ML20151U648

1985 Inservice Insp Rept, of Insp 2-3 Conducted During 850909-1101,including Various Components of Portions of Nuclear Steam Sys & Portions of Various Support Sys Piping

ML20151U648
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/04/1986
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20151U622	List: ML20151U619 ML20151U648
References
NUDOCS 8602110074
Download: ML20151U648 (42)

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ATTACHMENT Consumers ~ Power. Company Big Rock Point Plant Docket 50-155 1985 INSERVICE INSPECTION REPORT February 4, 1986 i

4 G602110074 860204

'PDR ADOCK 05000155 G PDR ; ~41 Pager

. IC0186-0013-NLO4

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Consumers Power Company -

Big Rock Point Plant 1985 INSERVICE INSPECTION NO. 2-3 1

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MIO186-0015-NI.04 f

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1985 INSERVICE INSPECTION No. 2/3 BIG ROCK POINT PLANT Inservice Inspection No. 2/3 was conducted during the period of September 9, 1985 through November 1, 1985 in accordance with Section 9.0 of the Big Rock Plant-Technical Specifications, except as specified by Consumers Power Company letter dated October 15, 1980, which updated the applicable ASME Boiler and Pressure Vessel Code,Section XI to the 1977 Summer 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. 2/3 Examination Table.

The examinations were performed using Radiographic (RT) Ultrasonic (UT),

Liquid Penetrant (PT), Visual (VT) and Magnetic Particle (MT) techniques.

The various examinations weto conducted in accordance with Consumers Power Company System Protection and Laboratory Services (SP&LS) or Vendor Magnaflux Quality Services (MAG) 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.

l MI0186-0015-NLO4 k

, FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner Consurers Power Connany. 212 W Michiean Ave. 3mekmon. MT 4o201 (Name and Address of Owner)

2. Plant Bit Rock Point Power Plant,'% rie' mix VT Ao72^

(Name and Address of Plant)

3. Plant Unit l

4. Owner Certificate of Authorization (if required)  !^

5. Commercial Service Date 12/62 6. Natior.al Board Number for Unit 14431

7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

See Bie Rock Point Dower Plant 1085 Inservic e Insteection No. 2-3 Outare Plan Deactor Vesse:1 Combustion Enrineering 16512 M-064454-M 14431 i

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i Note: Supplemental sheets in form of lists, skstches, 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 sheets is recorded at the top of this form.

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t12/82) This Form (E00029) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y.10017

FORM NIS-l (llack)

8. Examination Dates 9/9/95 m 11/1/95 9. Inspection Interval from 3 /*lO/R4 to 3/30/03

10. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

See ISI Report Table 2

11. Abstract of Conditions Noted See ISI ReDort 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 for ASME Section XI.1977 E only )dition, Summer of 197 8 Addenda Code,IWD-IWF for components. (80w80 Addenda Certificate of Authorization No. (if applicable) gf3 Expiration Date N/A Datc he.mbw- N 1966 Signed Consumers Power ('o. By -

Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid corrmission issued by the National Board of Boiler and Pressure Veggpectors and the State or Province of v4^4--- and employed by Protection Mu og Ma w u--- have inspected the components described in this bl*N*NokEMie period afn/S5 to 11/1/05 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described 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 measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or c nect with this inspection.

Factory Mutual System Commissions W O' i'1' CI' l'h U h

• 5 9'7 Inspector's Sigfure National Board, State, Provmee, and Endorsements Date ,2 I 7AA/VA/f/ 19 OS (12/82)

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Cover ' Sheet - Section XI

1. Date November 26, 1985

2. Corporate Headquarters Consumers Power Company 212 W Michigan Avenue 3:Camuu, MI 49201

3. Plant Big Rock Point Nuclear Plant Route 3, Box 591 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 November 1, 1985

12. Code Inspector (s) Randall L Riegler Raymond E Alsbury

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

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15. Signature of Inspector (s) A' -

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TABLE 1 Rasolution of Reportable Indications 1

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w _ . .2 + _- p .g ... mg_. g s Pspe .1 of .2 TABLE fl-RESOLiffl0N TO REPORTARLE INDICATIONS Exam .

Reporting Eram No. Component Nethod(s) ' Condition Reported Mechanism Disposition Re-exam Disposition

. I-5 Steam Drum PT Round Indications DN#091885-I Analysis, None . Acceptable T2-2 (South Side) D-BRP-85-63 Resolved in Flare Support Lugs I-6 Steam Drum PT Round Indications DN#091885-2 Analysis, None Acceptable T2-3 (Sout h Side) D- BRP-85-62 Resolved in Place Support Lugs 1-25 Steam Drum Relief VT-1 Linear & Round DN#KJWO92485-1 Replaced Valve Guide None Acceptable Valve 3-MSS-107 PT Indications on Valve D-BRP-85-69 and Adjusting Ring RV-5001 Guide & Adjusting Ring PT Internals (Augmented) 2-48 '10-FWS-201-44 UT Linear Indication MQS Report 1003 Removed Indication by PT Acceptable Elbow to Pipe PT D-BRP-85-75 Grinding and/or Flapping

3-19 6-RDS-105-2 RT Internal Concavity D-BRP-85-72 Analysis of Radiographs None Acceptable

Elbow to Valve by an Independent

CV-4183 Level III 5-1 1.5-MSS-114-8 PT Linear Indication . DN#KJWO91985-01 Removed Indication by PT- Acceptable Pipe to Elbow D- BRP-85-64 Crinding and/or Flapping Added Weld Material to Maintain Minimum W911 and Reground Area for Re-Exam 7-l 3-RCS-101-50-PR VT-3 Loose Hanger and D- BRP-85-51 Tightened Hanser VT-3 Acreptable Pipe Restraint VT-4 Hanger Nut & Nut VT-4 7-6 3-RCS-101-73-PSS VT-3 Lack of Contact D-BRP-85-65 shimmed Support VT-3 Acceptable Pipe Support Structure VT-4 Between Pipe Support VT-3 Structure and Floor 15-5 RPVCH NT Linear Indications D-BRP-85-49 Analysis, None Acceptable l Nuts in Place R.I.A.F #1001 Resolved in Place

S/N I thru 42 11-6 R PVCH VT-l I/8" Dents in Three D-BPR-85-60 Analysis, None Acceptable Washers Washers DN#KJWO98385-1 Resolved in Place

, S/N 1 thru 42 II-9 10" Instrument Nozzle VT-1 Top Threads of Fifth D- BRP-85-61 Analysis, None Acceptable Flange Stud Peened over DN#KJWO92085-1 Resolved in Place i

