Text

Inservice Inspection Summary Report for Cooper Nuclear Station
	ML020930016
Person / Time
Site:	Cooper
Issue date:	03/28/2002
From:	Denise Wilson; Nebraska Public Power District (NPPD)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NLS2002040
	Download: ML020930016 (112)
	v • d • e

H Nebraska Public Power District Nebraska's Energy Leader NLS2002040 March 28, 2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Inservice Inspection Summary Report Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46

References:

(1)

ASME Section XI, 1989 Edition, No Addenda (2)

ASME Section XI, 1992 Edition, 1992 Addenda, Subsection IWE The purpose of this submittal is to provide to the Nuclear Regulatory Commission the Inservice Inspection Summary Report for the Fall 2001 Refueling Outage at Cooper Nuclear Station. This report, submitted in accordance with the provisions of I OCFR50.55a and References 1 and 2, includes the Owner's Report for Inservice Inspections and the Owner's Report for Repairs and Replacements. Also included are the results of augmented examinations of the Reactor Pressure Vessel internal Core Spray piping performed in accordance with the Boiling Water Reactor Vessel Internals Project guidelines, BWR VIP-18 and the additional information required by I OCFR50.55a(b)(2)(ix)(D) for each flaw or area of degradation identified during the containment inspection which exceeded acceptance standards.

If you require any additional information regarding this report, please contact me at 402-825 2760 or David F. Kunsemiller, Risk and Regulatory Affairs Manager, at 402-825-5236.

Sincerely, David L. Wilson Vice President - Nuclear

/dnm Attachment Cooper Nuclear Station R,

P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 http://www.nppd.com

NLS2002040 Page 2 of 2 cc:

Regional Administrator USNRC-Region IV Senior Project Manager USNRC - NRR Project Directorate IV-1 Senior Resident Inspector USNRC NPG Distribution w/o attachments Records

ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2002040 The following table identifies those actions committed to by the District in this document.

Any other actions discussed in the submittal represent intended or planned actions by the District. They are described for information only and are not regulatory commitments.

Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None N/A

___________________________________________________________________________________________________ I.

1" PROCEDURE 0.42 REVISION 10 PAGE 12 OF 14 i

COOPER NUCLEAR STATION ASME SECTION XI

SUMMARY

REPORT FALL 2001 REFUELING OUTAGE - RE20

ASME Section XI Summary Report Cooper Nuclear Station RE 20, Fall 2001 Table of Contents

1.

NIS-1 Form and Summary Tables Abstract of Examinations, Results, and Corrective Measures ISI Exam inations...................................

Table 1.1 IWE Examinations during Mid-Cycle Outage............

Table 1.2 RPV In-Vessel Visual Inspections (IVVI)................

Table 1.3 (Including RPV Internal CS Piping/AHC UT Examinations)

Pressure Testing...................................

Table 1.4 Snubber Visual Examinations and Test Results...........

Table 1.5

2.

NIS-2 Form and Summary Table Commonly Used Abbreviations CB - Counter Bore FD - Fabrication Discontinuity IDG - Inside Surface Geometry INOP - Inoperable NGI - No Geometric Indication NRI - No Recordable Indication NRI - None Relevant Indication ODG - Outside Surface Geometry OP - Operable RG - Root Geometry RI - Recordable Indication RI - Relevant Indication SAT - Satisfactory SI - Spot Indication used in Table 1.1 used in Table 1.1 used in Table 1.1 used in Table 1.5 used in Table 1.1 used in Table 1.1 and Table 1.3 (UT exams) used in Table 1.3 (IVVI VT exams) used in Table 1.1 used in Table 1.5 used in Table 1.1 used in Table 1.1 and 1.3 (UT exams) used in Table 1.3 (IVVI VT exams) used in Table 1.5 used in Table 1.5

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

1.

Owner: Nebraska Public Power District,

2.

Plant: Cooper Nuclear Station, P0 Box 98, Brownville, NE 68321

3.

Plant Unit:

One

4. Owner Certificate of Authorization (if required): N/A

5.

Commercial Service Date: July, 1974

6. National Board Number for Unit:

20762

7.

Components Inspected: See Attached Report Summary

8.

Examination Dates: 05/30/2000 (End of Last Outage RE19 ) to 03/11/2002 (62 days following end of outage RE20)

9.

Inspection Period Identification: (ISI) Second Period - 7/01/99 to 10/31/02, (IWE) First Period 9/09/96 to 9/08/2001

10.

Inspection Interval Identification: Third Interval - 3/1/96 to 2/28/06

11.

Applicable Edition of Section XI: (ISI) 1989 Edition, No Addenda. (IWE) 1992 Edition, 1992 Addenda

12.

Date/Revision of Inspection Plan: (ISI) Revision 2, March 11, 2002, (IWE) Revision 0.1, March 8, 2000

13.

Abstract of Examinations and Tests: See Attached Report Summary.

14.

Abstract of Results of Examinations and Tests:

See Attached Report Summary

15.

Abstract of Corrective Measures:

See Attached Report Summary CERTIFICATE OF COMPLIANCE We certify that a) the statements made in this report are correct, b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of 4 uthorization No.

N/A Si oned_

ýL

(

Expiration Date Date N/A 3/2 z7

/

a

\\,_1 I

I 2D 0 0,2.

98 PAGES CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Nebraska and Employed by Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford Connecticut have inspected the components described in this Owner's Report during the period May 30, 2000 to March 11, 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owners's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

S/9/0 Commission Signate N

f B

, S, C

Inspector's Signature National Board, State, Province, and Endorsements Sine a da Date

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 1 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 B1.21 NB B1.22 B1.22 B1.22 B1.22 B1.22 B1.22 B1.22 B1.22 B1.22 NB NB NB NB NB NB NB NB NB B1.22 NB Component ID HMC-BB-1 HMA-BB-1 HMA-BB-2 HMA-BB-3 HMA-BB-4 HMA-BB-5 HMA-BB-6 HMA-BB-7 HMA-BB-8 HMB-BB-1 HMB-BB-2 Configuration BHD-C 0 ° - 360° BHD-M @ 390 BHD-M @ 840 BHD-M @ 1290 BHD-M @ 1740 BHD-M @ 2190 BHD-M @ 2640 BHD-M @ 3090 BHD-M @3540 BHD-M @ 50 BHD-M @ 65o Item No. System Results Commments/Corrective Measures NRI Axial Scans 44% Coverage From Bottom Side And NRI 56% From Top Side. 100% Of Circumferential B-A Category Components Examined Equal: 15 Work Order Performed By Report No.

Exam Procedure 4160194 Westinghouse R-114 Zone 1 60°RL PDI-UT-6 / E Zone 2 60°RL PDI-UT-6 / E Zone 2 600RL PDI-UT-6 / E 4160194 Westinghouse R-100 Zone 1 60°RL PDI-UT-6/I E Zone 2 60°RL PDI-UT-6 / E 4160194 Westinghouse R-101 Zone 1 60RL PDI-UT-6 / E Zone 2 60°RL PDI-UT-6 / E 4160194 Westinghouse R-102 Zone 1 60°RL PDI-UT-6S/

E Zone 2 60°RL PDI-UT-6S/

E 4160194 Westinghouse R-103 Zone 1 60*RL PDI-UT-6 / E Zone 2 60°RL PDI-UT-6 E

4160194 Westinghouse R-104 Zone 1 60°RL PDI-UT-6 E

Zone 2 60°RL PDI-UT-6 E

4160194 Westinghouse R-105 Zone 1 60°RL PDI-UT-6 / E Zone 2 60°RL PDI-UT-6 I E 4160194 Westinghouse R-106 Zone 1 60°RL PDI-UT-6 / E Zone 2 60°RL PDI-UT-6 / E 4160194 Westinghouse R-107 Zone 1 60°RL P0I-UT-6 E

Zone 2 60°RL PDI-UT-6 E

4160194 Westinghouse R-108 Zone 1 60°RL PDI-UT-6 E

Zone 2 60°RL PDI-UT-6SI E 4160194 Westinghouse R-109 Zone 1 60°RL PDI-UT-6 E

Zone 2 60°RL PDI-UT-6 E

NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Scans Achieved. Notification 10128962 was written to document reduced coverage.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-26.

100% ASME Code Coverage Achieved.

Reference Relief Request: RI-06. Estimated Coverage: 100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

Reference Relief Request: RI-06.

Estimated Coverage : 100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 2 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System B1.22 NB B1.22 NB B1.22 NB B122 NB Component ID HMB-BB-3 HMB-BB-4 HMB-BB-5 HMB-BB-6 Configuration BHD-M @ 1250 BHD-M @ 185° BHD-M @ 245° BHD-M @ 305-Work Order Performed By Report No.

Exam 4160194 Westinghouse R-110 Zone 1 60°RL Zone 2 60°RL 4160194 westinghouse R-111 Zone 1 60°RL Zone 2 60°RL 4160194 Westinghouse R-112 Zone 1 60°RL Zone 2 60°RL 4160194 Westinghouse R-113 Zone 1 60°RL Zone 2 60°RL Procedure PDI-UT-6 / E PDI-UT-6 I E Results NRI NRI Commments/Corrective Measures Reference Relief Request: RI-06. Estimated Coverage: 100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

PDI-UT-6 / E NRI Reference Relief Request: RI-06.

Estimated PDI-UT-6 I E NRI Coverage:

100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

PDI-UT-6 / E NRI Reference Relief Request: RI-06. Estimated PDI-UT-6 / E NRI Coverage: 100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

PDI-UT-6 / E NRI Reference Relief Request: RI-06.

Estimated PDI-UT-6 / E NRI Coverage: 100% Perpendicular Scans, 18% Of Parallel Scan Looking Up and 47% Of Parallel Scan Looking Down.

NIS-1, Table 1.1, RE20: ISI Examinations Page 3 of 30 Owner: NPPD P.O. Box 499 Columbus, NE 68602 Commerical Service Date: July, 1974 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Owner Certificate of Authorization: N/A Plant Unit: 1 National Board Number for Unit: 20762 Item No. System Component ID Configuration Work Order Performed By Report No.

Exam Procedure ResultsCommm,.ents/Corrective Measures B-G-1 Category Components Examined Equal: 7 B6.10 NB PRB-BGI-19 Thru 36 RPV NUT's 4160193 Westinghouse R-121 VT-1 CSP-ISI-8 / 0 RI Examined RPV Nuts PRB-BG1-19 thru PRB-BG1

36. Reference Relief Request: RI-16. Notification 10123836 was written to document the condition and evaluate for re-use. Indications appear to be caused by tooling used to remove and install the nuts. Indications are SAT.

86.180 RR RRP-1A-BG1 I thru 16 PUMP STUDS 4160205 Westinghouse R-160 UT-01 CSP-PDI-UT-5 / 0 NRI Examined RR-A Pump Studs RRP-1A-BG-1 thru RRP-1A-BG-16.

86.20 NB PRA-BGI-1 Thru 52 RPV STUD's 4160191 Westinghouse R-120 UT-00 CSP-PDI-UT-5 / 0 NRI Examined RPV Studs PRA-BG1-1 thru PRA-BG1

52.

B6&200 RR RRPN-1A-BG1 1 thru 16 NUT 4160205 Westinghouse R-162 VT-1 CSP-ISI-8 / 0 NRI Examined RR-A Pump Nuts RRPN-lA-BG1-1 thru RRPN-1A-BG1-16.

B6.200 RR RRPW-1A-BGI 1 thru 16 WASHER 4160205 Westinghouse R-163 VT-1 CSP-lSI-8 / 0 NRI Examined RR-A Pump Washers RRPW-1A-BG1-i thru RRPW-1A-BG1-16.

86.30 NB PRA-BG1-38 Thru 41 RPV STUD'S 4160192 Westinghouse R-170 MT CSP-ISI-70 / 2 NRI Examined RPV Studs PRA-BG1-38 thur PRA-BG1 UT- 0° CSP-PDI-UT-5 / 0 NRI

41. These studs were temporarily removed during vessel dissassembly.

B6.50 NB PRC-BGI-19 Thru 36 WASHER's 4160193 Westinghouse R-122 VT-i CSP-ISI-8 / 0 NRI Examined RPV Washers PRC-BG1-19 thru PRC BG1-36.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component ID Configuration Work Order B-G-2 Category Components Examined Equal: 14 B7.70 CS CS-CV-19CV Valve -Bolting 4160210 B7.70 HPCI HPCI-CV-29CV Valve - Bolting 4160197 B7.80 CRD CRD-BG2-02-27 CRD-Bolting 4159884 B7.80 B7.80 B7.80 B7.80 CRD CRD CRD CRD B780 CRD B7.80 CRD CRD-BG2-06-23 CRD-BG2-14-47 CRD-BG2-18-31 CRD-BG2-22-03 CRD-BG2-26-07 CRD-BG2-26-27 CRD-Bolting CRD-Bolting CRD-Bolting CRD-Bolting CRD-Bolting CRD-Bolting 4189197 4189306 4189309 4189312 Commerical Service Date: J Owner Certificate of Authoriz National Board Number for U Performed By Report No.

Exam Westinghouse R-086 Vr-1 Westinghouse R-092 VT-1 NPPD 4159884 VT-1 NPPD NPPD NPPD NPPD 4189317 NPPD 4189302 NPPD 4189197 4189306 4189309 4189312 4189317 VT-i VT-i VT-i vr-1 VT-i 4189302 VT-i Page 4 of 30 uly, 1974 zation: N/A Unit: 20762 Procedure Results CommmentsCorrective Measures CSP-ISI-8 / 0 NRI Examined Bolts and Nuts in place and under tension.

CSP-ISI-8 / 0 NRI Examined Bolts and Nuts in place and under tension.

3.28.1.1 Rev.2 RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10132330.

3.28-1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

3.28.1.1 Rev.2 RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10132330.

3.28.1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

3.28.1.1 Rev.2 RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10135680.

3.28.1.1 Rev.2 RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10132330.

3.28.1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 5 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System B7.80 CRD Component ID CRD-BG2-26-51 Configuration CRD-Bolting Work Order Performed By Report No.

4189342 NPPD 4189342 Exam VT-i Procedure 3.28.1.1 Rev.2 Results Commments/Corrective Measures RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10132330.

4189345 NPPD 4189345 VT-1 3.28.1.1 Rev.2 RI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order. Surface corrosion was detected, however, within Code allowable limits. Exam SAT.

Condition was documented on Notifcation 10132330.

4189347 NPPD 4189349 NPPD 4189356 NPPD 4189347 VT-i 4189349 VT-i 4189356 VT-i 3.28.1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

3.28.1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

3.28.1.1 Rev.2 NRI Bolting Examined when CRD was Disassembled.

Inspection results documented in referenced CNS Work Order.

B780 CRD CRD-BG2-30-39 CRD-Bolting B7.80 CRD B7.80 CRD B7.80 CRD CRD-BG2-34-51 CRD-BG2-38-19 CRD-BG2-50-23 CRD-Bolting CRD-Bolting CRD-Bolting

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 6 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System ComponentID.

