRS-132-4 Acceptable UT Pipe-to-Valve MO-N002B (IGSCC) 2-39 B-J B9.11 PT 5-MRS-132-7 Acceptable UT Elbow-to-Pipe i (ICSCC) 2-40 B-J B9.I1 PT 5-MRS-132-8 Acceptable l
l UT Pipe-to-Tee 2 (IGSCC) f M10387-1403A-BT01
Page 7 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Ites No. Cat. No. Method (s) Identification Examination Results 2-41 B-J B9.11 PT 5-MRS-132-11 Acceptable ITT Pipe-to-Branch Connection (IGSCC) 2-42 B-J B9.11 PT 4-MRS-141-2 Acceptable UT Pipe-to-Elbow (IGSCC) 2-43 B-J B9.I1 PT 4-MRS-141-3 Acceptable l UT Elbow-to-Pipe (ICSCC) 2-44 B-J B9.I1 PT 4-MRS-141-6 Acceptable UT Pipe-to-Elbow (IGSCC) 2-45 B-J B9.I1 PT 4-MRS-141-7 Acceptable UT Elbow-to-Pipe (IGSCC) 2-46 B-J B9.11 PT 4-MRS-141-8 Acceptable UT Pipe-to-Tee (IGSCC) 2-47 B-J B9.I1 PT 4-MRS-141-10 Acceptable UT Tee-to-Pipe (IGSCC) 2-48 B-J B9.11 PT 6-SCS-102-25A Acceptable UT Pipe-to-Branch Connection (IGSCC)
M10387-1403A-HTOl -
Page 8 of 18 TABLE #2 BIG ROCK NUCLEAR PIANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results i
i B-K-2 B11.10 VT-3 12-RDS-101-13-PR Acceptabla l 3-1 VT-4 Pipe Restraint l
B-C-2 B7.50 VT-1 6-RDS-103-3-BT Acceptable 3-2 Flange Bolting B-M-2 B12.40 VT-1 MO-7062 Deferred 3-3
" internal" 6-ECS-101 B11.10 VT-3 10-RDS-103D Acceptable 3-4 B-K-2 VT-4 PS-109-A Pipe Support Snubber VT-3 10-RDS-103D Acceptable 3-5 B-K-2 Bil.10 VT-4 PS-109-B Pipe Support Snubber B-K-2 B11.10 VT-3 2-RDS-107A Acceptable 3-6 VT-4 PS-115A Pipe Support Snubber VT-3 2-RDS-107A Acceptable 3-7 B-K-2 Bil.10 VT-4 PS-115B Pipe Support Snubber VT-3 3-RCS-101-19-Ph Deferred 4-1 B-K-2 Bil.10 VT-4 Pipe Restraint VT-3 3-RCS-101-34-PR Deferred 4-2 B-K-2 Bil.10 VT-4 Pipe Restraint MIO387-1403A-RT01
i Page 9 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4
. Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results
, 4-3 B-K-2 Bil.10 VT-3 3-RCS-102-17-PS Deferred VT-4 Pipe Support 4
4-4 B-J B9.21 PT 3-RCS-102-35 Deferred f
Elbow-to-Pipe 4-5 B-J B9.21 PT 3-RCS-102-38 Deferred Pipe-to-Nozzle 4-6 B-J B9.21 PT 3-RCS-102-43 Deferred i Pipe-to-Elbow 4-7 B-J B9.21 PT 3-RCS-102-44 Deferred Elbow-to-Pipe 4-8 B-K-1 B10.10 PT 2-CRD-101-44-PS Deferred Welded Pipe Support 4-9 B-K-2 Bil.10 VT-3 2-CRD-101-44-PSS Deferred VT-4 Pipe Support Structure 4-10 B-G-2 B7.70 VT-1 RCS-CK-2-BT Deferred (CU-302) 3-RCS-102 i
4-11 B-K-2 B11.10 VT-3 3-RCS-101-G-PR Deferred i
VT-4 P'ipe Restraint 4-12 B-K-1 B10.10 PT 3-RCS-102-44-PS Deferred Welded Pipe Support 5-1 B-K-2 Bil.10 VT-3 14-MRS-101-4-PR Acceptable l
VT-4 Pipe Restraint M10387-1403A-ItT01