807-IA-ST

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Pzge 2 af 2 TABLE fl RES01.trTION TO REPORTABLE INDICATIONS Exas Reporting Exas No. Component Nethod(s) Condition Reported Mechanism Disposition Re-exas Disposition 11-13 4-RDC-101-1-PR VT-3 Loose bolt D-BRP-85-55 Tightened Loose Bolt VT-3 Acceptable Pipe Restraint VT-4 VT-4 11-15 4-RDC-101-10-PR VT-3 Wear on Threads D-BRP-85-55 Analysis, None Acceptable Pipe Restraint VT-4 of Through Bolt Pesolved in Place 12-1 6-CSS-201-6-PR-B VT-3 Loose Nuts D-BRP-85-57 Tightened Loose VT-3 Acceptable Pipe Restraint Nuts 12-6 Condensate Tank VT-1 Three Linear D-BRP-85-73 Ground Indications PT Acceptable T40 Transfer Line PT Indications on Flange D-BRP-85-74 Re-Examined VT-1 Acceptable Pipe to Flange (2) Leak at Threaded DN#KJWO92185-1 Piping, Flange Gaskets, Connection DN#KJWO92385-1 Welds & Botting DN#KJW100785-1 DN#KJW101085-2 DN#KJW100885-2 14-4 8-RCW-3tl-2-PSS VT-3 Loose Nuts D-BRP-85-54 Tightened Loose 'VT-3 Acceptable Pipe Support Structure Nuts 17-1 10-FWS-201-Il UT Linear Indications D-BRP-85-50 Re-Examination by'RT RT Acceptable Valve-fv24 to Pipe DN#KJWD98385-2 19-7 Stub Tube to UT Indications D-BRP-85-90 Analysis, None Acceptable Vessel Wall HQS Report 1004 Resolved in Place CRD-7 (F-2) 21-4 10-FWS-201-II-PR VT-3 Cap Between Walt D-BRP-85-76 Analysis, None Acceptable Pipe Restraint and Support Plate 21-8 10-FWS-201-24 UT Rounded Indications D- BRP-85-78 Weld Removed and Pipe PT Acceptable-Pipe to Valve PT DN#KJW100285-1 was Rewelded and RT Acceptable FWS-25 RT DN#KJW100385-1 Re-Examined DN#KJW100485-1 DN#KJW101085-1 21-19 10-FWS-201-39-PSS VT-3 Loose Nuts D-BRP-85-52 Ana' lysis, Mone Acceptable Pipe Support Structure Resolved in Place 21-22 12-MSS-201-5-PL-I thru 8 PT Linear Indications D-BRP-85-77 Removed Indication by PT - Acceptable Pipe Lugs DN#KJW100285-02 Crinding and/or Flapping DN#KJW100985-1 21-25 10-SWS-301-3-PR VT-3 Missing Nut D-BRP-85-53 Installed New Mut VT-3 Acceptable Pipe Restraint Mil 285-0771A-hTOI-NLO4

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n TABLE'2 Examination Sumary i

MIO186-0015-NLO4

Page 1 of33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination'Results 1-1 B-F B5.30 PT Steam Drum Acceptable UT Nozrle to Safe End 14-MRS-105-6/ Nozzle C-5 Safe End to Nozzle (ICSCC) l-2 B-F B5.30 PT j Steam Drum Acceptable UT Nozzle to Safe End

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14-MRS-106-6/ Nozzle C-3 Safe End to Nozzle 1-3 B-G-1 B6.90 UT Steam Drum -Deferred A-1-Bt Manway Bolting Studs (16) 1-4 B-G-1 B6.110 VT-1 Steam Drum Acceptable

~A-1-BT (East)

Manway Bolting 1-5 B-H B8.30 PT Steam Drum D-BRP-85-63 T2-2 (South Side) (See Table 1)

Support Lugs 1-6 B-H B8.30 PT Steam Drum D-BRP-85-62 T2-3 (South Side) (See Tabic 1)

Support Lugs 1-7 B-J B9.11 PT 4-ECS-103-Il No Exam Due to UT Elbow to Valve Accessibility MO-7063 (Additional examinations to be added as necessary to meet interval requirements for B-J welds)

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Page 2 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 1-8 B-J B9.11 PT- 4-ECS-103-15 Acceptable UT Pipe to. Nozzle 1-9 B-J B9.ll PT 8-MSS-101-3 No Exam Due to UT Pipe to Elbow Accessibility (Additional examinations to be added as necessary to meet interval requirements for B-J welds) 1-10 B-J B9.ll PT 8-MSS-104-4 No Exam Due to UT Elbow to Pipe Accessibility (Additional examinations. to be added as necessary to meet interval requirements for B-J welds) 1-11 B-K-1 BIO.10 PT 8-MSS-104-7-PL ' Acceptable Welded Pipe Lug 1-12 B-K-2 Bil.10 VT-3 8-MSS-104-7-PLR Acceptable VT-4 Pipe Lug Restraint 1-13 B-F B5.50 PT 3-MSS-107-3 Acceptable RT Nozzle to Flange Dissimiliar Metal 1-14 B-F B5.50 PT 3-MSS-107-4 Acceptable RT Nozzle to Flange Dissimiliar Metal 1-15 B-C-2 B7.50 VT-1 3-MSS-107-5-BT Acceptable Flange Bolting mil 285-0762A-BT01-NLO4

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Page 3 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT.-

INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. X1 Exam Component .

Acty. Item No. Cat. No. Method (s) Identification Examination Results 1-16 B-G-2 B7.50 VT-1 3-MSS-107-6-BT Acceptable Flange Bolting 1-17 B-G-2 ~ B7.50 VT-1 3-MSS-107-Il-BT Acceptable Flange Bolting 1-18 B-G-2 B7.50 VT-1 3-MSS-107-12-BT Acceptable

, Flange Bolting 1-19 B-K-2' Bil.10 VT-3 1.5-MSS-110-13-PR Acceptable VT-4 Pipe Restraint 1-20 B-J B9.40 PT 1.5-MSS-110-21 Acceptable Pipe'to Coupling 1-21 B-J B9.40 PT 1.5-MSS-Il0-22 Acceptable Coupling to Nozzle 1-22 B-J - B9.21 PT 1.5-MSS-112-16 Acceptable Pipe to Elbow 1-23 B-J B9.21' PT 1.5-MSS-112-17 Acceptable Elbow to Nozzle 1-24 B-K-2 Bil.10 VT-3 12-RDS-101-IPR Acceptable VT-4 Pipe Restraint-1-25 B-G-2 B7.70 VT-1 Steam Drum RV D-BRP-85-69 Required PT 3-MSS-107 RV-5001 (See Table 1)