Configuration B-J Category Components Examined Equal: 8 B9.11 CS CSB-BJ-18 Valve - Pipe B9.11 CS CSB-BJ-26 Pipe - Flued Head B9.11 RF FWD'BJ-18*

Tee - Reducer B9.11 RF FWD.BJ-23*

Elbow - Pipe B9.11 MS MSB-BJ-42 Flued Head - Pipe B9.21 MSDR MSDR-BJ-4 Flued Head - Pipe B9.40 CS CSB-BJ-32 Valve - Pipe B9.40 CS CSB-BJ-35 Valve - Pipe Work Order Performed By Report No.

4160210 4160212 4160211 4160211 4160198 4160198 4160210 4160210 Westinghouse Westing house Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-087 R-088 R-135 R-136 R-093 R-099 R-089 R-090 Exam MT UT-45oS UT-60oS MT UT-45°S UT-60°S MT UT-45°S MT UT-45°S MT UT-45°S MT MT MT Procedure Results CSP-ISI-70 1 2 NRI PDI-UT-1 / C CB PDI-UT-1 / C CB CSP-ISI-70 i12 NRI PDI-UT-1 / C RG PDI-UT-1 / C RG CSP-ISI-70 1 2 NRI PDI-UT-1 / C NRI CSP-ISI-70 / 2 NRI PDI-UT-1 / C NRI CSP-ISI-70 / 2 NRI PDI-UT-1 / C NRI CSP-ISI-70 / 2 NRI CSP-ISI-70 /f2 NRI CSP-ISI-70 / 2 NRI Commments/Corrective Measures Examination was performed from the downstream pipe side only due to valve to pipe configuration, however 100% ASME code coverage was achieved.

Examination was performed from the downstream pipe side only due to valve to pipe configuration, however 100% ASME code coverage was achieved.

100% ASME code coverage was achieved.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 7 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration B-K Category Components Examined Equal: 2 B10.10 NB HNC-BH-C

.Vessel

-Skirt 0' -3600 Work Order Performed By Report No.

Exam 4160194 Westinghouse R-115 MT UT-0° UT-45°S UT-60°S Procedure Results Commments/Corrective Measures CSP-ISI-70 / 2 CSP-ISI-210 /1 CSP-ISI-210 / 1 CSP-ISI-210 / 1 NRI NRI NRI NRI Reference Relief Request No.: RI-07. Examined In Accordance With Code Case N-509. Estimated ASME Code Required Volume From 600 = 74.5%.

This Component Was Previously Examined Under Component Numbers HNC-C1-1, HNC-C1-2 and HNC-C1-3.

4160211 Westinghouse R-134 MT CSP-ISI-70 / 2 NRI Examined In Accordance With Code Case N-509.

85.19% Estimated Code Coverage Achieved.

Notification 10126153 was written to document the less than 90% coverage.

B1020 RF FWC-BK1-8 8 Welded Lugs

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 8 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component.ID Configuration B-M-2 Category Components Examined Equal: 3 B12.50 cs CS-MO-12A-BM2 Valve-Body B12.50 HPCI B12.50 RF HPCI-MO-15-BM2 Valve-Body RF-16-CV-BM2 Valve-Body Work.Order Performed By Report No.

Exam 4159957 NPPD 4211015 NPPD 4209932 NPPD 4159957 VT-3 4211015 VT-3 4209932 VT-3 Procedure Results.Commments/Corrective Measures 3.28.1.3 Rev.4 NRI Inspection results documented in referenced CNS Work Order.

3.28.1.3 Rev.4 NRI Inspection results documented in referenced CNS Work Order.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 9 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration B-O Category Components Examined Equal: 2 CRD-50-23-1 CRD-50-27-1 CRD Housing - Fange CRD Housing - Fange Work Order Performed By Report No.

Exam 4160206 Westinghouse R-084 PT 4160206 Westinghouse R-085 PT Procedure Results Comm mentsCorrective Measures CSP-ISI-i1 / 3 NRI Reference Relief Request RI-15.

100% ASME code coverage was achieved.

CSP-ISI-11 / 3 NRI Reference Relief Request RI-15.

100% ASME code coverage was achieved.

B14.10 CRD B14.10 CRD

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component*ID Configuration Work Order B-P Category Components Examined Equal: 5 815.10 NB 6.MISC.502 Pressure Vessels 6.MISC.50 B15.50 NB 6.MISC.502.PIP Pressure Retaining Piping 6.MISC.50 B15.50 NBI VS.HD.FLGSEL.LEK.DETEC RPV-Pipe 4184927 B15.60 NB 6.MISC.502.PMP Pumps 6.MISC.50 B15.70 NB 6.MISC.502.VAL Valves 6.MISC.50 Page 10 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Performed By.Report No.

Exam Procedure Results NPPD 6.MISC.502 VT-2 6.MISC.502 Rev.1oC1 SAT NPPD 6.MISC.502 VT-2 6.MISC.502 Rev.10Cd SAT NPPD PM 10606 VT-2 7.0.8.1 Rev.12 SAT NPPD 6.MISC.502 VT-2 6.MISC.502 Rev.10C iSAT NPPD 6.MISC.502 VT-2 6.MISC.502 Rev.10Ci SAT CommmentslCorrective Measures Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections. Reference PM 10606.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 11 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration C-A Category Components Examined Equal: 2 C1.10 RHR RHR-CA-2A SH-DRET C1.10 RHR RHR-CA-4A DRET-DR Work.Order Performed By Report No.

Exam 4160200 Westinghouse R-153 UT-45*'

UT-45oS 4160200 Westinghouse R-154 UT-45°S UT-45oS Procedure Results Commments/Corrective Measures S

CSP-ISI-209 / 0 Is CSP-ISI-209 / 0 s

CSP-ISI-209 / 0 s

CSP-ISI-209 1 0 NRI These examinations were limited on the shell side NRI due to welded attachment, however 92.25% code coverage of the exam volume was achieved.

Reference Code Case N-460.

NRI This examination was limited on the downstream NRI side of the weld due to N4 nozzle, however 92%

code coverage was achieved. Reference Code Case N-460.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 12 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration C-B Category Components Examined Equal: 2 C2.21 RHR RHR-CB-1A THD-NOZ C2.22 RHR RHR-IR-1A THD-NIR Work Order Performed By Report No.

Exam 4160201 Westinghouse R-155 4160201 Westinghouse R-157 MT UT-45°S UT-60GS Procedure Results Commments/Corrective Measures CSP-ISI-70 / 2 NRI CSP-ISI-209 / 0 NRI CSP-ISI-209 / 0 NRI A limited examination was performed on the upstream side of weld due to head to nozzle configuration, however 90.3% code coverage was achieved.

UT-70°S CSP-ISI-211 / oC1 NRI UT-80°S CSP-ISI-211 / oC1 NRI

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System ComponentID Configuration Work Order C-C Category Components Examined Equal: 5 C3.10 RHR RHR-CC-2A SP-VES 4160200 C3.20 PNC PNC-CEI-5 Welded Attachment 4160216 C3.20 MS RSA-CC-25 Welded Lugs 4160218 C3.20 RCIC RWA-CC-52A Welded Attachment 4160219 C3.30 RHR RPA-CC-9 Integrally Welded Attachment 4160202 Page 13 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Performed By.Report No.

Exam Procedure Westinghouse R-156 MT CSP-ISI-70 / 2 Westinghouse R-124 MT CSP-ISI-70 I 2 Westinghouse R-098 MT CSP-ISI-70 / 2 Westinghouse R-132 MT CSP-ISI-70 I 2 Westinghouse R-158 MT CSP-ISI-70 1 2 Results NRI NRI NRI NRI NRI CommmentslCorrective Measures Examined In Accordance With Code Case N-509.

Examined In Accordance With Code Case N-509.

85.48% Estimated ASME Code Coverage Achieved. Notification 10126100 was written to address the less than 90% coverage.

Examined In Accordance With Code Case N-509.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 14 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures C-F-2 Category Components Examined Equal: 11 C5.51 CS-A CSA-CF-42 CSA-CF-53 PNC-CG-10 PSA-CF-9 RAS-CF-10 RAS-CF-4 RAW-CF-25 RBW-CF-18 RCT-CF-9 RHA-CF-2 RHB-CF-2 CSP-ISI-70 / 1c1 NRI ELBOW - PIPE PIPE - ELBOW Elbow - Flange Pipe - Elbow Reducer - Reducer Pipe - Elbow Pipe - Elbow Pipe - Tee Elbow-Pipe Pipe -Elbow Elbow - Pipe 4160053 Westinghouse R-071 MT UT-0o UT-45°S UT-60'S 4160053 Westinghouse R-072 MT UT-0° UT-45°S UT-60 0S 4160216 Westinghouse R-125 MT UT-0° UT-45°S UT-70°S 4160216 Westinghouse R-097 MT UT-45°S 4160201 Westinghouse R-138 MT UT-0° UT-45°S 4160201 Westinghouse R-139 MT UT-45°S 4160204 Westinghouse R-140 MT UT-45°S 4160204 Westinghouse R-141 MT UT-45°S 4160203 Westinghouse R-142 PT UT-45°S UT-70°S 4160204 Westinghouse R-143 MT UT-45°S 4160201 Westinghouse R-144 MT UT-45°S CSP-ISI-209 / 0 PDI-UT-1 / C PDI-UT-1 / C CSP-lSl-70 / iCi CSP-ISI-209 / 0 PDI-UT-1 / C PDI-UT-1 / C CSP-ISI-70 / 2 CSP-ISI-209 / 0 PDI-UT-1I / C PDI-UT-1 / C CSP-ISI-70 / 2 PDI-UT-1 / C CSP-ISI-70 / 2 CSP-ISI-209 / 0 PDI-UT-1I / C CSP-ISI-70 / 2 PDI-UT-1 / C CSP-ISI-70 / 2 PDI-UT-1 / C CSP-ISI-70 / 2 PDI-UT-1

/ C CSP-ISI-11 I/3 PDI-UT-1 / C PDI-UT-1

/ C CSP-ISI-70 i 2 PDI-UT-1 / C CSP-ISI-70 / 2 PDI-UT-1

/ C NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI ID RG NRI IDG NRI NRI NRI NRI ID RG NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI C5.51 C5.51 C5.51 C5.51 C5.51 C5.51 C5.51 C5.51 C5.51 CS-A PNC MS RHR RHR RHR RHR RHR RHR 100% ASME Code coverage was achieved.

100% ASME Code Coverage Was Achieved.

This is a Base-Line exam on this component.

Code Case N-460, 90.9% ASME Code coverage Was Achieved.

100% ASME Code coverage was achieved.

100% ASME code coverage was achieved.

100% ASME Code coverage was achieved. One recordable indication was detected and determined to be ID root geometry.

100% ASME Code coverage was achieved.

100% ASME code coverage was achieved.

100% ASME Code coverage was achieved.

C5.51 RHR

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 15 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration C-H Category Components Examined Equal: 24 Work Order.Performed By ReportNo.

Exam, Procedure Results CommmentslCorrective Measures C7.10 RHR 6.IRHR.501 6.MISC.502.CRD 6.REC.501 6.1CS.501 6.1RHR.501.PIP 6.2CS.501 6.HPCI.502 6.MISC.502.CRD.PIP 6.RcIc.501 6.RCIC.502 6.REC.501.PIP Piping 6.1RHR.5 NPPD Pressure Vessels Pressure Vessels Pressure Vessels Piping Piping Piping Piping Piping Piping Piping NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD 6.REC.501 NPPD 6.1RHR.501 VT-2 6.MISC.502 V'-2 6.REC.501 VT-2 6.1CS.501 VT-2 6.1RHR.501 VT-2 6.2CS.501 VT-2 6.HPCI.502 VT-2 6.MISC.502 VT-2 6RClC.501 VT-2 6.RCIC.502 Vr-2 6.1RHR.501 Rev.6 6.MISC.502 Rev.ioCi 6.REC.501 Rev.6 6.lCS.501 Rev.5 6.1RHR.501 Rev.6 6.2CS.501 Rev.4 6.HPCI.502 Rev.0 6.MISC.502 Rev.10C1 6.RCIC.501 Rev.5 6.RCLC.502 Rev.0 6.REC.501 VT-2 6.REC.501 Rev.6 SAT Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and aii applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

6.MISC.50 6.REC.501 6.1CS.501 6.1 RHR.5 6.2CS.501 6.HPCI.50 6.MISC.50 6.RCIC.50 6.RCLC.50 C7.10 C7.10 C7.30 C7.30 C7.30 C7.30 C7.30 C7.30 C7.30 CRD REC Os RHR CS HPCI CRD RCIC RCIC C7.30 REC

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 16 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System C7.50 C7.50 C7.50 C7.50 C7.50 C7.70 C7.70 C7.70 C7.70 C7.70 C7.70 C7.70 Cs RHR Cs RCIC REC cs RHR cs HPCI CRD RClC RCIC Component ID 6.lCS.501.PMP 6.IRHR.501.PMP 6.2CS.501.PMP 6.RCIC.501.PMP 6.REC.501.PMP 6.1CS.501.VAL 6.1RHR.501.VAL 6.2CS.501.VAL 6.HPCI.502.VAL 6MISC.502.CRD.VAL 6.RCIC.501.VAL 6.RCIC.502.VAL Configuration Pump Pumps Pump Pumps Pumps Valves Valves Valves Valves Vlaves Valves Pumps Work Order Performed By Report No.

6.1CS.501 NPPD 6.1RHR.5 6.2CS.501 6.RCIC.50 6.REC.501 6.1cs.501 6.1RHR.5 6.2CS.501 6.HPCI.50 6.MISC.50 6.RCIC.50 6.RCIC.50 NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD NPPD Exam 6.1CS.501 VT-2 6.1CS.501 Rev.5 6.1RHR.501 6.2CS.501 6.RCIC.501 6.REC.501 6.1CS.501 6.iRHR.501 6.2CS.501 6.HPCI.502 6.MISC.502 6.RCOC.501 6.RCIC.502 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Vr-2 6.1RHR.501 Rev.6 6.2CS.501 Rev.4 6.RCLC.501 Rev.5 6.REC.501 Rev.6 6.1CS.501 Rev.5 6.1RHR.501 Rev.6 6.2CS.501 Rev.4 6.HPCI.502 Rev.0 6.MISC.502 Reviic1 6.RCIC.501 Rev.5 SAT Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

SAT SAT SAT SAT SAT SAT SAT SAT SAT SAT 6.RCLC.502 Rev.0 SAT Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section X1, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

Procedure Results Commments/Corrective Measures

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 17 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System C7.70 REC Component ID 6.REC.501.VAL Configuration Valves Work Order Performed By Report No.

Exam 6.REC.501 NPPD 6.REC.501 V'-2 Procedure Results Commments/Corrective Measures 6.REc.501 Rev.6 SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component.ID Configuration Work Order D-A Category Components Examined Equal: I 01.10 NBI 6.NBI.501 Pressure Retaining Component 6.NBI.501 Page 18 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Performed By Report No.

Exam NPPD 6.NBI.501 VT-2 Procedure Results CommmentslCorrective Measures 6.NBI.501 Rev.6 SAT Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component ID Configuration Work Order D-B Category Components Examined Equal: 4 D2.10 Sw 6.1SW.501 Pressure Retaining Component 6.1SW.50 D2.10 SW 6.2SW.502 Pressure Retaining Component 6.2SW.50 D2.10 NBI 6.NBI.501.PRC Pressure Retaining Component 6.NBI.501 D2.10 REC 6.REC.501.PRC Pressure Retaining Component 6.REC.501 Page 19 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Performed ByReport No.