J Page 10 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 i Exam- ASME Sec. XI ASME Sec. XI Exams Component l Acty. Item No. Cat. No. Method (s) Identification Examination Results
- 5-2 B-K-2 B11.10 VT-3 14-MRS-102-4-PR Acceptable VT-4 Pipe Restraint i
- 5-3 B-K-2 B11.10 VT-3 14-NRS-104-4-PR-2 Acceptable VT-4 Pipe Restraint 5-4 B-K-2 B11.10 VT-3 14-MRS-106-3-PR Acceptable
- VT-4 Pipe Restraint 5-5 B-K-2 B11.10 VT-3 14-MRS-106-4-PR Acceptable VT-4 Pipe Restraint l
6-1 B-K-2 B11.10 VT-3 1.5-MSS-117-14-PR Acceptable VT-4 Pipe Restraint ,
6-2 B-K-2 B11.10 VT-3 1.5-MSS-117-16-PR-1 Acceptable VT-4 Pipe Restraint i s
l 6-3 B-G-2 B7.70 VT-1 VW-9 D-BRP-87-45 10-WS-101 (See Table 1)
! 6-4 C-E C3.50 VT-3 10-FWS-201-46-PR Acceptable Pipe Restraint
]
! 6-5 C-E C3.40 PT 10-WS-201-46-PL-1 thru 4 No Exam Due to Welded Pipe Lugs Accessibility 6-6 B-K-2 B1I.10 VT-3 1.5-MSS-117-12-PR Acceptable VT-4 Pipe Restraint MIO387-1403A-BT01
Page 11 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component
!, Acty. Item No. Cat. No. Method (s) Identification- Examination Results 6-7 B-G-2 B7.70 VT-1 1.5-MSS-117 Acceptable MO-N004-BT Valve Bolting 6-8 B-J B9.20 PT 3/4-IWS-101-1 Acceptable Valve VFW-9-to-Coupling 6-9 p-J B9.11 PT 14-MRS-101-5 Acceptable UT Pipe-to-Safe End (IGSCC) 6-10 B-F B5.30 PT 14-MRS-101-6 Acceptable UT Safe End-to-Nozzle I (IGSCC) 6-11 B-J B9.11 PT 14-MRS-102-6 Acceptable l'
UT Pipe-to-Safe End (IGSCC) 6-12 B-F B5.30 PT 14-MRS-102-7 Acceptable j
UT Safe End-to-Nozzle
]
(IGSCC) t 6-13 B-J B9.I1 PT 14-MRS-103-5 Acceptable ITT Pipe-to-Safe End (IGSCC) 6-14 B-F B5.30 PT 14-MRS-103-6 Acceptable UT Safe End-to-Nozzle (IGSCC)
M10387-1403A-BT01
Page 12 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Actv. Ites No. Cat. No. Method (s) Identification Examination Results 6-15 B-J B9.11 PT 14-MRS-104-5 Acceptable UT Pipe-to-Safe End (IGSCC) 7-1 B-G-2 B7.60 VT-1 RCUP-BT Acceptable Pump Bolting 7-2 B-G-2 B7.70 VT-1 3-RCS-101 Acceptable VCU-62 Valve Bolting 8-1 B-J B9.40 PT 2-RCS-104-3 Deferred Valve-to-Pipe (CV-4047) 8-2 B-J B9.40 PT 2-RCS-104-6 Deferred Tee-to-Pipe 8-3 B-G-2 B7.70 VT-1 CV-4045-BT Deferred Top 2-RCS-107 8-4 B-G-2 B7.70 VT-1 CV-4045-BT Deferred Botton 2-RCS-107 9-1 B-J B9.21 PT 2-CRD-101-12 Acceptable Valve-to-Pipe VRD-302 9-2 C-F C5.21 PT 6-CRD-201-17 Acceptable UT Pipe-to-Pipe M10387-1403A-IIT01
.. 3 .,
Page 13 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 11-1 B-N-1 B13.10 VT-3 Vessel Interior Acceptable i 11-2 B-G-1 B7.50 VT-1 4-RDC-101-30-BT Deferred Flange Bolting
]
- 11-3 B-G-1 B6.20 UT Closure Head Deferred Studs (in place)