PT Internals (Augmented) 1-26 B-J B9.11 PT 14-MRS-102-6 Acceptable UT Pipe to Safe End

. (IGSCC) mil 285-0762A-BT01-NLO4

Page'4 of 33 TABLE 2 BIC ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No.  ; Method (s) Identification Examination Results 1-27 B-J B9.I1 PT 17-MRS-112-2 Acceptable UT Safe End to Pipe (IGSCC)-

1-28 B-J B9.ll PT- 14-MRS-106-5 Acceptable UT Pipe to Safe End (IGSCC) 1-29 B-J B9.ll PT 17-MRS-Il4-7 Acceptable UT Elbow to Reducer (IGSCC) 1-30 B-J B9.ll PT 4-ECS-103-14 Acceptable UT Elbow to Pipe 2-1 B-K-2 B11.10 VT-3 3-LPS-102-21-PR Acceptable Pipe Restraint 2-2 B-K-2 B11.10 VT-3 3'-LPS-102-23-PR Acceptable Pipe Restraint 2-3 B-K-2 B11.10 VT-3 3-LPS-102-25-PR Acceptable VT-4 Pipe Restraint 2-4 B-K-1 B10-10 PT 3-LPS-102-28-PL Acceptable-Welded Pipe Lug 2-5 B-K-2 811.10 VT-3 3-LPS-102-28-PLR Acceptable VT-4 Pipe Lug Restraint 2-6 B-J B9.21 PT 3-LPS-102-37 Acceptable Pipe to Elbow MI1285-0762A-BT01-NLO4'

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'Page 5 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-7 B-J B9.21 PT 3-LPS-102-38 Acceptable Elbow to Pipe 2-8 B-J B9.21 PT l'-LPS-102-39 Acceptable Pipe to Elbow 2-9 B-F B5.50 PT 3-LPS-103-8 Acceptable UT Tee to Pipe Dissimiliar Metal Weld 2-10 B-J B9.21 PT 3-LPS-103-9 Acceptable Pipe to Elbow 2-11 ,B-J B9.11 PT 8-SCS-102-2 Acceptable UT Pipe to Valve CV-7058 2-12 B-K-2 Bil.10 VT-3 8-SCS-102-4-PR Acceptable VT-4 Pipe Restraint 2-13 B-J B9.ll PT 8-SCS-102-6 Acceptable UT Elbow to Pipe 2-14 B-K-2 Bil.10 VT-3 8-SCS-102-8-PR Acceptable VT-4 Pipe Restraint 2-15 B-J B9.ll PT 8-SCS-102-9 Acceptable UT Pipe to Reducer 2-16 B-J B9.11 PT 6-SCS-102-24 Acceptable UT Pipe to Tee (ICSCC) mil 285-0762A-BT01-NLO4

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• Page 6 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI .ASME Sec'. XI Exam Component Acty. Item No. Cat. No '. Method (s) Identification ' Examination Resu.Its 2-17 B-J B9.I1 PT 6-SCS-102-25 Acceptable UT Tee to Pipe (ICSCC) 2-18 B-J B9.I1 PT 6-SCS-102-26 ' Acceptable UT Tee to Reducer (ICSCC) 2-19 B-K-2 B11.10 VT-3' RCS-102-50-PR Acceptable VT Pipe Restraint 2-20 B-K-2 B11.10 VT-3 3-RCS-102-51-PR Acceptable VT-4 Pipe Restraint 2-21 B-K-2 Bil.10 VT-3 3-RCS-102-52-PR Acceptable VT-4 Pipe Restraint 2-22 B-J B9.21 PT 3-RCS-121-2 Acceptable Elbow to Pipe 2-23 B-J B9.21- PT 3-RCS-121-9 Acceptable

., Pipe to Elbow 2-24 B-J B9.21 PT 3-RCS-121-13 Acceptable Pipe to Branch I Connection J

2-25 B-J B9.21 PT 3-RCS-122-12 Acceptable Pipe to Branch Connection i

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Page 7 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT IN3ERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-26 B-J B9.11 PT 17-MRS-lll-6 Acceptable PT Pipe to Elbow UT Deleted Component

. Material is Cast Stainless Steel 2-27 B-J B9.11 PT 17-MRS-Ill-7 Acceptable UT Elbow to Reducer (IGSCC) 2-28 B-K-2 Bil.10 .VT-3 17-MRS-Il3-6-PR Acceptable VT-4 Pipe Restraint 2-29 B-K-2 B11.10 VT-3 17-MRS-114-5-PR Acceptable VT-4 Pipe Restraint 2-30 B-J B9.11 PT 24-MRS-121-1 Acceptable UT Reducer to Tee (Circ. Weld)

(ICSCC) 2-31 B-K-2 B11.10 VT-3 24-MRS-122-3-PR Acceptable VT-4 Pipe Restraint 2-32 B-J B9.I1 PT 24-MRS-122-1 Acceptab1e UT Reducer to Tee (IGSCC) 2-33 B-K-2 Bil.10 VT-3 20-MRS-122-13-PR Acceptable VT-4 Pipe Restraint 2-34 B-J B9. ll' PT 4-MRS-141-11 No Exam Due to UT Reducing Tee Configuration (Replaced (ICSCC) With Other Welds For Generic Letter 84-11 Res'ponse)

MI1285-0762A-BT01-NLO4

Page 8 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3~

Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-35 B-K-2 B11.10 VT-3 4-CSS-101-13-PR Acceptable VT-4 -Pipe Restraint 2-36 B-J B9.31 PT 20-MRS-122-17/5-MRS-132 PT Acceptable UT Branch Connection UT Deferred (No Calibration Block) 2-37 B-K-2 B11.10 VT-3 20-MRS-122-18-PLR _ Acceptable VT-4 Pipe Lug Restraint 2-38 B-K-2 B11.10. VT-3 5-MRS-132-7-PR-1 Acceptable VT-4 Pipe Restraint 2-39 B-K-2 B11.10 VT-3 5-MRS-132-7-PR-2 Acceptable VT-4 Pipe Restraint 2-40 B-J B9.ll PT 5-MRS-132-9 PT Acceptable UT Tee to Reducer No UT Exam Due to (ICSCC) Configuration (Replaced with other Welds for Generic Letter 84-11 Response) 2-41 B-J B9.11 PT 5-MRS-132-10 PT Acceptable UT Tee to Pipe No UT Exam Due to (ICSCC) Configuration (Replaced with Other Welds for i Generic Letter 84-11 Response) 2-42 B-J B9.ll PT 4-MRS-141-7 Acceptable UT Elbow to Pipe (IGSCC) mil 285-0762A-BT01-NLO4

Page 9 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION-NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No, Metbod(s) Identification Examination Results 2-43 B-J ~B9.I1 ~

PT 4-MRS-141-9 No Exam Due to.