Exam Procedure..

NPPD R-226 VT-2 6.1SW.501 Rev.8 NPPD R-227 VT-2 6.2SW.502 Rev.7 NPPD 6.NBI.501 VT-2 6.NBI.501 Rev.6 NPPD 6.REC.501 VT-2 6.REC.501 Rev.6 Results SAT SAT SAT SAT Commments/Corrective Measures Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section Xl, 1989 Edition, No Addenda and all applicable procedure sections.

Pressure testing performed in accordance to ASME Section XI, 1989 Edition, No Addenda and all applicable procedure sections.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 20 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration Work Order Performed By.Report No..

Exam Procedure Results Commments/Corrective Measures F-A Category Components Examined Equal: 22 FI.10.A RF RFH-61 Sway Strut Constant Spring Trapeze Sway Strut Sway Strut Stanchion Sway Strut Sway Strut Stanchion Sway Strut Ridged Restraint 4160211 Westinghouse R-137 4160213 4160216 4160216 4160216 4160216 4160216 4160202 4160203 4160218 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-164 R-126 R-127 R-128 R-129 R-130 R-146 R-147 R-096 VT-3 vr-3 VT-3 Vr-3 VT-3 VT-3 VT-3 Vr-3 VT-3 vr-3 CSP-ISI-8 I 0 RI CSP-ISI-8 / 0 CSP-ISI-8 i 0 CSP-ISI-8 / 0 CSP-lSl-8 / 0 CSP-ISI-8 / 0 CSP-lSl-6 / 0 CSP-ISI-8 / 0 CSP-lSI-8 / 0 CSP-lSI-8 / 0 NRI NRI NRI NRI NRI NRI NRI NRI NRI Examined In Accordance With Code Case N-491.

Notification 10124859 was written to document the missing jam nut and Notification 10124860 was written to document stiffener plates that were not identified on the support drawing. Engineering evaluation determined both conditions to be SAT.

Examined In Accordance With Code Case N-491.

F1.10O.C Fl.20.A FI.20A F1.20.A Fl.20.A FI.20.A F1.20.A Fl.20.A F1.208 RWCU PNC PNC PNC PNC PNC RHR RHR MS CU-H50 PVH-108 PVH-109 PVH-110 PVS-IB&R PVS-2B&R RHH-2 RHH-52A MSH-99

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 21 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System F1.20.C MS F1.20.C F1.20.C F1.20.C F1.20.C FI.30.B F1.30.C Fl.40A F1.40.A Fl.40.A Fl.40.A MS RCIC RHR RHR SW SW RHR RHR RHR RHR Component ID MSH-106 MSH-121 RCH-6 RHH-10 RHH-62 SW-H-62A SW-H-60 RHHX-1A1 RHHX-1A2 RHHX-1A3 RHHX-1A4 Configuration Wo Constant Spring Trapeze Dual Spring Hanger Variable Spring Hanger Variable Spring Hanger Variable Spring Hanger Trapez Ridgid Hanger Variable Spring Hanger PW PW Pvv PW ork Order Performed By Report No.

Exam 4160218 Westinghouse R-094 4160218 4160219 4160204 4160203 4160217 4160217 4160200 4160200 4160200 4160200 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-095 R-131 R-145 R-148 R-169 R-168 R-149 R-150 R-151 R-152 V'-3 VT-3 VT-3 VT-3 Vr-3 VT-3 Vr-3 VT-3 VT-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures CSP-ISI-8 / 0 RI Examined In Accordance With Code Case N-491.

The two recordable indications are considered SAT base Engineering Evaluation.

Notification 10127173 was written to document the condition. 11/24/01. TPM CSP-ISi-8 / 0 NRI Examined In Accordance With Code Case N-491.

CSP-ISI-8 / 0 RI Examined In Accordance With Code Case N-491.

The recordable condition is considered SAT based on Engineering Evaluation. Notification 10125143 was written to document condition.

CSP-ISI-8 / 0 NRI Examined In Accordance With Code Case N-491.

CSP-ISI-8 i/0 RI Examined In Accordance With code Case N-491.

Notification 10129110 was written to documentsa missing load scale on the north west spring can.

Condition determined SAT based on Engineering evaluation.

CSP-iSi-8 I 0 NRI Examined In Accordance With Code Case N-491.

CSP-ISI-8 / 0 NRI Examined In Accordance With Code Case N-491.

CSP-ISI-8 i 0 NRI Examined In Accordance With Code Case N-491.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 22 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System FI.40.A NB Component ID RPV-SKIRT Configuration Ridge Structual Fram Work Order Performed By Report No.

Exam 4160194 Westinghouse R-123 VT-3 Procedure Results Commments/Corrective Measures CSP-ISI-8 / 0 NRI Examined In Accordance With Code Case N-491.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 23 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration XMA-AUG Category Components Examined Equal: 3 Augm RR RRPC-IA-BGI Pump - Cover Augm RWCU Augm RWCU RWCU-13 RWCU-26 Pipe - Elbow Pipe - Elbow Work Order Performed By Report No.

Exam 4160205 Westinghouse R-161 4160214 Westinghouse R-166 4160215 Westinghouse R-167 VT-1 Procedure Results Commments/Corrective Measures CSP-ISI-8 / 0 NRI This exam was performed for information only.

Examined visible portions of RR-1A pump cover, pump was assembled, in conjunction with required Cat: B-G-1 RR-1A pump bolting, nuts, and washer examinations. Examination of pump cover/Iflange surface areas is only required when RR pump is disassembled.

UT-45°S PDI-UT-2 / C NRI UT-70°S PDI-UT-2 / C IDG UT-45'S PDI-UT-2 / C NRI

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 24 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Configuration XMA-REC Category Components Examined Equal: 72 A11.12 REC-A Al1.12 REC-A Al 1.12 A11.12 Al1.12 Al1.12 A11.12 A11.12 Al1.12 REC-A REC-A REC-A REC-NCL REC-NcL REC-NCL REC-B All-12 REC-B 2848-14-WIO 2848-14-WIl 2848-14-W12 2848-14-W13 2848-14-W9 2848-16-W31 2848-16-W36 2848-16-WP 2848-2-W34 2848-2-W36 ELBOW - PIPE PIPE-TEE TEE - PIPE PIPE - CAP PIPE - ELBOW PIPE - PIPE PIPE - PIPE PIPE - ELBOW PIPE - ELBOW PIPE-TEE Work Order Performed ByReport No.

4160048 Westinghouse R-001 4160048 Westinghouse R-002 4160048 4160048 4160048 4160051 4160051 4160045 4160050 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-003 R-004 R-005 R-006 R-007 R-008 R-009 Exam UT-45°S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45 0S UT-70°S UT-450S UT-70°S UT-45°S UT-70os UT-45°S UT-70oS UT-45 0S UT-70°S UT-45°S UT-70°S Procedure Results Commments/Corrective Measures CSP-ISI-208 / oCl NRI CSP-ISI-208 / oCl cSP-ISI-208 / oci CSP-ISI-208 / oC1 CSP-ISI-208 / oC1 CSP-ISI-208 / oC1 cSP-ISI-208 / oCI cSP-ISI-208 / oCi cSP-IsI-208 / oci CSP-ISI-208 / oCi CSP-ISI-208 / OCI CSP-ISI-208 / OCl CSP-ISI-208 / oC1 CSP-ISI-208 / oCi CSP-ISI-208 I oCi CSP-ISI-208 ! oCi CSP-ISI-208 oCl CSP-ISI-208 / oC1 IDG IDG RG RG RG NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI 4160050 Westinghouse R-010 UT-45°S CSP-ISI-208 / oCI NRI UT-70°S CSP-ISI-208 / oC1. IDG Examination performed per the Augmented IS[

Program Section 11.12. Two (2) indications were detected and determined to be root geometry.

Examination performed per the Augmented iSI Program Section 11.12. Two (2) indications were detected with one to be root geometry and the other was determined to be a fabrication discontinuity.

Examination performed per the Augmented IS[

Program Section 11.12. One (1) recordable indication was detected and determined to be ID root geometry.

Examination performed per the Augmented ISI Program Section 11.12.

Examination was perforemd to meet the requirements of the Augmented ISI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12. Examined repair area per WO 4203836-35.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 25 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 REC-B Al1.12 Al1.12 All-12 Al1.12 Al1.12 REC-B REC-B REC-B REC-B REC-SCL Al1.12 REC-SCL A11.12 REC-SCL A11.12 REC-SCL A11.12 REC-NCL Al1.12 REC-B Component ID 2848-2-W36 2848-2-W37 2848-2-W37A 2848-2-W38 2848-2-W39 2848-2-W51 2848-2-W62 2848-2-W69 2848-2-W70 2848-2-W72 2848-2-W81 Configuration PIPE -TEE TEE - PIPE PIPE - PIPE PIPE - FLANGE TEE - PIPE Pipe - Tee ELBOW - PIPE REDUCER - TEE REDUCER-TEE ELBOW - PIPE REDUCER - FLANGE Work Order Performed By Report No.

Exam 4160050 Westinghouse R-010 UT-45°S UT-70°S UT-60°RL 4160050 Westinghouse R-01 1 UT-45°S UT-70°S 4160050 Westinghouse R-012 UT-45°S UT-70°S 4160050 Westinghouse R-013 UT45°S UT-70°S 4160050 Westinghouse R-014 UT-45°S UT-70°S 4159603 Westinghouse R-171 UT-45°S UT-70°S 4160047 Westinghouse R-015 UT-45°S UT-70°S 4160047 Westinghouse R-016 UT-45°S UT-70°S 4160047 Westinghouse R-017 UT-450S UT-70°S 4160045 Westinghouse R-018 UT-45°S UT-70°S 4160050 Westinghouse R-019 UT-45*S Procedure Results Commments/Corrective Measures CSP-ISI-208 OCI NGI CSP-ISI-208 I OC1 NGI CSP-ISI-299 / 0 CSP-ISI-208 /OCI CSP-ISI-208 / OCl CSP-ISI-208 / OCi CSP-ISl-208 / OCl CSP-ISI-208o IOCl CSP-ISI-208o

/OCl CSP-ISI-208 / OCi CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 / OCI CSP-ISI-208 / OC1 CSP-ISI-208 / OC1 CSP-ISl-208 / OCl CSP-ISI-208 I OCI CSP-ISI-208 I OCi CSP-ISI-208 I OCl CSP-ISI-208 / OC1 CSP-ISI-208 / OCi NGI NRI IDG NRI RG, F NRI NRI NRI RG NRI IDG NRI NRI NRI NRI NRI RG NRI IDG CSP-ISI-208 I OC1 NRI UT-70°S CSP-ISI-208 / OCi NRI Examination performed per the Augmented ISI Program Section 11.12. A non-geometric indication was detected. Notification 10118213 was written to identify the condition. The notification recommended the indication be repaired as good practice. Repair completed per WO 4203836 and re-examined. One geometric indication of the repair was determined to be root geometry.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed following a repair during RE20. Original indication was found during RE19 and documented on Westinghouse Report No.R 047 as part of the ISI Augumented Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented IS[

Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12-

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 26 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 Al1.12 A11.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 REC-B REC-SCL REC-SCL REC-NCL REC-SCL REC-NCL REC-NCL REC-SCL REC-ENC REC-ENC REC-ENC REC-ENC Component ID 2848-2-WM 2848-2-WO 2848-2-WP 2848-2-WR 2848-2-WT 2848-50-WF 2848-50-WFG 2848-50-WL 2848-51-WAL 2848-51 -WCA 2848-51-WCB 2848-51-WW Configuration ELBOW - PIPE VALVE - REDUCER VAVLE - PIPE ELBOW -VALVE PIPE - ELBOW TEE - PIPE PIPE - ELBOW ELBOW - PIPE PIPE - PIPE PIPE - WOL WOL-FLANGE ELBOW - PIPE Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures 4160050 Westinghouse R-020 UT-45°S CSP-ISI-208 oC1 NRI 4160047 4160047 4160045 4160047 4160051 4160051 4160052 4160043 4160043 4160043 4160043 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse UT-70°S R-021 UT-45'S UT-70°S R-022 UT-45°S UT-70°S R-023 UT-45°S UT-70°S R-024 UT-45°S UT-70oS R-025 UT-45os UT-70Os R-026 UT-45°S UT-70°S R-027 UT-45°S UT-70°S R-028 UT-45°S UT-70°S R-029 UT-45°S UT-70°S R-030 UT-450S UT-70°S R-031 UT-45oS CSP-ISI-208 0/OC1 RG CSP-ISI-208 0/OC1 CSP-ISI-208 /OCI CSP-ISI-208 / OC1 CSP-ISI-208 I/OCi CSP-ISI-208 / OCi CSP-ISI-208 / OCI CSP-ISI-208 / OCi CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 OCl CSP-ISI-208 / OC1 CSP-ISI-208 I OCl CSP-ISI-208 / OCi CSP-ISI-208 / OCl CSP-ISI-208 / OCI CSP-ISI-208 I OCi CSP-ISI-208 / OCl CSP-ISI-208 I OCl CSP-ISI-208 0OCl CSP-ISI-208 / OCl CSP-ISI-208 I/OCl NRI NRI NRI IDG NRI NRI NRI IDG NRI NRI NRI NRI NRI NRI NRI FD NRI NRI NRI NRI NR[

UT-70°S CSP-ISI-208 I OC1 NRI Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

NIS-1, Table 1.1, RE2O: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 27 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 REC-ENC Al1.12 REC-ENC Al1.12 REC-SCL Al1.12 REC-SCL A1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL A1.12 REC-SCL Component ID 2848-51-WX 2848-51-WZ 2848-55-Wl 2848-55-W14 2848-55-W16 2848-55-W17 2848-55-WI8 2848-55-WI9 2848-55-W2 2848-55-W20 2848-55-W3 2848-55-W4 Configuration PIPE - ELBOW PIPE - ELBOW PIPE -VALVE REDUCER - ELBOW ELBOW - PIPE PIPE - ELBOW ELBOW - PIPE PIPE - ELBOW ELBOW - PIPE ELBOW - PIPE PIPE - ELBOW ELBOW - PIPE Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures 4160043 Westinghouse R-032 UT-45°S CSP-ISI-208 I OC1 NRI 4160043 4160049 4160049 4160049 4160049 4160049 4160049 4160049 4160049 4160049 4160049 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-033 R-034 R-035 R-036 R-037 R-038 R-039 R-040 R-041 R-042 R-043 UT-70°S UT-456S UT-70°S UT-45°S UT-70°S UT-45*S UT-70°S UT-45°S UT-70°S UT-45 05 UT-70°S tJT-45*S uT-70*S UT-45oS UT-70°S UT-45°S UT-70°S UT-45°S UT-70oS UT-45°S UT-70°S UT-45°S CSP-ISI-208 I OCl CSP-ISI-208 / OCI CSP-ISI-208 / OC1 CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 I OCl CSP-ISI-208 / oCi CSP-ISI-206 / OC1 CSP-ISI-208 / OCi CSP-ISI-208 0/OC1 CSP-ISI-208 / OC1 CSP-ISI-208 / OCl CSP-ISI-208 0/OC1 CSP-ISI-208 / OC1 CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 / OCl CSP-ISI-208 I OC1 CSP-ISI-208 / oci NRI RG, F NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI UT-70°S CSP-ISI-208 I OCl NRI CSP-ISI-208 / 0C1 RG Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented IS]

Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented iSI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented iSI Program Section 11.12.