S/N 1 thru 28 11-4 B-G-1 B7.50 VT-1 4-RDC-101-14-BT Acceptable Flange Bolting 12-1 C-F C5.11 PT 6-CSS-201-11 Acceptable Bend-to-Pipe 12-2 C-E C3.50 VT-3 6-CSS-201-19-PR Acceptable Pipe Restraint 12-3 F-B F-3 VT-3 6-SWS-303-3-PR Acceptable Pipe Restraint i
12-4 C-F C5.10 VT-1 T-40 D-BRP-87-11 ,
(AUG) C5.11 PT Transfer Line (See Table 1)
! 12-5 F-B F-3 VT-3 6-SWS-303 Acceptable j 2 PSS I Pipe Support Structure
) 13-1 C-F C5.11 PT 8-SCS-201-2 Acceptable
' Pipe-to-Elbow l 13-2 C-F C5.1I PT 8-SCS-201-5 Acceptable Elbow-to-Tee i
l M10387-1403A-BT01
l .. ...
l Page 14 of 18 TABLE #2 BIG ROCK NUCLEAR PI. ANT Inservice Inspection No. 2/4 l Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Metbod(s) Identification Examination Results l
1 13-3 C-F C5.I1 PT 6-SCS-201-13 D-BRP-87-16 Pipe-to-Elbow (See Table 1)
C-F C5.I1 PT 6-SCS-203-3 Acceptable 13-4 Pipe-to-Elbow 13-5 C-F C5.ll PT 6-SCS-203-4 Acceptable Elbow-to-Pipe C-F C5.I1 PT 6-SCS-203-8 D-BRP-87-08 13-6 Elbow-to-Pipe (See Table 1)
C-F C5.I1 PT 8-SCS-203-26 D-BRP-87-14 13-7 Elbow-to-Pipe (See Table 1)
C-F C5.1I PT 6-SCS-204-14 D-BRP-87-05 13-8 Valve SC-300 to (See Table 1)
Valve SC-2 C-E C3.50 VT-3 6-SCS-204-17-PR Acceptable 13-9 Pipe Restraint C-F C5.I1 PT 6-SCS-204-20 Acceptable 13-10 Pipe-to-Elbow PT 6-SCS-204-22 Acceptable 13-11 C-F C5.I1 Pipe-to-Elbow F-B F-3 VT-3 2-RCW-305-1-PR Acceptable 13-12 Pipe Restraint C6.20 PT 6-SCS-204 Delete Exam 13-13 C-G VSC-300 No Valve BvJy Welds Valve Body Weld M10387-1403A-BT01
.o ..,
Page 15 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Ites No. Cat. No. Method (s) Identification Examination Results 14-1 F-B F-2 VT-3 8-SWS-301-11-PSS Acceptable Pipe Support Structure 14-2 F-B F-2 VT-3 8-SWS-301-12-PSS Acceptable Pipe Support Structure 14-3 F-B F-2 VT-3 8-SWS-301-13-PSS Acceptable Pipe Support Structure 14-4 F-B F-2 VT-3 8-SWS-301-14-PSS Acceptable Pipe Support Structure 14-5 F-B F-2 VT-3 8-SWS-302-1-PSS Acceptable Pipe Support Structure 14-6 F-B F-2 VT-3 8-SWS-302-2-PSS Acceptable Pipe Support Structure 14-7 F-B F-2 VT-3 8-SWS-302-3-PSS Acceptable Pipe Support Structure 14-8 F-A F-1 VT-3 8-RCW-302-3-PR Acceptable Pipe Restraint 14-9 F-A F-1 VT-3 8-RCW-312-4-PR Acceptable Pipe Restraint 15-1 F-A F-1 VT-3 5-RCW-311-3-PR Acceptable Pipe Restraint 15-2 F-A F-1 VT-3 8-RCW-312-1-PR Acceptable Pipe Restraint M10387-1403A-BT01
- O **,
Page 16 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 ASME Sec. XI Exams Component Exam- ASME Sec. XI Examination Results Cat. No. Method (s) Identification Acty. Ites No.