UT Tee to Valve MRS-1 Configuration (Replaced (IGSCC) With other Welds for Generic Letter 84-11 Response) 2-44 B-G-2 B7.50 VT-1 4-CSS-101-5A-BT Acceptable Flange Bolting 2-45 B-J B9.ll PT 4-CSS-101-13 No Exam Due to UT Elbow to Pipe Accessibility (Additional examinations to be added as necessary to meet interval requirements for B-J welds) 2-46 B-J B9.40 PT 2-CRD-Ill-21 Acceptable Pipe to Elbow 2-47 B-G-2 B7.70 VT-1 VRD-305-BT Acceptable 2-CRD-11 2-48 C-F C5.21 UT 10-FWS-201-44 D-BRP-85-75 PT Elbow to Pipe (See Table 1) 2-49 B-J B9.11 PT 5-MRS-131-7 Acceptable UT Pipe'to Elbow (ICSCC) 2-50 B-J B9.11 PT 5-NRS-132-3 Acceptable UT Elbow to Fipe (ICSCC) mil 285-0762A-BT01-NLO4

Page 10 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 2-51 B-J B9.ll PT 5-MRS-132-7 Acceptable UT Elbow to Pipe (ICSCC) 2-52 B-J B9.ll PT 4-MRS-141-6 Acceptable UT Pipe to Elbow (IGSCC) 2-53 B-J B9.ll PT 4-MRS-141-4 Acceptable UT Pipe to Elbow (IGSCC) 2-54 B-J. B9.ll PT 5-ARS-132-Il Acceptable dipe to Branch Connection 3-1 B-D B3.150 UT Emergency Condenser Acceptable Nozzle to Vessel 103-N 6" North Bundle 3-2 B-D B3.150 UT Emergency Condenser Acceptable Nozzle to Vessel

, 103-S 6" South Bundle 3-3 B-K-1 B10.10 PT 6-ECS-101-2-PL Acceptable' Welded Pipe Lug 3-4 B-K-2 B11.10 VT-3 6-ECS-101-2-PLR Acceptable VT-4 Pipe Lug Restraint 3-5 B-K-2 B11.10 VT-3 6-ECS-101-8-PR-1 Acceptable VT-4 Pipe Restraint mil 285-0762A-BT01-NLO4

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Page 11 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI. Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 3-6 B-J B9.ll PT 6-ECS-101-12 Acceptable UT Elbow to Pipe 3-7 B-J B9.32 MT 6-ECS-102-1/2-LPS-101 Acceptable Branch Connection 3-8 B-J B9.11 PT 6-ECS-102-2 Acceptable UT Pipe to Valve MO-7052 3-9 B-J B9.ll PT 6-ECS-102-14 Acceptable UT Pipe to Nozzle 3-10 B-K-2 Bil.10 VT-3 4-ECS-104-5-PSS Acceptable VT-4 Pipe Support Structure 3-11 B-K-2 B11.10 VT-3 4-ECS-104-8-PLR Acceptable VT-4 Pipe Support Structure 3-12 B-J B9.40 PT 2-LPS-101-12 Acceptable Pipe to Elbow-3-13 B-J B9.40 PT 2-LPS-101-13 Acceptable Elbow to Pipe 3-14 B-J B9.40 PT. 3-LPS-102-4 Acceptable Pipe to Valve CV-4020 3-15 B-J B9.21 PT 3-LPS-102-10 Acceptable Pipe to Elbow mil 285-0762A-BT01-NLO4

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Page 12~of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3

- Exam- ASME Sec. XI ASME Sec. XI Exam .

Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 3-16 li-J B9.21 PT 3-LPS-102-11 Acceptable Elbow to Pipe 3-17 B-G-2 B7.50 VT-1 6-RDS-104-3-BT' Acceptable Flange Bolting 3-18 B-J B9.I1 PT 6-RDS-105-1 Acceptable UT Reducer to Elbow RT 3-19 B-J B9.ll PT 6-RDS-105-2 D-BRF-85-72 UT Elbow to' Valve (See Table 1)

RT CV-4183 3-20 B-J B9.40 PT 2-RDS-107A-4 Acceptable Pipe to Elbow 3-21 B-J B9.40 PT 2-RDS-107A-7 Acceptable Elbow to Pipe 3-22 B-F B5.50 PT 2-RDS-107A-8 Acceptable Pipe to Valve CV-4184 1 (Dissimilar Matal Weld) 3-23 B-K-2 Bil.30 VT-3 2-RDS-107A-8-PR Acceptable VT-4 Valve Support

. '4 B-F B5.50 PT 1.5-RDS-Il2-5 Acceptable Pipe to Valve RDS-101A-3-25 B-F B5.50 PT 1.5-RDS-Il3-5 Acceptable Pipe to Valve RDS-101B i mil 285-0762A-BT01-NLO4 1

'Page 13 of 33' TABLE 2 BIG ROCK NUCLEAR. PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI .ASME Sec. XI. Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results.

3-26 B-F B5.50 PT 1.5-RDS-Il3-6 Acceptable Valve to Pipe 3-27 B-J B9.40 ' PT 1.5-RDS-Il4-7 Acceptable Pipe to Elbow 3-28 B-J B9.40 PT 1.5-RDS-Il4-8 Acceptable Eliow to Pipe 3-29 B-K-2 Bil.10 VT-3 12-RDS-101 Acceptable VT 9-P1-1 (PS-106B)

VT-4(F) Snubber Includes Functional 3-30 B-K-2 Bil.10 VT-3 12-RDS-101' Acceptable VT-4 9-PR-2 (PS-106A)

VT-4(F) Snubber Includes Functional 4-1 B-H B8.40 PT Clean-up Regen Acceptable Heat Ex Unit .' A '

AS-1 Outer Support 4-2 B-D B3.150 UT Clean-up Regen Acceptable Heat Ex Unit 'B' Nozzle Welds B-5 3" Channel Inlet 4-3 B-D B3.150 UT Clean-up Regen. Acceptable Heat Ex Unit 'B' Nozzle Welds B-6 3" Channel Outlet.

mil 285-0762A-BT01-NLO4

r ..