Examination performed per the Augmented Isi Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 28 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 Al1.12 A11.12 All-12 REC-SCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL REC-NCL Component ID 2848-55-W5 2848-57-Wl 2848-57-W14A 2848-57-WI5 2848-57-W16 2848-57-WI7 2848-57-WI8 2848-57-WI9 2848-57-W20 2848-57-W3 2848-57-W34 2848-57-W4 Configuration PIPE - ELBOW REDUCER - ELBOW PIPE - REDUCER ELBOW - PIPE PUP PIECE - ELBOW ELBOW-PUP PIECE PIPE - ELBOW ELBOW - PIPE PIPE - ELBOW ELBOW - PIPE PIPE - PIPE PIPE - ELBOW Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures 4160049 Westinghouse R-044 UT-45°S CSP-ISI-208 OC1 NRI 4160044 4160044 4160044 4160044 4160044 4160044 4160044 4160044 4160044 4160044 4160044 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-045 R-046 R-047 R-048 R-049 R-050 R-051 R-052 R-053 R-054 R-055 UT-70°S UT-45*S UT-70°S UT-45°S UT-70*S UT-45°S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-456S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45°S CSP-ISI-208 0

OC1 NRI CSP-ISI-208 0/OC1 CSP-ISI-208 /OCl CSP-ISI-208 I/OCI CSP-ISI-208 I/OC1 CSP-ISI-208 / OC1 CSP-ISI-208 I OCI CSP-ISI-208 / OCi CSP-ISI-208 / OC1 CSP-ISI-208 I OCI CSP-ISI-206 /OC1 CSP-ISI-208 I/OC1 CSP-ISI-208 / OC1 CSP-ISI-208 I/OC1 CSP-ISI-208 I/OC1 CSP-ISI-208 / OCi CSP-ISI-208 I/OC1 CSP-ISI-2068/OC1 CSP-ISI-208 / OCI CSP-ISI-208 I OC1 CSP-ISI-208 I OC1 CSP-ISI-208 / OC1 NRI RG, F NRI NRI NRI RG, F NRI NRI NRI NRI NRI FD NRI IDG NRI RG, F NRI NRI NRI NRI NRI UT-70°S CSP-ISI-208 I OC1 IDG Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented IS[

Program Section 11.12.

Examination performed per the Augmented IS[

Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented IS]

Program Section 11.12.

NIS-1, Table 1.1, RE20: IS[ Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 29 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 REC-NCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL All112 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL All-12 REC-SCL Component ID 2848-57-W5 2848-9-WO 2848-9-W3 2848-9-W37 2848-9-W38 2848-9-W41 2848-9-W75 2848-9-W76 2848-9-W77 2848-9-W78 2848-9-W82 2848-9-W83 Configuration ELBOW - PIPE PIPE - ELBOW PIPE - PIPE PIPE - PIPE PIPE - ELBOW ELBOW-PIPE PIPE - PIPE ELBOW - PIPE PIPE - ELBOW ELBOW - PIPE REDUCER - PIPE VALVE - REDUCER Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures 4160044 Westinghouse R-056 UT-45°S CSP-ISI-208 OCl NRI 4160049 4160052 4160049 4160049 4160049 4160049 4160049 4160049 4160049 4160049 4160049 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse R-057 R-058 R-059 R-060 R-061 R-062 R-063 R-064 R-065 R-066 R-067 UT-70°S UT-45°S UT-70°S UT-45°S UT-70oS IJT-45'5 UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45*S UT-70°S UT-45°S UT-70°S UT-45°S UT-70°S UT-45oS UT-70'S UT-45°S UT-70°S UT-45°S CSP-ISI-208 I OC1 IDG CSP-ISI-208 / OC1 CSP-ISI-208 / OC1 CSP-ISI-208 I OC1 CSP-ISI-208 / OC1 CSP-ISI-208 / OCi CSP-ISI-208 / OC1 CSP-ISI-208 / OCi CSP-ISI-208 / OC1 CSP-ISI-208 / OC1 CSP-ISI-208 I OC1 CSP-ISI-208 / oci CSP-ISI-208 I OC1 CSP-ISI-208 I OCI CSP-ISI-208 I OC1 CSP-ISI-208 / OCi CSP-ISI-208 I OC1 CSP-ISI-208 / OCi CSP-ISI-208 I OC1 CSP-ISI-208, OCi CSP-ISI-208 / IOC CSP-ISI-208 I OC1 NRI SI NRI RG NRI NRI NRI NRI NRI NRI NRI NRI NRI RG NRI NRI NRI NRI IDG NRI NRI UT-70°S CSP-ISI-208 / OC1 RG Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented iSI Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented iSI Program Section 11.12.

Examination performed per the Augmented Isi Program Section 11.12.

Examination performed per the Augmented ISI Program Section 11.12.

NIS-1, Table 1.1, RE20: ISI Examinations Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 30 of 30 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Al1.12 REC-SCL Al1.12 REC-SCL Al1.12 REC-SCL Component ID 2848-9-W88 2848-9-WJ 2848-9-WX Configuration PIPE - PIPE ELBOW - PIPE ELBOW - PIPE Work Order Performed By Report No.

Exam 4160052 Westinghouse R-068 UT-45°S UT-70°S 4160049 Westinghouse R-069 4160052 Westinghouse R-070 Procedure Results Commments/Corrective Measures CSP-ISI-208 / oC1 NRI Examination performed per the Augmented IS!

CSP-ISI-208 / oCi NRI Program Section 11.12.

UT-45°S CSP-ISI-208 / 0C1 NRI UT-70°S CSP-ISI-208 / OCl NRI UT-45°S CSP-ISI-208 / oC1 NRI UT-70°S CSP-ISI-208 oC1 NRI Examination performed per the Augmented ISI Program Section 11.12.

Examination performed per the Augmented IS!

Program Section 11.12.

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page I of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component ID Containment Section E-C Category Components Examined Equal:

E4.11.

B-DWN-ID-SS Bay 1, Downcomer Submerged Section Interior Surface Class: Mc System: PC MWR No. 00-2410 E4. 11 BI.-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 Bay 1, Downcomer Submerged Section Exterior Surface Including Attachment Welds B1-INT-SS Bay 1, Submerged Section Including Attachment Welds Class: Mc System: PC MWR No. 00-2410 E4.11 B10-DWN-ID-SS Class: Mc System: PC MWR No. 00-2410 E4.11 BI0-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 Bay 10, Downcomer Submerged Section Interior Surface Bay 10, Downcomer Submerged Section Exterior Surface Including Attachment Welds E4.11 Bi0-INT-SS Bay 10, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 Report No.

Exam Procedure 49 CNSOI-001 VT-i 0 1634-3, Rev 1 Performed By:

Underwater Construction Corporation CNSOI-001 VT-i 01 634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS01 -001 VT-i 01634-3, Rev 1 Performed By:

underwater Construction Corperation Results I Corrective Measures VT-1 examinations were performed on the accessible interior-surface areas (approximately 18" from the bottom)),

including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-1. These examinations were not scheduled, but were performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Some tiger striping with discoloration and beginning of pinpoint rusting was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted for-Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-1. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to bracing was observed. Random pitting, mostly within the tiger stiping was observed. None of the pitting exceeded the threshold for recoating or further engineering evaluation. Some isolated corrosion cells with slight metal loss and discoloration over most of the downcomer was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted for Code credit in the submerged section, including attachment welds, of the referenced Torus Bay in accordance to ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Record no.

1-1. Isolated to random areas of pitting corrosion, ranging from pinpoint rusting to uniform corrosion was observed.

None of the pits exceeded the examination screening criteria requiring further engineering evaluation. Small areas of mechanical damage, especially near the invert weld seam were observed. Areas of discoloration were observed throughout and near the ring girders. At the waterlines, some tiger striping with pinpoint rusting with uniform corrosion were observed. At the ring girder adjacent to each gusset plate on the web of the girder, isolated areas of uniform rusting with 100% coating loss was discovered. Discoloration, pinpoint rusting and uniform corrosion concentrated at the invert weld seam. Random areas of discoloration and pinpoint rusting, with isolated pitting were found on the balance of the general shell. Near the ring girder regions, tiger striping was more prevalent and advanced, as was the pinpoint and uniform corrosion. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

CNS01-010 VT-1 01634-3, Rev1 VT-i examinations were performed on the accessible interior surface areas including attachmentwelds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section X1, 1992 Performed By:

Edition, 1992 Addenda. Reference UCC Record number 1-10. These examinations were not scheduled, but were Underwater Construction Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss were observed near the bottom of the downcomers. Some tiger striping with discoloration and the beginning of pinpoint rusting were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

cNSo*-010 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation "CNSOl-010 VOT-01634-3, Rev 1 Performed By:

Underwater Construction Corporation VT-I examinations were conducted for code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-10. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to the bracing were observed. Random pitting mostly within the tiger striping was observed.

None of the pits exceeded the examination screening criteria requiring further engineering evaluation nor recoating.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Additional-VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-10 and 3-10. These additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a) of ASME Section XI, 1992 Edition, 1992 Addenda.. Pitting was observed. However, none of the pits exceeded the examination screening criteria requiring further engineering evaluation. Pits exceeding the examination screening criteria for recoating were recoated. Areas of discoloration and tiger striping were observed throughout. Small areas of mechanical damage were observed. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 2 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component.ID E4.11 B11-DWN-ID-SS Class: Mc System: PC MWR No. 00-2410 E4.11 B11-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Containment Section Bay 11, Downcomer Submerged Section Interior Surface Bay 11, Downcomer Submerged Section Exterior Surface Including Attachment Welds B11-INT-SS Bay 11, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 E4.11 B12-DWN-ID-SS Class: MC System: PC MWR No. 00-2410 E4.11 B12-DWN-OD-SS Class: Mc System: PC MWR No. 00-2410 E4.11 Bay 12, Downcomer Submerged Section Interior Surface Bay 12, Downcomer Submerged Section Exterior Surface Including Attachment Welds B12-INT-SS Bay 12, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 Report No.

Exam Procedure CNS01-011 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation cNSOIll-

.VT-i

.0e1634-3, RevlI Performed By:

Underwater Construction Corporation CNSO1 -011 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation CNS01-012 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation CNSOI-012 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation CNS01-012 VT-1 01634-3, Revi1 Performed By:

Underwater Construction Corporation Results I Corrective Measures VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-11. These examinations were not scheduled, but were performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss were observed near the bottom of the downcomers. Some tiger striping with discoloration and the beginning of pinpoint rusting were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-11. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to the bracing were observed. Random pitting mostly within the tiger striping was observed.

None of the pits exceeded the examination screening criteria requiring further engineering evaluation nor recoating.

These conditions are noted but represent littie or no degradation to the base metal and therefore are acceptable.

Additional VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records number 1-11, 2-11, and 3-11. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell.

Therefore, no conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-12. These examinations were not scheduled, but were performed to provide information on surface conditions. ome isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed on the bottom 12" of the downcomer. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-12. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

"Additional VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay assa result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-12, 2 12, and 3-12. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an alternative to IWE-2430(a).

Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline.

No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 3 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component ID E4.11 B13-DWN-ID-SS Class: MC System: PC MWR No. 00-2410 E4 11 B13-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Containment Section Bay 13, Downcomer Submerged Section Interior Surface Bay 13, Downcomer Submerged Section Exterior Surface Including Attachment Welds B13-INT-SS Bay 13, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 E4.11 B14-DWN-ID-SS Class: MC System: PC MWR No. 00-2410 E4.1 1.

B14-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 Report No.

Exam Procedure CNS01-013 VT-1 01634-3, Rev 1 Performed By:

Underwater Construction Corporation c~s~i~o ev CNSOI-013 VT-I 01634-3. Rev 1 Performed By:

Underwater Construction Corporation CNS01-013 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation Bay 14, Downcomer Submerged CNS01-014 Section Interior Surface Bay 14, Downcomer Submerged Section Exterior Surface Including Attachment Welds Performed By Underwater Cons Results I Corrective Measures VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-13. These examinations were not scheduled, but were performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Some tiger striping with discoloration and beginning of pinpoint rusting was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-13. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to bracing was observed. Random pitting, mostly within the tiger stiping was observed. None of the pitting exceeded the threshold for recoating or further engineering evaluation. Some isolated corrosion cells with slight metal loss and discoloration over most of the downcomer was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

"Additional VT-i examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay assa result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-13.

These additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an alternative to IWE-2430(a) of ASME Section XI, 1992 Edition, 1992 Addenda. Isolated to random areas of pitting corrosion, ranging from pinpoint rusting to uniform corrosion was observed. None of the pits exceeded the examination screening criteria requiring further engineering evaluation or coating. Small areas of mechanical damage, especially near the invert weld seam were observed. Areas of discoloration were observed throughout and near the ring girders. At the waterlines, some tiger striping with pinpoint rusting with uniform corrosion were observed. At the ring girder adjacent to each gusset plate on the web of the girder, isolated areas of uniform rusting with 100% coating loss was discovered. Discoloration, pinpoint rusting and uniform corrosion concentrated at the invert weld seam. Random areas of discoloration and pinpoint rusting, with isolated pitting were found on the balance of the general shell. Near the ring girder regions, tiger striping was more prevalent and advanced, as was the pinpoint and uniform corrosion. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 01634-3, Rev 1 VT-i examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-14. These examinations were not scheduled, but were struction Corporation performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Some tiger striping with discoloration and beginning of pinpoint rusting was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

CNS01-014 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation VT-I examinations-were conducted on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-14. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

I ----

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: I Page 4 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component ID E4.11 B14-INT-SS Class: MC System: PC MWR No. 00-2410 E4 11.

.15-DWN-ID-SS Class: MC System: PC MWR No. 00-2410 E4,11 B15-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Containment Section Bay 14, Submerged Section including Attachment Welds Report No.

Exam CNSo1-014.V-i Performed By:

Procedure 01634-3, Rev 1 Underwater Construction Corporation Bay 15, Downcomer Submerged Section Interior Surface "Bay 15, Downcomer Submerged Section Exterior Surface Including Attachment Welds B15-INT-SS Bay 15, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 CNS01-015 vr-i Performed By:

Underwater Construction C Results I Corrective Measures Additional VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay assa result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-14,2 14, and 3-14. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an altemative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline.

No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-15. These examinations were not scheduled, but were Corporation performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Some tiger striping with discoloration and beginning of pinpoint rusting was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

CNSOI-015 VT-i 0 1634-3, Rev 1 Performed By:

Underwater Construction Corporation "CNSOI-015 VT-1i 01634-3, Rev1 Performed By:

Underwater Construction Corporation VT.1-I examinations.were conducted on theeexterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-15. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

"Additional VT-i examinations were conducted in the submergedlsection, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records number 1-15, 2-15, and 3-15. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR S/N 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell.

Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline. No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

E4.11 B16-DWN-ID-SS Class: MC System: PC MWR No. 00-2410 Bay 16, Downcomer Submerged Section Interior Surface CNS01-016 VT-i Performed By:

Underwater Construction C 01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-16. These examinations were not scheduled, but were Corporation performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Some tiger striping with discoloration and beginning of pinpoint rusting was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 5 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Containment Section Bay 16, Downcomer Submerged Section Exterior Surface Including Attachment Welds INT-SS Bay 16, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2401 E4.11 B2-DWN-ID-SS Bay 2, Downcomer Submerged Section Interior Surface Class: MC System: PC MWR No. 00-2410 E4.1 1

.B2-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Bay 2, Downcomer Submerged Section Exterior Surface Including Attachment Welds B24NT-SS Bay 2, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 E4.11 B3-DWN-ID-SS Bay 3, Downcomer Submerged Section Interior Surface Class: MC System: PC MWR No. 00-2410 E4. 11 B3-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 "Bay 3, Downcomer Submerged Section Exterior Surface Including Attachment Welds Item No.

Component ID E4.11 B16-DWN-OD-SS tem: PC Class: MC Sysi MWR No. 00-2410 E4.11 B16-1 Report No.

Exam Procedure CNSOI0-016 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corporation "CNS01-016 V.-i 01 634-3, Rev 1 Performed By:

Underwater Construction Corporation CNS01-002 VT-i

.01634-3, Rev 1 Performed By:

Underwater Construction Corporation "CNS0i-002 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS01-002 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS0oi-003 VT-i 01 634-3, Rev I Performed By:

Underwater Construction Corporation CNSOi-003 VT-.1i 634-3, Rev 1 Performed By:

Underwater Construction Corperation Results I Corrective Measures VT-1 examinations were conducted on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-16. These examinations were not scheduled at this time, but were performed to provide information on surface conditions. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to the bracing were observed. Random pitting mostly within the tiger striping was observed.

None of the pits exceeded the examination screening criteria requiring further engineering evaluation nor recoating.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Additional VT-i examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-16 and 3-16. These additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a) of ASME Section XI, 1992 Edition, 1992 Addenda. Pitting was observed. However, none of the pits exceeded the examination screening cdteria requiring further engineering evaluation. Pits exceeding the examination screening critera for recoating were recoated. Areas of discoloration and tiger striping were observed throughout. Small areas of mechanical damage were observed. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-2. These examinations were not scheduled, but were performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss were observed near the bottom of the downcomers. Some tiger striping with discoloration and the beginning of pinpoint rusting were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-2. Tiger striping with uniform corrosion concentrated at the waterline and adjacent to the bracing were observed. Random pitting mostly within the tiger stdping was observed.

None of the pits exceeded the examination screening criteria requiring further engineering evaluation nor recoating.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-I examinations were conducted for Code credit in the submerged section, including attachment welds, of the referenced Torus Bay in accordance to ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Records numbered 1-2 and 3-2. Pitting was observed. However, none of the pits exceeded the examination screening criteria requiring further engineering evaluation. Pits exceeding the examination screening criteria for recoating were recoated. Areas of discoloration and tiger striping were observed throughout. Small areas of mechanical damage were observed. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-3. These examinations were not scheduled, but were performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

VT-1 examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-3. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 6 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Component ID Containment Section B34NT-SS Bay 3, Submerged Section Including Attachment Welds System: PC 0-2410 "B4-DWN-ID-SS Bay 4, Downcomer Submerged Section Interior Surface Class: MC System: PC MWR No. 00-2410 Report No.

Exam Procedure CNSO1-003 VT-.

01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS01-004 VT-i Performed By:

Underwater Construction C Results I Corrective Measures......

VT-i examinations were performed for Code credit in the submerged section, including attachment welds, of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Pitting was observed, primadly around the piping penetrations. Reference UCC Records numbered 1-3, 2-3, and 3-3. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation, none of the pits exceeded the NEDC 92-213, Revision 2 design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Therefore, no conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline.

Additional examinations of the remaining bays were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an alternative to IWE-2430(a). The remaining bays exhibited similar or lesser levels of degradation from pitting. Preservice VT-i examinations were performed on the recoated areas and found to be acceptable.

01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-4. These examinations were not scheduled, but were Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger strping with pinpoint rusting and general corrosion were observed. Near 100% coating loss on bottom 12" of downcomer. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11 B4-DWN-OD-SS Class: MC System: PC Bay 4, Downcomer Submerged Section Exterior Surface Including Attachment Welds MWR No. 00-2410 E4.11 B4-INT-SS Bay 4, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 CNSO1-004 V.-li 01634-3, Rev 1 Performed By:

Underwater Construction Corperation "CNS01-004 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation VT-1 examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-4. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

"VT-1i examinations were performed for Code credit in the submerged section, including attachment welds, of the referenced Torus Bay in accordance to ASME Section XI, 1992 Edition, 1992 Addenda. Pitting was observed, primarily around the piping penetrations. Reference UCC Records numbered 1-4, 2-4, 3-4. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation, none of the pits exceeded the NEDC 92-213, Revision 2 design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Therefore, no conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Also areas of tiger striping with pinpoint rusting, uniform corrosion near the waterline, and random areas of discoloration were observed. Small areas of mechanical damage near the invert weld seam were observed. Additional examinations of the remaining bays were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an alternative to IWE-2430(a). The remaining bays exhibited similar or lesser levels of degradation from pitting. Preservice VT-I examinations were performed on the recoated areas and found to be acceptable.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11 B6-DWN-ID-SS Class: MC System: Pc MWR No. 00-2410 Bay 5, Downcomer Submerged CNS01-005 VT-1 01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the Section Interior Surface downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section XI, 1992 Performed By:

Edition, 1992 Addenda. Reference UCC Record number 1-5. These examinations were not scheduled, but were Underwater Construction Corporation performed to provide information on surface conditions. Some isolated cells with slight metal loss was noted primarily near the bottom of the downcomer. Dense tiger striping over the bottom 12" of the downcomer with discoloration and near uniform pitting corrosion. None of the pitting was deep enough to require engineering evaluation or recoating.

These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Item No.

C E4.11 Class: MC MWR No. o0 E4.1 1

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Item No.

Component ID Containment Section E4.1 1 85-DWN-OD-SS BayS5, Downcomer Submerged Section Exterior Surface Class: MC System: PC Including Attachment Welds MWR No. 00-2410 E4.11 B5-INT-SS Bay 5, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 B6-DWN-ID-SS Bay 6, Downcomer Submerged Section Interior Surface Class: MC System: PC MWR No. 00-2410 Page 7 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Report No.

Exam Procedure Results IlCorrective Measures CNS01-005 VT-i 01634-3, Rev 1 VT-1 examinations were conducted forCode crediton the exteriorasurface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance toASME Section X, 1992 Edition, Performed By:

1992 Addenda. Reference UCC Record number 1-5. Tiger striping with uniform corrosion concentrated at the Underwater Construction Corperation waterline and adjacent to bracing was observed. Random pitting, mostly within the tiger stiping was observed. None of the pitting exceeded the threshold for recoating or further engineering evaluation. Some isolated corrosion cells with slight metal loss and discoloration over most of the downcomer was observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

cNS0i-005 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNSOI-006 VT-i Performed By:

Underwater Construction C VT-I examinations were conducted for Code credit in the submerged section, including attachment welds, of the referenced Torus Bay in accordance to ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Records numbered 1-5 and 3-5. Isolated to random areas of pitting corrosion, ranging from pinpoint rusting to uniform corrosion was observed. None of the pits exceeded the examination screening criteria requiring further engineering evaluation. Small areas of mechanical damage, especially near the invert weld seam were observed. Areas of discoloration were observed throughout and near the ring girders. At the waterlines, some tiger striping with pinpoint rusting with uniform corrosion were observed. At the ring girder adjacent to each gusset plate on the web of the girder, isolated areas of uniform rusting with 100% coating loss was discovered. Discoloration, pinpoint rusting and uniform corrosion concentrated at the invert weld seam. Random areas of discoloration and pinpoint rusting, with isolated pitting were found on the balance of the general shell. Near the ring girder regions, tiger striping was more prevalent and advanced, as was the pinpoint and uniform corrosion. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section XI, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-6. These examinations were not scheduled, but were Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed on the bottom 12" of the downcomer were observed with near 100% loss of coating. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11 B6-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Bay 6, Downcomer Submerged Section Exterior Surface Including Attachment Welds B6-INT-SS Bay 6, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 CNSO1-006 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS01-006 VT-I 01634-3, Rev 1 Performed By:

Underwater Construction Corporation V1T-1 examinationsowere conducted for-Code credit on-the eterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section X1, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-6. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Additional VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-6, 2-6, 3-6 and 4-6 (for the new test area). The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D) Section 50.55a(b)2(D) as an alternative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition.

Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline. No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-I examinations were performed on the recoated areas and found to be acceptable.

B7-DWN-ID-SS Bay 7, Downcomer Submerged Section Interior Surface Class: MC System: PC MWR No. 00-2410 CNS01-007 VT-i 01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section XI, 1992 Performed By:

Edition, 1992 Addenda. Reference UCC Record number 1-7. These examinations were not scheduled, but were Underwater Construction Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed on the bottom 12" of the downcomer. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11 E4.11 I..............................................

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 8 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component ID Containment Section E4.11 B7-DWN-OD-SS Bay 7,Downcomer Submerged Section Exterior Surface Class: Mc System: Pc Including Attachment Welds MWR No. 00-2410 E4.11 B7-INT-SS Bay 7, Submerged Section Including Attachment Welds Class: Mc System: Pc MWR No. 00-2410 Report No.

Exam Procedure CNSOI-007 VT-i 01634-3, Rev 1 Performed By:

Underwater Construction Corperation "CNSOi-007 VT-.

01634-3, Rev 1 Performed By:

Underwater Construction Corporation Results I Corrective Measures VT-I examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-7. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

"Additional VTr-i examinations were condcucted in the submerged section, including attach ment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-7, 2-7, and 3-7. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an altemative to IWE-2430(a).

Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline.

No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

98-DWN-ID-SS Bay 8, Downcomer Submerged Section Interior Surface Class: Mc System: PC MWR No. 00-2410 E4.11

.B8-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 Bay 8, Downcomer Submerged Section Exterior Surface Including Attachment Welds B8-INT-SS Bay 8, Submerged Section Including Attachment Welds Class: Mc System: PC MWR No. 00-2410 CNS01-008 VT-1 01634-3, Rev 1 VT-i examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Performed By:

Edition, 1992 Addenda. Reference UCC Record number 1-8. These examinations were not scheduled, but were Underwater Construction Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed on the bottom 12" of the downcomer. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

CNS01-008 VT-1 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNS01 -008 VTF-i 01 634-3, Rev 1 Performed By:

Underwater Construction Corporation VT-1 examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record number 1-8. Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping.

Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Additional VT-1 examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-8, 2-8, and 3-8. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR SIN 4-14626 documented this condition. Pit depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth. This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline.

No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-1 examinations were performed on the recoated areas and found to be acceptable.

B9-DWN-ID-SS Bay 9, Downcomer Submerged Section Interior Surface CNS01-009 VT-1 01634-3, Rev 1 VT-1 examinations were performed on the accessible interior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance with ASME Section Xl, 1992 Performed By:

Edition, 1992 Addenda. Reference UCC Record number 1-9. These examinations were not scheduled, but were Underwater Construction Corporation performed to provide information on surface conditions. Some isolated corrosion cells with slight metal loss near the bottom of the downcomers were observed. Heavy tiger striping with pinpoint rusting and general corrosion were observed on the bottom 12 of the downcomer. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

E4.11 E4.11 E4.11 Class: MC System: PC MWR No. 00-2410

NIS-1, Table 1.2, MCO-01-01: IWE Examinations during Mid-Cycle Outage Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98 Brownville, NE 68321 Plant Unit: 1 Page 9 of 9 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number: 20762 Item No.

Component ID E4.11 B9-DWN-OD-SS Class: MC System: PC MWR No. 00-2410 E4.11 Containment Section Bay 9, Downcomer Submerged Section Exterior Surface Including Attachment Welds B9-4NT-SS Bay 9, Submerged Section Including Attachment Welds Class: MC System: PC MWR No. 00-2410 E4.11 DW-SH-FLG-SS Drywell Shell Flange, Lower Flange in Cavity Class: MC System: Pc MWR No. 00-2887 Report No.

Exam Procedure CNS01-009 VT-1 01634-3, Rev 1 Performed By:

Underwater Construction Corperation CNSo1-009 VT-..

01634-3, Rev 1 Performed By:

Underwater Construction Corporation 00-2887 VTF-*

CNS 3.28.1.5 REV 1 Performed By:

NPPD Results Corrective Measures VT-i examinations were conducted for Code credit on the exterior surface areas, including attachment welds, of the downcomers in the submerged section of the referenced Torus Bay in accordance to ASME Section Xl, 1992 Edition, 1992 Addenda. Reference UCC Record numbers 1-9 and 5-9 (for the test area). Tiger striping with uniform corrosion concentrated a the waterline and adjacent to bracing was observed. Random pitting was observed primarily within the tiger striping. Some isolated corrosion cells with slight metal loss were observed. These conditions are noted but represent little or no degradation to the base metal and therefore are acceptable.

Additional VT-i examinations were conducted in the submerged section, including attachment welds, of the referenced Torus Bay as a result of indications discovered in Bays 1-5. Reference UCC Records numbered 1-9, 2-9, and 3-9. The additional examinations were performed in accordance with 10 CFR 50.55a Codes and Standards, (D)

Section 50.55a(b)2(D) as an alternative to IWE-2430(a). Pitting was observed, primarily around the piping penetrations. PIR S/N 4-14626 documented this condition. Pits depths exceeding pre-established examination criteria were evaluated by DED Civil Engineering and were recoated. Based on the Engineering Evaluation and calculation NEDC 92-213, Revision 2, none of the pits exceeded the design code allowable for maximum pit depth.

This is documented in NEDC 94-214, Revision 3, which also establishes the revised corrosion rate for the Torus shell. Some tiger striping and discoloration were noted throughout with pinpoint rusting and uniform corrosion near the waterline. No conditions were found which effect the structural integrity of the Torus beyond Code Allowable criteria under postulated accident conditions. Preservice VT-i examinations were performed on the recoated areas and found to be acceptable.

Exam SAT.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Commerical Service Date: July, 1974 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Owner Certificate of Authorization: N/A Plant Unit: 1 National Board Number for Unit: 20762 Item No. System Exam Location ID Discription Work Order Performed By Report No.

Exam Procedure B-N-1 Category Components Examined Equal:

4 B13 10 NB SUR-SPECHLD-1@30 Surveillance Specimen Holder 4160145 Westinghouse RE20 IVVI VT-3 IV-BWR-001 Rev:1 AISI:

Number 1 at 30 degrees Azimuth BWRVIP:

B13.10 NB SUR-SPECHLD-2@120 Surveillance Specimen Holder 4160145 Westinghouse RE20 IVl VT-3 IV-BWR-001 Rev:1 Number 2 at 120 degrees AISI:

Azimuth BWRVIP:

B13.10 NB SUR-SPECHLD-3@300 Surveillance Specimen Holder 4160145 Westinghouse RE20 IVl VT-3 IV-BWR-001 Rev:1 Number 3 at 300 degrees AISI:

Azimuth BWRVIP:

813.10 NB VES-INTER@0>180 RPV Interior Surfaces (One Half 4160145 Westinghouse RE20 IVl VT-3 IV-BWR-001 Rev:1 AISI:

RPV Wall Accessible Areas)

BWRVIP:

Page 1 of 35 Results Commments/Corrective Measures NRI See RE20 IVl Report, Section 3, Tab 8 for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 8 for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 9 for inspection results. Access limited to area above Shroud flange.