VT-3 6-RCW-303-8-PS Acceptable 15-3 F-A F-1 Welded Pipe Support VT-3 6-RCW-303-8-PSS Acceptable 15-4 F-A F-1 Pipe Support Structure PT 12-MSS-105-14/ Acceptable 16-1 B-J B9.32 1.5-MSS-106 Branch Connection PT 1.5-MSS-106 Acceptable 16-2 B-J B9.21 Branch Connection-to-Pipe PT 1.5-MSS-106-4 Acceptable 16-3 B-J B9.21 Pipe-to-Valve MO-7065 PT 6-PIS-201-7 Acceptable 16-4 C-F C5.11 l Bend-to-Pipe Branch Connection j
PT 6-WS-204-3 D-BRP-87-13 17-1 C-F C5.21 ITT Pipe-to-Valve W-6 (See Table 1)
PT 6-WS-205 Delete Exas 17-2 C-G C6.20 No Valve Body Welds VW-2 Valve Body Weld PT 10-WS-201 Delete Exas 17.3 C-G C6.20 No Valve Body Welds CV-4000 PT 6-PIS-201-18 Acceptable 18-1 C-F C5.11 Elbow-to-Reducer MIO387-1403A-HTO1
o..c, Page 17 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Ites No. Cat. No. Method (s) Identification Examination Results 18-2 F-A F-1 VT-3 6-RCW-302-8-PR D-BRP-47-06 Pipe Restraint (See Table 1) 18-3 F-A F-1 VT-3 6-RCW-302-10-PR D-BRP-87-07 Pipe Restraint (See Table 1) 18-4 F-A F-1 VT-3 6-RCW-303-2-PS Acceptable Welded Pipe Support 18-5 F-A F-1 VT-3 6-RCW-303-2-PSS Acceptable Pipe Support Structure 18-6 F-A F-1 VT-3 6-RCW-303-5-PS Acceptable Welded Pipe Support 18-7 F-A F-1 VT-3 6-RCW-303-5-PSS Acceptable Pipe Support Support a
20-1 C-E C3.50 VT-3 8-PIS-202-3-PR Acceptable Pipe Restraint 20-2 C-F C5.I1 PT 8-PIS-203-3 Acceptable Tee-to-Reducer 21-1 C-F C5.I1 PT 6-CSS-201-24 D-BRP-87-29 Pipe-to-Elbow (See Table 1) 21-2 C-F C5.11 PT 6-CSS-201-30 Acceptable Pipe-to-Elbow 21-3 C-F C5.I1 PT 6-CSS-201-34 D-BRP-87-28 Pipe-to-Elbow (See Table 1)
M10387-1403A-BT01
-o 5 c, Page 18 of 18 TABLE #2 BIG ROCK NUCLEAR PLANT Inservice Inspection.No. 2/4 Exam- ASME Sec. XI ASME Sec. XI Exams Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 21-4 C-F C5.11 PT 6-CSS-201-36 D-BRP-87-32 Penetration-to-Pipe (See Table 1) 21-5 C-E C3.50 VT-3 12-MSS-201-14-PR Acceptable Pipe Restraint OTHER EXAMS Augmented Functional 12-RDS-101 Acceptable PS-103A Snubber Augmented Functional 12-RDS-101 E-BRP-87-05 PS-103B (See Table 1)
Snubber Augmented Functional 10-RDS-103D Acceptable PS-109B Snubber Augmented Functional 10-RDS-103D E-BRP-87-05 PS-109-B (See Table 1)
Snubber Augmented Functional 2-RDS-107A Acceptable PS-115A Snubber Augmented Functional 2-RDS-107A Acceptable PS-115B Snubber MIO387-1403A-HT01