I Page 14 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results-4-4. B-D B3.150 UT Clean-up Regen Acceptable

~

Heat Ex Unit 'B' Nozzle Welds B-7 -

3" Shell Inlet 4-5 B-D B3.150 UT Clean-up Regen Acceptable Heat Ex Unit 'b" Nozzle Welds B-8 3" Shell Outlet 4-6 B-H B8.40 PT Clean-up Regen Acceptchle Heat Ex Unit 'D' DT-1 4-7 B-K-2 Bil.10 VT-3 3-RCS-101-15-PR Acceptable VT-4 Pipe Restraint 4-8 B-J B9.21 PT 3-RCS-101-16 Acceptable Pipe to Elbow 4-9 B-F B5.50 .PT 3-RCS-101-22 Acceptable UT Pipe to Pipe Dissimiliar Metal Weld 4-10 B-J B9.21 PT 3-RCS-101-23 Acceptable Pipe to Nozzle 4-11 E-3 .B9.21 PT 3-RCS-101-31 Acceptable Pipe to Nozzle 4-12 B-G-2 B7.50 VT-1 3-RCS-101-41-BT Acceptable Bolting. Flange ,

mil 285-0762A-BT01-NLO4

• 'n Page 15 of~33 TABLE'2 BIG ROCK NnCLEAR PLANT INSERVICE INS *ECTION No. 2/3 Exam- #SME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 4-13 B-K-2 Bil.10 VT-3 3-RCS-101-43-PSS- Acceptable VT-4 Pipe Support Structure 4-14' B-J B9.21 PT 3-RCS-102-13 Acceptable Elbow to Pipe 4-15 B-J B9.21 PT 3-RCS-102-31_ Acceptable Nozzle to Pipe 4-16 B-K-2 Bil.10 VT-3 3-RCS-102-44-PSS Acceptable VT-4 Pipe Support Structure 4-17 B-K-2 Bil.10 VT-3 3-RCS-102-46-PR Acceptable VT-4 Pipe Restraint 4-18 B-J B9.40 PT 2-CRD-101-44 Acceptable Elbow to Pipe 4-19 B-J B9.40 PT 2-CRD-101-45 Acceptable Pipe to Elbow 5-1 B-J B9.21 PT 1.5-MSS-Il4-8 D-BRP-85-64 Pipe to Elbow (See Table 1) 5-2 B-J B9.21 PT 1.5-NSS-114-9 Acceptable Elbow to Pipe 5-3 B-J E9.40 PT '2-MSS-122-Il Acceptable Reducer to Tee 5-4 B-J 89.40 PT 2-MSS-122-12 Acceptable Pipe to Tee mil 285-0762A-BT01-NLO4

(

e *

• e_

Page 16 of 33-TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec..XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 5-5 B-J B9.40 PT 2-MSS-122-13 Acceptable Tee'to Pipe 5-6 B-J B9.40 PT 2-MSS-122-14 Acceptable Pfpe to Tee 5-7 B-J B9.40 PT 1.5-MSS-124-17A No Exam Coupler to Pipe High Radiation Area (Additional examinations to be added as necessary to meet interval requirements for B-J welds) 5-8 B-J B9.40 PT 1.5-MSS-124-18 No Exam Pipe to Tee High Radiation Area (Additional examinations to be added as necessary to meet interval requirements for.

B-J welds) 5-9 B-J B9.40 PT 2-MSS-131-15 No Exam Pipe.to Tee High Radiation Area (Additional examinations to be added as necessary to meet interval requirements for B-J welds) 5-10 B-J B9.40 PT 2-MSS-131-16 Ph> Exam Pipe to Tee High Radiation Area (Additional examinations to be added as necessary to meet' interval requirements for B-J welds) mil 285-0762A-BT01-NLO4

r- -

Page 17 of 33 1 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec.'XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 5-11 B-K-2 B11.10 VT-3 14-MRS-103-3-PR-2 Acceptable VT-4 Pipe Restraint-5-12 B-K-2 Bil.10 VT-3 14-MRS-104-2-PR Acceptable VT-4 Pipe Restraint 5-13 B-K-2 Bil.10 VT-3 14-MRS-104-3-PR Acceptable VT-4 Pipe Restraint.

5-14 B-K-2 Bll.10 VT-3 14-MRS-105-3-PR-1 Acceptable VT-4 Pipe Restraint 5-15 B-K-2 Bil.10 VT-3 14-MRS-105 PR-2 Acceptable VT-4 Pipe Restraint 5-16 B-K-2 BI1.10 VT-3 20-MRS-122-19-PR-1 Acceptable VT-4 Pipe Restraint 5-17 B-K-2 Bil.10 VT-3 20-MRS-122-19-PR-2 Acceptable VT-4 Pipe Restraint 6-1 B-J B9.40 'PT 1.5-MSS-Il7 Acceptable Tee to Pipe 6-2 B-J B9.40 PT 1.5-MSS-Il7-35 Acceptable Pipe to Elbow 6-3 B-J B9.40 PT 1.5-MSS-117-36 Acceptable Elbow to Pipe 6-5 B-K-2 Bil.10 VT-3 14-MRS-103-4-PR-1 Acceptable VT-4 Pipe Restraint MII285-0762A-BTOl-NLO4

Page 18 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam- Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 6-6 B-K-2 B11.10 VT-3 14-MRS-103-4-PR-2 Acceptable VT-4 Pipe Restraint 6-7 B-K-2 B11.10 VT-3. 14-MRS-104-4-PR-1 Acceptable VT-4 Pipe Restraint 6-8 B-K-2 BI1.10 VT-3 14-MRS-105-4-PR-1 Acceptable VT-4 Pipe Restraint 6-9 B'K-2 Bil.10 VT-3 14-MRS-105-4-PR-2 Acceptable VT-4 Pipe Restraint 6-10 B-J B9.ll PT 14-MRS-105-5 Acceptable UT Pipe to Safe End (IGSCC) 6-12 B-K-2 B11.10 VT-3 10-FWS-101-5-PR Acceptable VT-4 Pipe Restraint 7-1 B-K-2 Bil.10 VT-3 3-RCS-101-50-PR D-BRP-85-51 VT-4 Pipe Restraint (See Table 1) 7-2 B-J B9.21 PT 2-RCS-101-60 Acceptable Reducer to Pipe 7-3 B-J 'o9.21 PT 2-RCS-101-63 Acceptable Pipe to Pipe 7-4 B-J B9.21 PT 3-RCS-101-72 Acceptable Strainer to Pipe 7-5 B-K-1 B10-10 PT 3-RCS-101-73-PS Acceptable Welded Pipe Support MI1285-0762A-BTOl-h104