NIS-1, Table1.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 2 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Exam Location ID B13.30 NB SHRD-SUPLTWLD-H9@0>180 AISI:

BWRVIP:

B13.30 NB AISI: 11.

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13-40 NB AISh BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

SHRD-SUPLTWLD-H9@1 80>360

.15 CRGT-(06-35)

CRGT-(10-19)

CRGT-(10-35)

CRGT-(14-23)

CRGT-(14-31)

CRGT-(18-15)

CRGT-(22-23)

CRGT-(22-39) cRGT-(30-15)

Discription Core Shroud Support Assembley Integral we Reactor Vesses H9 WE to 180 degrees azimuti Core Shroud Support Assembley Integral we Reactor Vesses H9 Wg 180 to 360 degrees azi Control Rod Guide Tub Control Rod Guide Tul Control Rod Guide Tut "control Rod Guide Tul control Rod Guide Tut control Rod Guide Tu Control Rod Guide Tu Control Rod Guide Tu Control Rod Guide TU Item No. System be ibe be 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse RE20 IVl RE20 IVl RE20 IwI VT-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures Work Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVl VT-3 I=d to eld fron 0 th 4160145 Westinghouse RE20 IVVI VT-3

.ld to aeld fron imuth be 4160145 Westinghouse RE20 IVVI VT-3 be 4160145 Westinghouse RE20 IVl VT-3 be 4160145 Westinghouse RE20 IVVI VT-3 Te 4160145 Westinghouse RE20 Iw.I VT-3 be 4160145 Westinghouse RE20 IVl VT-3 be 4160145 Westinghouse RE20 IVl VT-3 B-N-2 Category Components Examined Equal:

31 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev 1 NRI See RE20 iWI Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NRI See RE20 IWI Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NRI See RE20 IWI Report, Section 3, Tab 10 for inspection results.

NRI See RE20 IV l Report, Section 3, Tab 10 for inspection results.

NRI See RE20 WIi Report, Section 3, Tab 10 for inspection results.

NRI See RE20 IWI Report, Section 3, Tab 10 for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 10 for inspection results. Debris found in bottom of tube and removed prior to reassembly.

Notifications 10128156 and 10128282 were written to document the condition. See ESD memo ESDO1 077 for disposition.

NRI See RE20 IWI Report, Section 3, Tab 10 for inspection results.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Exam Location ID Discription B13-40 NB CRGT-(34-15) control Rod Guide Tube AlSh:

BWRVIP:

B13.40 NB CRGT-(34-35)

Control Rod Guide Tube AISI:

BWRVIP:

B13.40 NB CRGT-(38-23)

Control Rod Guide Tube AISI:

BWRVIP:

B13.40 NB cRGT-(42-19)

Control Rod Guide Tube AISh BWRVIP:

813.40 NB OFSC-(06-35)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

B13.40 NB OFSc-(10.19)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

B13.40 NB OFSC-(10-35)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

613.40 NB OFSC-(14-23)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

B13.40 NB oFSc-(14-31)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

B13-40 NB OFSC-(18-15)

Four Lobed Orificed Fuel AlSh:

Support Casting Assembly BWRVIP:

813.40 NB OFSC-(22-23)

Four Lobed Orificed Fuel AISI:

Support Casting Assembly BWRVIP:

Page 3 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

Exam Procedure 4160145 Westinghouse RE20 IVl VT-3 IV-BWR-001 Rev:l 4160145 Westinghouse RE20 Iwi VT-3 IV-BWR-001 Rev:i 4160145 Westinghouse RE20 IVl VT-3 IV-BWR-001 Rev:l 4160145 Westinghouse RE20 IVVI Vr-3 IV-BWR-001 Rev:l 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IWI RE20 IWI RE20 IWI RE20 WIi RE20 IWI RE20 IWI RE20 IWI VT-3 VT-3 vr-3 VT-3 VT-3 VT-3 VT-3 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:1 IV-BWR-001 Rev:1 IV-BWR-001 Revwl IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI See RE2O IWI Report, Section 3, Tab 10 for NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI inspection results.

See RE20 IVVI Report, Section 3, Tab 10 for inspection results.

See RE20 IWI Report, Section 3, Tab 10 for inspection results. Debris found in bottom of tube and removed prior to reassembly.

Notifications 10128156 and 10128282 were written to document the condition. See ESD memo ESDO1077 for disposition.

See RE20 IWI Report, Section 3, Tab 6 for inspection results.

See RE20 IVl Report, Section 3, Tab 6 for inspection results.

See RE20 IWI Report, Section 3, Tab 6 for inspection results.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 4 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 813.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP:

B13.40 NB AISI:

BWRVIP: 25 B13.40 NB AISI:

BWRVIP: 38 B13.40 NB AISI:

BWRVIP: 38 Exam Location ID OFSC-(22-39)

OFSC-(30-15)

OFSC-(34-15)

OFSC-(34-35)

OFSC-(38-23)

OFSC-(42-19)

Core Plate SHRD-SuPASEM@0>180 SHRD-SUPASEM@180>360 Discription Wc Four Lobed Orificed Fuel Support Casting Assembly Four Lobed Orificed Fuel Support Casting Assembly Four Lobed Orificed Fuel Support Casting Assembly Four Lobed Orificed Fuel Support Casting Assembly Four Lobed Orificed Fuel Support Casting Assembly Four Lobed Orificed Fuel Support Casting Assembly Core Plate Assembly Core Shroud Support Assembley, Lower Cylinder and Suppo'rt Plate, from the H7 Weld and H8 Weld areas to the H9 Weld area 0 to 180 degress azimuth Core Shroud Support Assembley, Lower Cylinder and Support Plate, from the H7 Weld and H8 Weld areas to the H9 Weld area 180 to 360 degree azimuth ork Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVl VT-3 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVl RE20 IWI RE20 iWI RE20 WI RE20 IWI RE20 IVVI VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Procedure Results CommmentslCorrective Measures IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Revil IV-BWR-001 Rev.i IV-BWR-001 Rev:l IV-BWR-001 Revw1 IV-BWR-001 Rev:l 4160145 Westinghouse RE20 IWI VT-3 IV-BWR-001 Rev:l 4160145 Westinghouse RE20 IVVI VT-3 IV-BWR-001 Rev:l NRI See RE20 IVVl Report, Section 3, Tab 6 for inspection results.

NRI See RE20 IWI Report, Section 3, Tab 6 for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 6 for inspection results.

NRI See RE20 IWI Report, Section 3, Tab 6 for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 10 for inspection results. Examination were performed in area of Fuel Cells removed at locations 22 23, 30-15, 22-39, 34-15, 14-31, 18-15, 38-23, 06-35, 14-23, 10-19, 10-35, 34-15, and 42-19.

NRI See RE20 IWI Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NRI See RE20 IVl Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 5 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Exam Location ID Discription Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures XMA-VIP18 Category Components Examined Equal:

61 IVI NBCS AISI: 11.8 BWRVIP: 18 IVi NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.8 BWRVIP: 18 IVI NBCS AISI: 11.8 BWRVIP: 18 IVI NBCS AISI: 11.8 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 CS-A-TJB@90-(PI)

CS-Ali@170-(P8b)

CS-AlO@90-(P3)

CS-All@90-(P2)

CS-Al2@90-(P3)

CS-AI5@10-(PS)

CS-Al6@l0-(P6)

CS-A17@10-(P7)

CS-A2@170-(P8a)

CS-A20@I0-(P8a)

Core Spray Piping Tee Junction 4160145 Box at 90 degrees azimuth, Thermal Sleeve to Junction Box Weld (hidden)

Core Spray Piping Downcomer 4160144 "C" at 170 degrees azimuth, Collar to Shroud Weld Core Spray Piping Tee Junction 4160144 Box at 90 degrees azimuth, Horizontal Pipe to Junction Box Weld, from Downcomer "C" Core Spray Piping Tee Junction 4160145 Box at 90 degrees azimuth, Cover Plate to Junction Box Weld Core Spray Piping Tee Junction 4160144 Box at 90 degrese azimuth, Horizontal Pipe to Junction Box Weld, to Downcomer "A" Core Spray Piping, Sliding 4160144 Sleeve to Upper Downcomer "A" at 10 degrees azimuth Core Spray Piping, Sliding 4160144 Sleeve Weld to Outer Sleeve, off Downcomer "A" at 10 degrees azimuth Core Spray Piping, Outer Sleeve 4160144 to Lower Downcomer "A" at 10 degrees azimuth Core Spray Piping Downcomer 4160144 "C" at 170 degrees azimuth, Collar to Shroud Pipe Weld Core Spray Piping Downcomer 4160144 "A" at 10 degrees azimuth, Collar to Shroud Pipe Weld Westinghouse RE20 Iwi Westinghouse Westinghouse NA CSP-ISI-100 Rev 5C1 IV-BWR-001 Rev:l EDS#-I UT-65S CSP-ISI-100 Rev 5CI EV-1I IV-BWR-001 Rev:l EDS#-9 UT-65S CSP-ISl-100 Rev 5c1 EVT-1 IV-BWR-001 Rev:l Westinghouse RE20 IWI EV-F-1 Westinghouse IV-BWR-001 Rev:l EDS#-10 UT-65S CSP-ISI-100 Rev 5CI EVT-1 IV-BWR-001 Rev:l Westinghouse EDS#-I11 UT-65S CSP-ISI-100 Rev 5CI Westinghouse EDS#-12 UT-65S CSP-ISI-100 Rev 5CI EV-1-I IV-BWR-001 Rev:l Westinghouse Westinghouse Westinghouse EDS#-13 UT-65S CSP-ISI-100 Rev 5C1 EVF-1 IV-BWR-001 Rev:l EDS#-2 UT-65S CSP-ISI-100 Rev 5C1 EDS#-14 UT-65S CSP-ISI-100 Rev 6C1 NA Weld is inaccessible, no examination performed.

RI indication documented in notification 10127742.

RI Accepted by Engineering Evaluation per NEDC 98-054. 360 degree coverage on upstream side only due to configuration. Visual exam performed per WO 4160145.

RI Spot of lack of fusion at midwall detected by NRI UT. Visual performed per WO 4160145 with approximately 65% coverage.

NRI NRI Performed UT scan from 268 through 0 to 10 NRI degrees and 148 to 250 on the downstream side only due to the configuration. Visual exam performed under WO 4160145 with approximately 65% coverage.

NRI Scanned 360 degrees on both sides. Weld geometry seen.

NRI Performed UT scans of 360 degrees on both NRI sides. Comer geometry seen. Visual exam performed per WO 4160145 with approximately 65% coverage.

NRI Scanned 360 degrees on downstream side.

NRI Scanned 60 to 330 degrees on the upstream side due to configuration. Weld geometry seen Visual exam performed per WO 4160145 with approximately 65% coverage.

NRI Scanned 360 degrees on downstream side only due to configuration.

NRI Scanned 360 degrees on downstream side only due to configuration. OD geometry seen.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 6 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID cS-A21@10-(Pab)

CS-A22@10-(P9)

CS-A23@170-(P9)

CS-A3@170-(P4d)

CS-A4@170-(P4c)

CS-A5@170-(P7)

CS-A6@170-(P6)

CS-A7@170-(P5)

Discription Work Order Performed By Core Spray Piping Downcomer 4160144 Westinghouse "A" at 10 degrees azimuth, Collar to Shroud Weld Core Spray Shroud Pipe to Sparger Tee Box (hidden weld)

Upper Sparger Downcomer "A" at 10 degrees azimuth Core Spray Shroud Pipe to Sparger Tee Box (hidden weld)

Upper Sparger Downcomer "C" at 170 degrees azimuth 4160144 Westinghouse 4160144 Westinghouse Core Spray Piping, Elbow to 4160145 Shroud Pipe, off Downcomer "C" at 170 degrees azimuth Core Spray Piping, Lower 4160144 Downcomer "C" to Elbow at 170 degrees azimuth Core Spray Piping, Outer Sleeve 4160144 to Lower Downcomer "C" at 170 degrees azimuth Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "C" at 170 degrees azimuth Core Spray Piping, Sliding Sleeve to Upper Downcomer "C" at 170 degrees azimuth Report No.

Exam EDS#-15 UT-65S Procedure Results Commments/Corrective Measures CSP-ISl-100 Rev 5C1 RI 360 degree coverage on upstream side only due to configuration. This is a re-examination from the last several outages. Change in length is insignificant and within the accuracy of the equipment. Indication has been previously evaluated and accepted per Engineering evaluation documented in NEDC98-054. Weld geometry also observed.

EDS#-28 uT-45S CSP-ISI-1.00 Rev 5C1 EDS#-29 UT-45S CSP-ISI-100 Rev 5C1 Westinghouse RE20 IVVI EVT-1 IV-BWR-001 Rev:l Westinghouse EDS#-3 UT-65S CSP-ISI-100 Rev 5CI Westinghouse 4160144 Westinghouse EDS#-4 UT-65S CSP-ISI-1 00 Rev 5C1 EVT-1 IV-BWR-001 Rev:l EDS#-5 uT-65S CSP-ISI-1i00 Rev 5C1 4160144 Westinghouse EDS#-6 UT-65S CSP-ISI-100 Rev 5C1 RI1 Scanned 360 degrees on upstream side only due to configuration limitations. No recordable weld crown and associated geometry of weld seen intermittently. Recordabel indications which are similar to the flaws seen in the EPRI P9 sample blocks, but due to the complexity of this examination technique, flaw characterization is not feasible. Notification 10128653 was written to document indication.

Per NEDC 98-054, Revision 4 this weld is not credited for structural integrity.

NRI Scanned 360 degrees on upstream side only due to configuration limitations. No recordable weld crown and associated geometry of weld seen intermittently.

NRI Limited to approximately 95% coverage.

NRI Scanned 360 degrees on upstream side only due to configuration.

NRI Scanned 360 degrees on both sides. Visual NRI exam performed per WO 4160145. Visual exam limited to approximately 65% coverage.

NRI Scanned 360 degrees on both sides.

NRI Scanned 360 degrees on both sides. Weld geometry seen.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 7 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.8 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.8 BWRVIP: 18 Ivi NBCS AISI: 11.8 BWRVIP: 18 IVI NBCS AISI: 11.8 BWRVIP: 18 ivi NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID CS-A8@170-(P4b)

CS-A9@170-(P4a)

CS-B-TJB@270-(PI)

CS-BI@350-(P8b)

CS-BIO@270-(P3)

CS-B11@270-(P2)

CS-B12@270-(P3)

CS-Bl5@190-(P5)

CS-Bl6@190-(P6)

CS-Bl7@190-(P7)

Discription Core Spray Piping, Elbow to Pipe Downcomer "C" at 170 degrees azimuth Core Spray Piping, Horizontal 4160144 Pipe to Elbow, off Downcomer "C" at 170 degrees azimuth core Spray Piping Tee Junction 4160145 Box at 270 degrees azimuth, Thermal Sleeve to Junction Box Weld (hidden)

Core Spray Piping Downcomer 4160144 "B" at 350 degrees azimuth, Collar to Shroud Weld Core Spray Piping Tee Junction 4160144 Box at 270 degrees azimuth, Horizontal Pipe to Junction Box Weld, from Downcomer "B" Core Spray Piping Tee Junction 4160145 Box at 270 degrees azimuth, Cover Plate to Junction Box Weld Core Spray Piping Tee Junction 4160144 Box at 270 degrees azimuth, Horizontal Pipe to Junction Box Weld, to Downcomer "D" "Core Spray Piping, Sliding 4160144 Sleeve to upper Downcomer "D" at 190 degrees azimuth Core Spray Piping, Sliding 4160144 Sleeve Weld to Outer Sleeve, off Downcomer "D" at 190 degrees azimuth Core Spray Piping, Outer Sleeve 4160144 to Lower Downcomer "D" at 190 degrees azimuth Work Order Performed By Report No.

Exam 4160144 Westinghouse EDS#-7 UT-65S EVT-1 Westinghouse Procedure Results Commments/Corrective Measures CSP-ISI-1oo Rev 5CI IV-BWR-001 Rev:l EDS#-8 UT-65S CSP-ISI-1 00 Rev 5C1 Westinghouse RE20 IV l Westinghouse Westinghouse NA IV-BWR-001 Rev:l EDS#-16 UT-65S CSP-ISI-100 Rev 5CI EDS#-21 UT-65S CSP-ISI-100 Rev 5C1 EVT-1 IV-BWR-001 Rev:l Westinghouse RE20 Il E/VT-1 Westinghouse IV-BWR-001 Rev:l EDS#-22 UT-65S CSP-ISI-100 Rev 5C1 EVT-1 IV-BWR-001 Rev:l "Westinghouse EDS#-23 UT-65S CSP-ISI-100 Rev 5Ci Westinghouse EDS#-24 UT-65S CSP-ISI-100 Rev 5CI Westinghouse EDS#-25 UT-65S CSP-ISI-100 Rev 5C I EVT-1 IV-BWR-001 Rev:l NRI Performed a UT scan from 322 through 0 to 74 RI degrees and 142 to 254 on the downstream side only due to the configuration-Visual exam performed per WO 4160145 with coverage limited to 70%. Surface indication noted by visual exam however could not be substantiated by UT so exam considered SAT.

NRI Scanned from 345 through 0 to 224 degrees on the upstream side only due to the configuration.

NA Weld inaccessible for examination.

NRI Scanned 360 degrees on the upstream side due to configuration limitations. Weld geometry seen.

NRI Performed a uT scan from 350 to 94 degrees NRI and 110 to 214 on the downstream side only due to the configuration. Visual exam performed per WO 4160145 with approximately 55%

coverage.

NRI NRI Performed a UT scan from 264 through 0 to 10 NRI degrees and 144 to 250 on the downstream side due to configuration limitations. Visual exam performed per WO 4160145 with approximately 55% coverage.

NRI Scanned 360 degrees on both sides. Weld geometry seen.

NRI Scanned 360 degrees on upstream side.

Scanned 10 to 323 degrees on the downstream side due to configuration limitations. Corner geometry seen.

NRI Performed a UT scan of 360 degrees on NRI downstream side. Scanned 10 to 323 degrees on the upstream side due to configuration limitations. Weld geometry seen. Visual exam performed per WO 4160145 with approximately 65% coverage.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 8 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NBCS AISh 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISh 11.2 BWRVIP: 18 IVi NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID CS-B2@350-(P8a)

CS-B20@190-(P8a)

CS-B21@190-(P8b) cS-B22@190-(P9)

CS-B23@350-(P9)

CS-B5@350-(P7)

CS-B6@350-(P6)

CS-B7@350-(P5)

Discription Work Order Performed By Report No.

Exam Core Spray Piping Downcomer 4160144 Westinghouse EDS#-17 UT-65S "B" at 350 degrees azimuth, Collar to Shroud Pipe Weld Core Spray Piping Downcomer 4160144 "D" at 190 degrees azimuth, Collar to Shroud Weld Core Spray Piping Downcomer "D" at 190 degrees azimuth, Collar to Shroud Pipe Weld Core Spray Shroud Pipe to Sparger Tee Box (hidden weld)

Lower Sparger Downcomer "D" at 190 degrees azimuth Core Spray Shroud Pipe to Sparger Tee Box (hidden weld)

Lower Sparger Downcomer "B" at 350 degrees azimuth Westinghouse 4160144 Westinghouse Procedure Results Commments/Corrective Measures CSP-ISI-100 Rev 5C1 EDS#-26 UT-65S CSP-ISI-100 Rev 5C1 EVT-1 IV-BWR-001 Rev:l EDS#-27 UT-65S CSP-ISI-1 00 Rev 5Cl 4160144 Westinghouse EDS#-30 UT-45S CSP-ISI-100 Rev 5C1 4160144 Westinghouse Core Spray Piping, Outer Sleeve 4160144 Westinghouse to Lower Downcomer "B" at 350 degrees azimuth Core Spray Piping, Sliding Sleeve Weld to Outer Sleeve, off Downcomer "B" at 350 degrees azimuth Core Spray Piping, Sliding Sleeve to Upper Downcomer "B" at 350 degrees azimuth 4160144 Westinghouse 4160144 Westinghouse EDS#-31 UT-45S CSP-ISI-100 Rev 5C1 EDS#-18 uT-65S CSP-ISI-100 Rev 5Cl EVT-1 IV-BWR-001 Rev:l EDS#-19 UT-65S CSP-ISI-100 Rev 5C1 EDS#-20 UT-65S CSP-ISI-100 Rev 5C1 NRI Scanned 360 degrees on downstream side due to configuration limitations. OD corner geometry seen.

RI Indication documented in notification 10131163.

NRI Accepted by Engineering Evaluation per NEDC 98-054. 360 degree coverage on downstream side due to configuration. Visual exam performed per WO 4160145.

NRI 360 degree coverage on upstream side only due to configuration limitations. Weld geometry seen.

RI Scanned 360 degrees on upstream side only due to configuration limitations. No recordable weld crown and associated geometry of weld seen intermittently. Recordabel indications which are similar to the flaws seen in the EPRI P9 sample blocks, but due to the complexity of this examination technique, flaw characterization is not feasible. Notification 10128653 was written to document indication.

Per NEDC 98-054, Revision 4 this weld is not credited for structural integrity.

RI Scanned 360 degrees on upstream side only due to configuration limitations. No recordable weld crown and associated geometry of weld seen intermittently. Recordabel indications which are similar to the flaws seen in the EPRI P9 sample blocks, but due to the complexity of this examination technique, flaw characterization is not feasible. Notification 10128653 was written to document indication.

Per NEDC 98-054, Revision 4 this weld is not credited for structural integrity.

NRI Scanned from 20 to 315 degrees on the NRI upstream side due to configuration limitations.

Scanned 360 degrees on the downstream side.

Weld geometry seen. Visual exam performed per WO 4160145 with approximately 65%

coverage.

NRI Scanned from 20 to 315 degrees on the downstream side due to configuration limitations. Scanned 360 degrees on the upstream side. Weld geometry seen.

NRI Scanned 360 degrees on both sides. Weld geometry seen.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 9 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NBCS AISI: 11.2 BWRVIP: 18 IVi NBCS AISI: 11.2 BWRVIP: 18 IV]

NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 lvi NBCS AISI: 11.2 BWRVIP: 18 IVi NBCS AISI: 11.2 BWRVIP: 18 ivi NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID S-BL-XTRW@346 S-BL-XTRW@354 SI-AU-TB@10 Sl-BL-TB@350 SI-CU-TB@170 Sl-DL-TB@190 S2@12-AU-TB@10 S2@168-CU-TB@170 S2@172-CU-TB@170 S2@188-DL-TB@190 S2@192-DL-TB@190 Discription W(

Core Spray Sparger "B" Lower, Sparger Pipe to Sparger Pipe, Extra Weld at 346 degrees azimuth Core Spray Sparger "B" Lower, Sparger Pipe to Sparger Pipe, Extra Weld at 354 degrees azimuth Core Spray Sparger "A" Upper Tee Box at 10 degrees azimuth, Cover Plate to Sparger Tee Box Weld Core Spray Sparger "B" Lower Tee Box at 350 degrees azimuth, Cover Plate to Sparger Tee Box Weld Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Cover Plate to Sparger Tee Box Weld Core Spray Sparger "D" Lower Tee Box at 190 degrees azimuth, Cover Plate to Sparger Tee Box Weld Core Spray Sparger "A" Upper Tee Box at 10 degrees azimuth, Sparger Pipe to Tee Box Weld at 12 degrees azimuth Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Sparger Pipe to Tee Box Weld at 168 degrees azimuth Core Spray Sparger "C" Upper Tee Box at 170 degrees azimuth, Sparger Pipe to Tee Box Weld at 172 degrees azimuth Core Spray Sparger "D" Lower Tee Box at 190 degrees azimuth, Sparger Pipe to Tee Box Weld at 188 degrees azimuth Core Spray Sparger "D" Lower Tee Box at 190 degrees azimuth, Sparger Pipe to Tee Box Weld at 192 degrees azimuth ork Order Performed By Report No.

4160145 Westinghouse RE20 IVVI 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse RE20 IWI RE20 IWI RE20 IVl RE2O WIw RE20 IVl RE20 IVl RE20 iwI Exam Procedure Results CommmentslCorrective Measures EVT-1 IV-BWR-001 Rev:l EVT-1 EVT-1 EVT-1 EVT-i EVT-1 EVT-1 EVr-1 RE20 Il EVT-1 RE20 Il EVT-1 RE20 IVl EVT-1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev 1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Revwl IV-BWR-001 Rev:l NRI See RE20 IVl Report Section 3 Tab 2 NRI NRI NRI NRI NRI NRI NRI See RE20 IVl Report Section 3 Tab 2 NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 10 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IV[

NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID S2@348-BL-TB@350 S2@352-BL-TB@350 S2@8-AU-TB@10 S3a-CU-NSPW@92>269 IVI NBCS S3b-CU-NOW@92>269 AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 IVI NBCS AISI: 11.2 BWRVIP: 18 VI NBCS AISI: 11-2 BWRVIP: 18 IVI NBCS AISh 11.2 BWRVIP: 18 S3c-DL-DRSPW@261 S4-AU-ECSPW@271 S4-AU-ECSPW@89 S4-BL-ECSPW@271 S4-BL-ECSPW@89 Discription Core Spray Sparger "B" Lower Tee Box at 350 degrees azimuth, Sparger Pipe to Tee Box Weld at 348 degrees azimuth Work Order Performed By F 4160145 Westinghouse Core Spray Sparger "B" Lower 4160145 Tee Box at 350 degrees azimuth, Sparger Pipe to Tee Box Weld at 352 degrees azimuth Core Spray Sparger "A" upper 4160145 Tee Box at 10 degrees azimuth, Sparger Pipe to Tee Box Weld at 8 degrees azimuth Core Spray Sparger "C" Upper, 4160145 Nozzle to Sparger Pipe Welds, all spray nozzles from 92 to 269 degrees azimuth Core Spray Sparger "C" Upper, Nozzle to Orifice Welds, all spray nozzles from 92 to 269 degrees azimuth 4160145 Core Spray Sparger"D" Lower, 4160145 Drain to Sparger PipeWeld at 81 degrees azimuth, Includes Tack Weld on Drain Plug Core Spray Sparger "A" Upper, 4160145 End Cap to Sparger Pipe Weld at 271 degrees azimuth Assumed to be creviced internally Core Spray Sparger"A" Upper, 4160145 End Cap to Sparger Pipe Weld at 89 degrees azimuth Assumed to be creviced internally Core Spray Sparger "B" Lower, 4160145 End Cap to Sparger Pipe Weld at 271 degrees azimuth Assumed to be creviced internally Core Spray Sparger"B" Lower, 4160145 End Cap to Sparger Pipe Weld at 89 degrees azimuth Assumed to be creviced internally Report No.

Exam Procedure Results Commments/Corrective Measures RE20 IWI EVT-1 IV-BWR-001 Rev:1 NRI Westinghouse RE20 IVVI Westinghouse RE20 IWI Westinghouse RE20 IVVI Westinghouse RE20 IVVI Westinghouse Westinghouse EVT-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l EVF-1 IV-BWR-001 Rev:l RE20 WI EVT-1 IV-BWR-001 Rev:l RE20 IWl EVT-1 IV-BWR-001 Rev:l Westinghouse RE20 IVl Westinghouse RE20 IVl Westinghouse RE20 IVl EVT-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l NRI NRI RI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 11 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System lVI NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 IVi NBCS AISI: 11.2 BWRVIP: 18 Ivi NBCS AISI: 11.2 BWRVIP: 18 Exam Location ID S4-CU.ECSPW@269 S4-CU-ECSPW@91 S4-DL-ECSPW@269 S4-DL-ECSPW@91 Discription Work Order Performed By Core Spray Sparger'"C" Upper, 4160145 Westinghouse End Cap to Sparger Pipe Weld at 269 degrees azimuth Assumed to be creviced internally Core Spray Sparger "C" upper, 4160145 Westinghouse End Cap to Sparger Pipe Weld at 93 degrees azimuth Assumed to be creviced internally Core Spray Sparger"D" Lower, 4160145 Westinghouse End Cap to Sparger Pipe Weld at 269 degrees azimuth Assumed to be creviced internally Core Spray Sparger"D" Lower, 4160145 Westinghouse End Cap to Sparger Pipe Weld at 91 degrees azimuth Assumed to be creviced internally Report No.

Exam RE20 IWl EV--1 RE20 IWI EVT-1 Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l RE20 IVl EVT-1 IV-BWR-001 Rev:l RE20 IVVI EVT-1 IV-BWR-001 Rev:l NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 12 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Exam Location ID Discription XMA-VIP26 Category Components Examined Equal:

16 IVI NB TG-HLDWN-ASEM@O AISI:

BWRVIP: 26 IVI NB TG-HLDWN-ASEM@180 AISI:

BWRVIP: 26 MVI NB TG-HLDWN-ASEM@270 AISI:

BWRVIP: 26 IVi NB TG-HLDWN-ASEM@90 AISI:

BWRVIP: 26 IVi NB TG-HOZALNPIN-ASEM@0 AISI:

BWRVIP: 26 IVI NB TG-HOZALNPIN-ASEM@180 AISI:

BWRVIP: 26 IVI NB TG-HOZALNPIN-ASEM@270 AISI:

BWRVIP: 26 IV[

NB TG-HOZALNPIN-ASEM@90 AISI:

BWRVIP: 26 IVI NB TG-RIMWLD>290>300 AISI:

BWRVIP: 26 IV[

NB TG.RIMWLD@110>120 AISI:

BWRVIP: 26 Vi NB TG-RIMWLD@140>150 AISh BWRVIP: 26 Work Order Performed By Report No.