. . s Page 19 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT

' INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI _

Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 7-6 B-K-2 Bil.10 VT-3 3-RCS-101-73-PSS D-BRP-85-65 VT-4 Pipe Support Structure (See Table 1) 7-7 B-J B9.21 PT 3-RCS-101-75 Acceptable Pipe to Valve CV-4042 7-8 B-J B9.21 PT 3-RCS-101-76 Acceptable Valve to Pipe 7-9 B-J B9.40 PT 2-RCS-106-7 Acceptable Elbow to Pipe 7-10 B-J B9.40 PT 2-RCS-106-10 Acceptable Pipe to Valve CV-4044 7-11 B-J B9.21 PT 2-RCS-106-14 Acceptable Elbow to Pipe 7-12 B-J B9.40 PT 1.5-RCS-IIO-4 Acceptable Tee to Reducer 7-13 B-J B9.40 PT 2-RCS-Il0-5 Acceptable Reducer to Nozzle 7-14 B-K-2 Bil.20 VT-3 RCUP Acceptable VT-4 103 Pump Support 7-15 B-K-2 Bil.20 VT-3 RCUP Acceptable VT-4 111 Pump Support

. Mll 285-0762A-BT01-NI O4

Page 20.of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI 'ASME Sec. XI Exam Component Acty. Ites No. Cat. No. Method (s) Identification Examination Results 7-16 B-G-2 B7.70 VT-1 CV-4042 Acceptable 3-RCS-101 8-1 B-D B3.150 UT Clean-up Demin Tank Defe red 212 Influent (Added Exam 8-12)

Nozzle to Shell Weld 8-2 B-D B3.150 UT Clean-up Demin Tank Acceptable 213 3" Effluent Nozzle to Head Weld 8-3 B-J B9.21 PT 3-RCS-102-10 Acceptable Pipe to Elbow 8-4 B-J B9.21 PT 3-RCS-102-ll Acceptable Elbow to Pipe 8-5 B-J B9.40 PT 2-RCS-105-1 Acceptable Tee to Pipe 8-6 B-K-2 Bil.10 VT-3 2-RCS-105-1-PR Acceptable VT-4 Pipe Restraint 8-7 B-J B9.40 PT 2-RCS-105-4 Acceptable Pipe to Valve CV-4114 8-8 B-G-2 B7.70 VT-1 CV-4047-BT-Top Acceptable 2-RCS-104 8-9 B-G-2 B7.70 VT-1 CV-4047-BT-Bottom Acceptable 2-RCS-104 M11285-0762A-BT01-NLO4

Page 21 of 33.

TABLE 2-BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identificat ,

Examination Results 8-10 B-G-2 B7.70 VT-1 CV-4114-BT-Top Acceptable 2-RCS-105 8-11 B-G-2 B7.70 VT-1 CV-4114-BT-Bottom Acceptable 2-RCS-105 8-12 B-D B3.150 UT Clean-up Demin Tank Acceptable 214 Inlet Nozzle to Shell Weld 9-1 B-J B9.40 PT 2-CRD-101-7 Acceptable Pipe to Elbow 9-2 B-J B9.40 PT 2-CRD-101-13 Acceptable Pipe to Elbow 9-3 B-K-2 Bil.10 VT-3 2-CRD-101-16PR Acceptable VT-4 Pipe Restraint 9-4 B-K-2 Bl1.10 VT-3 2-CRD-101-28-PR Acceptable VT-4 Pipe Restraint 9-5 B-K-2 Bil.10 VT-3 2-CRD-101-30-PR-1 Acceptable VT-4 Pipe Restraint 9-6 B-K-2 B11.10 VT-3 .2-CRD-101-30-PR-2 Acceptable VT-4 Pipe Restraint 9-7 B-G-2 B7.70 VT-1 VRD-19-BT Acceptable 2-CRD-101 9-8 B-G-2 B7.70 VT-1 VRD-20-BT Acceptable 2-CRD-102 MII285-0762A-BT01-NLO4

I

. 1

• e Page 22 of 33 TABLE 2.

BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 9-9 C-F C5.21 UT 6-CRD-201-7 Acceptable PT Tee to Pipe 9-10 C-A C1.10 UT Scram Dump Tank Defer Exam

-Head to Shell Weld no Cal Block 102 (East End) 9-11 C-C C3.10 PT Vessel Supports Acceptable C3.20 VT-3 Support 2 (North) 10-1 B-J B9.40 PT 2-CRD-Ill-ll Acceptable Pipe to Elbow 10-2 B-K-2 B11.10 VT-3 2-CRD-Ill-12-PR-2 Acceptable VT-4 Pipe Restraint 10-3 B-J B9.40 PT 2-CRD-Ill-16 Acceptable Elbow to Pipe 11-1 B-A Bl.40 UT RPVCH Acceptable Head to Flange Weld 806-2 11-2 B-D B3.90 UT RPVCH Acceptable Nozzle to Head (10")

807-2A 11-3 B-D B3.90 UT RPVCH Acceptable Nozzle to Head (10"0) 807-2B 11-4 B-D B3.90 UT RPVCH Acceptable Nozzle to Head (10")

807-3 MI1285-0762A-BTOl-NLO4

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Page 23 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- . ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 5 B-G-1 B6.10 MT RPVCH D-BRP-85-49 Nuts-In Place (See Table 1)

S/N 1 thru 42 11-6 B-G-1 B6.50 VT-1 .RPVCH D-BRP-85-60 Washers (See Table 1)

S/N I thru 42 11-7 B-G-2 B7.10 VT-1 10" Instrument Nozzle Acceptable Flange 807-5A-ST Studs 11-8 B-G-2 B7.10 ~ VT-1 10" Instrument Nozzle Acceptable Flange 807-5A-NT Nuts 11-9 B-G-2 B7.10 VT-1 10" Instrument Nozzle D-BRP-85-61 Flange (See Table 1) 807-1A-ST Studs 11-10 B-G-2 B7.10 VT-1 RPVCH Acceptable 10" Instrument Nozzle Flange 807-1B-ST Studs 11-11 B-G-2 B7.50 VT-1 1. 5-MSS-11 ~ BT Acceptable Flange B ..ing 11-12 B-J B9.40 PT 1.5-MSS-Il7-5 Acceptable Pipe to Elbow mil 285-0762A-BT01-NLO4

o Page 24 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Resulta 11-13 B-K-2 .Bil.10 VT-3 4-RDC-101-1-PR D-BRP-85-55 VT-4 Pipe Restraint (See Table 1)

Il-14 B-J B9.I1 PT 4-RDC-101-7 Acceptable UT Pipe to Elbow I

11-15 B-K-2 B11.10 VT-3 4-RDC-101-10-PR D-BRP-85-55 i VT-4 Pipe Restraint (See Table 1)'

.i 11-16 B-J B9.11 PT 4-RDC-101-13 Acceptable UT Elbow to Pipe f 11-17 B-J B9.ll PT 4-RDC-101-22 Acceptable i UT Elbow to Pipe 12-1 C-E C3.50 VT-3 6-CSS-201-6-PR-B D-BRP-85 Pipe Restraint (See Table 1) a 12-2 C-F C5.ll PT 6-CSS-201-7 Acceptable Pipe to Elbow 12-3 C-F C5.I1 PT 6-CSS-201-16' Acceptable Elbow to Pipe 12-4 C-C C6.20 PT 6" Chapman Gate Valves Delete Exam VFP-29 No Valve Body Welds-6-CSS-201 12-5 F-B F-3 VT 10-SWS-302-2-PSS Acceptable

Pipe Support mil 285-0762A-BT01-NLO4

e r o Page 25'of 33 TABLE 2

. BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ACME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 12-6 C-F C5.10 VT-1 Condensate Tank 'D-BRP-85-73 (AUG) C5.ll PT T40 Transfer Line. 'D-BRP-85-74 Pipe to Flange (2) (See Table 1)

Piping, Flange Caskets.

Welds, and Bolting 13-1 C-F C5.ll PT 8-SCS-201-1 Acceptable Valve MO-7057 to Pipe 13-2 C-F C5.ll PT 8-SCS-201-4 Acceptable Pipe to Elbow 13-3 C-F' C5.ll PT 6-SCS-201-8 Acceptable Reducer to Pipe 13-4 C-F C5.ll PT 6-SCS-201-12 Acceptable Elbow to Pipe 13-5 C-E C3.50 VT-3 6-SCS-201-12-PR Acceptable Pipe Restraint 13-6 C-F C5.ll PT 6-SCS-201-15 Acceptable Pipe to Elbow 13-7 C-E C3.50 VT-3 6-SCS-201-15-PR Acceptable Pipe Restraint 13-8 C-F C5.ll PT 6-SCS-202-2 Acceptable Pipe to Elbow 13-9 C-E C3.50 VT-3 6-SCS-202-4-PR Acceptable Pipe Restraint MI1285-0762A-BT01-NLO4

.s ,-

9 Page 26 of 33-TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 13-10 C-F C5.I1 PT 6-SCS-202-6 Acceptable Valve SC-3 to IIx 13-11 C-F C5.Il PT 6-SCS-203-2 Acceptable Elbow to Pipe 13-12 C-F C5.ll PT 6-SCS-203-5 Acceptable Pipe to Elbow 13-13 C-F C5.ll PT 6-SCS-203-7 . Acceptable Pipe to Elbow 13-14 C-F C5.ll PT 6-SCS-204-7 Acceptable Pipe to Elbow.

13-15 C-C C6.20 PT 6" Walworth Cate Valves Delete Exam VSC-2 No Valve Body Welds 6-SCS-204 13-16 C-G C6.20 PT 6" Walworth Cate Valves Delete Exam VSC-1 No Valve Body Welds 6-SCS-201 14-1 F-A F-1 VT-3 10-SWS-301-1-PR Acceptable Pipe Restraint 14-2 F-A F-1 VT-3 10-SWS-301-2-PR Acceptable Pipe Restraint 14-3 F-A F-1 VT 8-RCW-302-2-PR Acceptable Pipe Restraint 14-4 F-A F-1 VT-3 8-RCW-311-2-PSS D-BRP-85-54

' Pipe Support Structure (See Table 1) mil 285-0762A-BTO:-NLO4

o.

Page 27 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 14-5 F-A F-1 VT-3 8-RCW-312-3-PSS Acceptable Pipe Support Structure 14-6 F-A F-1 VT-3 8-RCW-312-5-PR Acceptable Pipe Restraint 16-1 B-J B9.11 PT 12-MSS-105 Acceptable.

UT Pipe to Elbow 16-2 B-K-2 Bil.10 VT-3 12-MSS-105-14-PR-1 Acceptable VT-4 Pipe Restraint 16-3 B-K-2 Bil.10 VT-3 12-MSS-105-14-PR-2 Acceptable Whip Restraint 16-4 B-J B9.ll PT 12-MSS-105-15 Acceptable UT Pipe to Valve MO-7050 17-1 C-F C5.21 UT 10-FWS-201-ll D-BRP-85-50 PT Valve-FW24 to Pipe (See Table 1)

RT 17-2 C-F C5.21 UT 6-FWS-205-1 Acceptable PT Valve FW-301 to Elbow '

RT i

17-3 C-F C5.31 PT 6-FWS-205-2/2.5-FWS-208 Acceptable Branch Connection t 18-1 C-E C3.50 VT-3 6-PIS-201-12-PR- Acceptable Pipe Restraint MI1285-0762A-BT01-NLO4

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Page 28 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO.'2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 18-2 F-B F-2 .VT-3 8-SWS-301-6-PSS Acceptable Pipe Support Structure 18-3 F-B F-2 VT-3 8-SWS-301-7-PSS' Acceptable Pipe Support Structure 18-4 F-A F-3 VT-3 8-SWS-302-8-PSS Acceptable Pipe Support Structure 18-5 F-A F-3 VT-3 8-SWS-302-9-PSS Acceptable Pipe Support Structure 18-6 F-A F-1 VT-3 6-RCW-302-3-PS- . Acceptable Welded Pipe Support 18-7 F-A F-1 VT-3 6-RCW-302-3-PSS Acceptable Pipe Support Structure 18-8 F-A F-1 VT-3 6-RCW-302-5-PS Acceptable:

Welded Pipe Support 18-9 F-A F-1 VT-3 6-RCW-302-5-PSS Acceptable Pipe Support Structure 18-10 F-A F-1 VT-3 6-RCW-302-7-PS Delete Welded Pipe Support Does.not Exist 18-11 F-A F-1 VT-3 6-RCW-302-7-PSS Delete Pipe Support Structure Does not Exist 18-12 F-A F-1 VT-3 6-RCW-303-4-PS Acceptable Welded Pipe Support MI1285-0762A-BT01-NLO4

4

. . + , - o; -,

Page 29 of 33 TABLE 2.

BIC ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3

} Exam- ASME Sec. XI ASME Sec. XI Exam Component j Acty. Item No. Cat. No. Me thod (s) - Identification Examination Results l IE-13 F-A , F-1 VT-3 6-RCW-303-4-PSS- Acceptable

~

Pipe Support Structure 18-14 F-A F-1 VT-3 6-RCW-303-9-PS .

Acceptable Welded Pipe Support l  ;

i 18-15 F-A F-1 VT-3 6-RCW-303-9-PSS Acceptable

Pipe Support Structure 18-16 B-A Bl.21 UT Circ Weld Acceptable 806-3

, (CW) 0*-160*

19-1 B-E B4.13 VT-2 RPV Acceptable CRD 'J' Welds CRD-5 (E-6) 19-2 B-E B4.13 VT-2 RPV Acceptable CRD 'J' Welds CRD-31 (D-4)

I9-3 B-E B4.13 VT-2 RPV Acceptable

CRD 'J' Welds CRD-14 (F-4) 19-4 AUG UT RPV Acceptable CRD 'J' Welds

CRD-7 (F-2) i

19-5 B-0 B14.10 PT CRD Housing Welds Deferred Housing to Flange Weld Unable to perform (798-1) wet surface, CRD-3 (A-5) i MII285-0762A-BT01-NLO4

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Page 30 of 33 TABLE 2 BIC ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Method (s) Identification Examination Results 19-6 AUG UT Housing Acceptable CRD-7 (F2) 19-7 AUG UT Stub Tube to D-BRP-85-90 Vessel Wall (See Table 1)

CRD-7 (F2) 19-8 AUG UT Reactor Vessel Acceptable Wall CRD-7 (F-2) 20-1 C-E C3.50 VT-3 6-CSS-201-39-PR Acceptable Pipe Restraint 20-2 C-F C5.I1 PT 6-PIS-201-4 Acceptable

-Pipe to Tee 20-3 C-F C5.Il PT 8-PIS-202-1 Acceptable Valve 9 to Elbow 20-4 C-F C5.ll PT 8-PIS-202-4 Acceptable Pipe to Elbow 21-1 C-E C3.50 VT-3 6-CSS-201-27-PR Acceptable Pipe Restraint 21-2 C-F C5.Il PT 6-CSS-201-31 Acceptable Elbow to Pipe 21-3 C-E C3.40 PT 10-FWS-201-ll-PL-1 thru 4 Acceptable Welded Pipe Lugs 21-4 C-E C3.50 VT-3 10-WS-201-11-PR D-BRP-85-76 Pipe Restraint (See Table 1) mil 285-0762A-BT01-NLO4

c, .9 Page 31 of 33 TABLE 2 BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION NO. 2/3 Exam- ASME Sec. XI ASME Sec. X1 Exam Component Acty. Item No. Cat. No. ( Method (s) Identification Examination Results 21-5 C-E C3.50 VT-3 10-FWS-201-23-PR-A Acceptable Pipe Restraint 21-6 C-E C3.50 VT-3 10-FWS-201-23-PR-B Acceptable s Pipe Restraint 21-7 C-E C3.50 '

VT-3 10-FWS-201-27-PR Acceptable Pipe Restraint 21-8 C-F C5.21 '

UT 10-FWS-201-24' D-BRP-85-78 PT Pipe to Valve- (See Table 1)

RT FWS-25 n-9 C-F C5.21 UT 10-FWS-201-28 Acceptable PT Pipe to Tee 21-10 C-F. C5.21 UT 10-FWS-201-30 Acceptable PT Pipe to Elbow 21-11 C-F C5.21 UT 10-FWS- 201-31 Acceptable PT Elbow to Pipe 21-12 C-F C5.21 UT 10-WS-201-32 Acceptable Pipe to FE-IDOS 21-13 C-E C3.50 VT-3 10-WS-201-33-PR Acceptable Pipe Restraint 21-14 C-F C5.21 UT 10-FWS-201-35 Acceptable PT Bend to Pipe 21-15 C-F C5.21 UT FWS-201-36 Acceptable PT- Pipe to Bend MII285-0762A-BTOl-NLO4 ,

[

oe C, Page 32 of 33 TABLE 2 BIC ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam Component Acty. Item No. Cat. No. Metbod(s) Identification Examination Results 21-16 ,C-F C5.21 UT 10-FWS-201-38 No Exas Due PT Tee to Flange .

to Accessibility (Additional examinations to be added as necessary to meet.

interval requirements for B-J welds) 21-17 C-F C5.21 UT 10-FWS-201-39 Acceptable PT Tee to Pipe 21-18 C-E '

C3.40 PT 10-FWS-201-39-PL Acceptable I thru 4 Welded Pipe Lugs 21-19 C-E C3.50 VT-3 10-FWS-201-39-PSS D-BRP-85-52 Pipe Support Structure (See Table 1) 21 C-F C5.21 UT 10-FWS-201-40 Delete Exam PT Pipe to Containment Fillet Weld Pentration Not Within Scope of ISI 21-21 C-E C3.50 VT-3 12-MSS-201-5-PS Acceptable Pipe Support 21-22 C-E C3.40 PT 12-MSS-201-5-PL-1 thru 8 D-ERP-85-77 Pipe Lugs (See Table 1) 21-23 C-F C5.21 UT 12-MSS-201-7 Acceptable PT Pipe to Tee 21-24 C-F C5.21 UT 12-MSS-201-17 Acceptable PT Pipe to Elbow MI1285-0762A-BT01-NLO4

c.=g-Page 33 of 33

. TA3LE 2 ,

BIG ROCK NUCLEAR PLANT INSERVICE INSPECTION No. 2/3 Exam- ASME Sec. XI ASME Sec. XI Exam. Component Acty. Item No. Cat. No. Method (s)- Identification Examination Results

., 21-25 F-A F-1 VT-3 10-SWS-301-3-PR. D-BRP-85-53 Pipe Restraint (See Table 1)

0 21-26 F-A. F-1 VT-3 10-SWS-301-4-PR Acceptable Pipe Restraint 21-27 F-A F-1 VT-3 8-SWS-301-5-PR Acceptable Pipe Restraint l 21-28 F-A F-1 VT-3 8-SWS-302-10-PR Acceptable Pipe Restraint t

f MI1285-0762A-BT01-NLO4

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