4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IlVi RE20 IWI Exam VT-1 VT-1 RE20 IVVI VT-i RE20OIWi VT-i RE20 IVVI VT-1 RE20 Il VT-i RE20 IVVi VT-1 RE20 IVVI EVT-1 RE20 Il EVT-1 RE20 Il EVT-1 Procedure Results Commments/Corrective Measures IV-BWR-001 Revw1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l iV-BWR-001 Rev:l iV-BWR-001 Rev 1 IV-BWR-001 Rev:1 IV-BWR-001 Rev l iV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI F

F

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Exam Location ID Discription Mvi NB TG-RIMWLD@20>30 AISI:

BWRVIP: 26 IVI NB TG-RIMWLD@200>210 AISI:

BWRVIP: 26 IVI N1B TG-RIMWLD@230>240 AISI:

BWRVIP: 26 IV]

NB TG-RIMWLD@320>330 AISI:

BWRVIP: 26 ivi NB TG-RIMWLD@50-60 AISI:

BWRVIP: 26 Page 13 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

Exam Procedure 4160145 Westinghouse RE20 IWi EVT-1 IV-BWR-001 Rev:l 4160145 Westinghouse RE20 IVVi EVT-1 IV-BWR-001 Revwl 4160145 Westinghouse RE20 IVVi EVT-1 IV-BWR-001 Rev:1 4160145 westinghouse RE20 iVVi EVT-1 IV-BWR-001 Rev:1 4160145 Westinghouse RE20 IVVIl EV--1 IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 14 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Exam Location ID Discription Work-Order Performed By Report No.-

Exam Procedure Results CommmentslCorrective Measures XMA-VIP38 Category Components Examined Equal:

8 IV[

NB GW@1 35 Shroud Support Plate Gusset Al~l:11.26Weld at 135 Degree Azimuth BWRVIP: 38 IVI NB GW@15 Shroud Support Plate Gusset AISI:11.26Weld at 15 Degree Azimuth BWRVIP: 38 IV]

NB GW@165 Shroud Support Plate Gusset AISI:11.26Weld at 165 Degree Azimuth BWRVIP: 38 IV[

NB GWl@195 Shroud Support Plate Gusset AISI:11.26Weld at 195 Degree Azimuth BWRVIP: 38 IVI NB GW@315 Shroud Support Plate Gusset AISI:11.26Weld at 315 Degree Azimuth BWRVIP: 38 IVI NB GW@45 Shroud Support Plate Gusset AISI:11.26Weld at 45 Degree Azimuth BWRVIP: 38 lvi NB SHRD-SUPLTWLD-H8 Core Shroud Horizontal AISI:11.15Circumferential Weld including AISI:11.15intersections of vertical seam BWRVIP: 38 welds IVI NB SHRD-SUPLTWLD-H9 Core Shroud Horizontal AISI:11.15Circumferential Weld including AISI:1115intersections of vertical seam BWRVIP: 38 welds 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 WIVV EVr-1 V1-1 RE20 WIV RE20 WIV EVT-1 RE20 IWVI EVT-1 RE20 IVVI EVT-1 RE20 IWVI EVT-1 RE20 IWVI EVT-1 RE20 IWVI EVT-1 IV-BWR-001 Rev 1 IV-BWR-001 Rev.1 IV-BWR-001 Rev:l IV-BWR-001 Rev.1 IV-BWR-001 Rev:1 IV-BWR-001 Rev:1 IV-BWR-001 Rev 1 IV-BWR-001 Rev:1 NRI NRI NRI NRI N RI NRI NRI NRI See RE20 IVVI Report Section 3, Tab 7 for inspection results.

See RE20O WI Report Section 3, Tab 7 for inspection results.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Exam Location ID Discription XMA-VIP41 Category Components Examined Equal:

157 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 AD-1-JP1 AD-I-JP10 AD-1-JP2 AD-I-JP3 AD-1-JP4 AD-I-JP5 AD-I-JP6 AD-I-JP7 AD-1-JP8 AD-I-JP9 AD-2-JP1 Jet Pump Adapter Top to Adapter Bottom Weld (Bi metallic weld)

Jet Pump Adapter Top to Adapter Bottom Weld (Bi metallic weld)

Jet Pump Adapter Bottom to Core Shroud Support Plate Page 15 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

4160145 Westinghouse RE20 Iwi 4160145 Westinghouse RE20 IVVI 4160145 Westinghouse RE20IVVI 4160145 Westinghouse RE20 IWI 4160145 Westinghouse RE20 IVl 4160145 Westinghouse RE20-IVWI 4160145 Westinghouse RE20 Ivvi 4160145 Westinghouse RE20 IVl 4160145 Westinghouse RE20 Iwi 4160145 Westinghouse RE20 IVVI 4160145 Westinghouse RE20 IWI Exam EV'-1 EV'-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l Procedure Results Commments/Corrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System MVI NB AISI: 11.3 BWRVIP: 41 MVI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISh 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Vi NB AISI: 11.3 BWRVIP: 41 ivi NB AISI: 11.3 BWRVIP: 41 MI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Exam Location ID AD-2-JPIO AD-2-JP2 AD-2-JP3 AD-2-JP4 AD-2-JP5 AD-2-JP6 AD-2-JP7 AD-2-JP8 AD-2-JP9 AD-3a-JP1 AD-3a-JP10 Discription VY Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to Core Shroud Support Plate Jet Pump Adapter Bottom to core Shroud Support Plate Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface lork Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVVI EVT-1 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVl RE20 IWI RE2 0wI RE20 IVl RE20 IwI RE20 IVl RE20 Iwi RE20 WIw RE20 IVl RE20 IVl EVT-1 EVT-1 EVF-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l iV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BwR-001 Rev:1 IV-BwR-001 Rev:l IV-BWR-001 Rev:l NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Exam Limited to 40% Due to Configuration Exam Limited to 40% Due to Configuration Exam Limited to 40% Due to Configuration Exam Limited to 40% Due to Configuration Page 16 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 17 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System VI NNB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 IVl NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 Exam Location ID AD-3a-JP2 AD-3a-JP3 AD-3a-JP4 AD-3a-JP5 AD-3a-JP6 AD-3a-JP7 AD-3a-JP8 AD-3a-JP9 AD-3b-JPI AD-3b-JP10 AD-3b-JP2 Discription Work Orde Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface r Performed By F Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Report No.

Exam RE20 IWI EV'-I RE20 IVVI EVT-1 RE20 IWI EVT-1 RE20 IVVI EVT-1 RE20 IWI EVT-1 RE20 IVVI EVT-1 RE20 IVVI EVT-1 RE20 iWI EVT-1 RE20 IWI EVT-1 RE20 IWI EVT-1 Westinghouse RE20 IVVI Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:1 NRI Exam Limited to 40% Due to configuration IV-BWR-001 Revwl NRI Exam Limited to 40% Due to Configuration IV-BWR-001 Rev:1 NRI Exam Limited to 40% Dur to Configuration IV-BWR-001 Rev:1 NRI Exam Limited to 40% Durto Configuration IV-BWR-001 Rev:1 NRI Exam Limited to 40% Dur to Configuration IV-BWR-001 Rev:l NRI Exam Limited to 40% Due to Configuration IV-BWR-001 Rev:1 NRI Exam Limited to 40% Due to Configuration IV-BWR-001 Rev:1 NRI Exam Limited to 40% Due to Configuration IV-BWR-001 Rev:1 N/A Not Accessible IV-BWR-001 Rev:1 N/A NotAccessible EV-r-1 IV-BWR-001 Rev:l N/A Not Accessible

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 18 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 ivi NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11-3 BWRVIP: 41 Exam Location ID AD-3b-JP3 AD-3b-JP4 AD-3b-JP5 AD-3b-JP6 AD-3b-JP7 AD-3b-JP8 AD-3b-JP9 BB-1-JPI&JP2 BB-1-JP3&JP4 BB-1-JP5&JP6 BB-1-JP7&JP8 Discription Work Order Performed By Report No.

Jet Pump Adapter Backing Ring 4160145 Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Adapter Backing Ring Fillet Welds at the Diffuser Tailpipe-to-Adapter Interface Jet Pump Beam Bolt Hole Region Jet Pump Beam Bolt Hole Region Jet Pump Beam Bolt Hole Region Jet Pump Beam Bolt Hole Region 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse RE20 IVl Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVl RE20 IVVI RE20 IWI RE20 IWI RE20 lWI RE20 IVl RE20 IVl RE20 IVl RE20 IVl Exam EVT-1 EvT-I EVT-1 EVT-1 EV--1 EVT-1 EVT-1 EVT-1 EVT-i EVT-1 IV-BWR-001 Rev:l iV-BWR-001 Rev:1 IV-BWR-001 Rev:1 IV-BWR-001 Rev:1 Iv-BWR-001 Rev:i IV-BWR-001 Rev:1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l 4160145 Westinghouse RE20 IWI EVT-1 IV-BWR-001 Rev:l Procedure Results Commments/Corrective Measures Not Accessible Not Accessible Not Accessible Not Accessible Not Accessible Not Accessible Not Accessible N/A N/A N/A N/A N/A N/A N/A NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 19 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 VI NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 113 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVi NB AISI: 11.3 BWRVIP: 41 Exam Location ID BB-1-JPD&JP10 BB-2-JPI&JP2 BB-2-JP3&JP4 BB-2-JP5&JP6 BB-2-JP7&JP8 BB-2-JP9&JPl0 DF-1-JP1 DF-I-JP10 DF-1-JP2 DF-I-JP3 DF-1-JP4 Discription V

BWRVIP Location BB-1 Jet Pump Beam Bolt Hole Region Jet Pump Beam Transition Arm Region et Pump Beam Transition Arm Region Jet Pump Beam Transition Arm Region Jet Pump Beam Transition Arm Region BWRVIP Location BB-2 Jet Pump Beam Transition Arm Region Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld Nork Order Performed By Report No.

Exam 4160145 Westinghouse RE20 WIl EVr-1 I

4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse 4160145 Westinghouse RE20 IVl RE20 IVl RE20 IVl RE20 IVl RE20 lWI RE20 lWI RE20 iWI RE20 Iwi RE20 IVl EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 Ev-r-1 EVT-1 RE20 IWI EVT-1 Procedure Results Commments/Corrective Measures V-BWR-001 Rev:1 NRI V-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:I NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 20 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System VI NB AISI: 11,3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVl NB AISI: 11-3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IV[

NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 IVI NB AISI: 11.3 BWRVIP: 41 Exam Location ID DF-1-JP5 DF-I-JP6 DF-I-JP7 DF-I-JP8 DF-1-JP9 DF-2-JP1 DF-2-JP10 DF-2-JP2 DF-2-JP3 DF-2-JP4 DF-2-JP5 Discription V

Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld Diffuser Collar to Diffuser Shell Weld BWRVIP Location Jet Pump Diffuser Collar to Diffuser Shell Weld BWRVIP Location DF-i Jet Pump Diffuser Collar to Diffuser Shell Weld Diffuser Shell to Tailpipe Weld Diffuser Shell to Tailpipe Weld Diffuser Shell to Tailpipe Weld Diffuser Shell to Tailpipe Weld Diffuser Shell to Tailpipe Weld Diffuser Shell to Tailpipe Weld Nork Order Performed By F 4160145 Westinghouse 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Report No.

RE20 IWI RE20 Iwi RE20 IVV RE20 IVVI RE20 IVl RE20 IVl RE20 IVl RE20 IWI RE20 IVV RE20 IVl 4160145 Westinghouse RE20 IVl Exam EVT-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l FVT-1 IV-BWR-001 Rev:l EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:1 EV--1 IV-BWR-001 Rev:l NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Procedure Results Commments/Corrective Measures

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 21 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System lVI NB AISI: 11_3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 Ivi NB AISI: 11.3 BWRVIP: 41 IVi NB AISI: 11.6 BWRVIP: 41 IVi NB AISI: 11_6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 IV[

NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 Exam Location ID DF-2-JP6 DF-2-JP7 DF-2-JP8 DF-2-JP9 IN-4-JP1 IN-4-JP2 IN-4-JP3 IN-4-JP4 IN-4-JP5 IN-4-JP6 MX-2-JPI Discription Work Order Performed By Report No.

Diffuser Shell to Tailpipe Weld 4160145 Westinghouse RE20 IWI Diffuser Shell to Tailpipe Weld BWRVIP Location Jet Pump Diffuser Shell to Tailpipe Weld BWRVIP Location DF-2 Jet Pump Diffuser Shell to Tailpipe Weld Jet Pump Inlet Single Hole Nozzle Casting to Mixer Barrel Jet Pump inlet Single Hole Nozzle Casting to Mixer Barrel Jet Pump Inlet Single Hole Nozzle Casting to Mixer Barrel Jet Pump Inlet Single Hole Nozzle Casting to Mixer Barrel Jet Pump Inlet Single Hole Nozzle Casting to Mixer Barrel Jet Pump inlet Single Hole Nozzle Casting to Mixer Barrel BWRVIP Location MX-2 Jet Pump Barrel to Adapter Weld 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse RE20 IVl RE20 IVl RE20,WI RE20 IVl RE20 Iwi RE20 IVl RE20 IVl RE20 IWI RE20 IVI RE20 IWI Exam Procedure EVT-l IV-BWR-001 Rev:l EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:1 IV-BWR-001 ReVwl EVT-1 IV-BWR-001 Rev:l EVT-I IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l EVr-1 IV-BWR-001 Rev:l EVT-1 IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 22 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 Ivi NB AISI: 11-6 BWRVIP: 41 Ivi NB AISI: 11-6 BWRVIP: 41 Ivi NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.6 BWRVIP: 41 lvi NB AISI: 11.6 BWRVIP: 41 Ivi NB AISI: 11.6 BWRVIP: 41

]VI NB AISI: 11.6 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 Ivi NB AISI: 11.19 BWRVIP: 41 Exam Location ID MX-2-JP10 MX-2-JP2 MX-2-JP3 MX-2-JP4 MX-2-JP5 MX-2-JP6 MX-2-JP7 MX-2-JP8 MX-2-JP9 RB-la-JP1&JP2 RB-la-JP3&JP4 Discription BWRVIP Location MX-2 Jet Pump Barrel to Adapter Weld Barrel to Adapter Weld Barrel to Adapter Weld Barrel to Adapter Weld Barrel to Adapter Weld Barrel to Adapter Weld Barrel to Adapter Weld BWRVIP Location MX-2 Jet Pump Barrel to Adapter Weld BWRVIP Location MX-2 Jet Pump Barrel to Adapter Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Work Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVVI EVT-1 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse 4160145 Westinghouse RE20 IVl RE20 IWI RE20 IVl RE20 IVl RE20 IVl RE20 IVl RE20 WIl RE20 IVl RE20 iWI EVT-1 EVT-1 EvT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 RE20 Il EVT-1 IN Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:1 NRI IV-BWR-001 Revi NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IVwBWR-001 Rev:l NRi IV-BWR-001 Rev:1 NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 23 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.19 BWRVIP: 41 VI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 1119 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVl NB AISI: 11.19 BWRVIP: 41 VI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 VI NB AISI: 11.19 BWRVIP: 41 iVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 Exam Location ID RB-la-JP5&JP6 RB-lb-JPI&JP2 RB-lb-JP3&JP4 RB-lb-JP5&JP6 RB-lc-JPI&JP2 RB-ic-JP3&JP4 RB-Ic-JP5&JP6 RB-Id-JPI&JP2 RB-Id-JP3&JP4 RB-ld-JPS&JP6 RB-2a-JPI&JP2 Discription Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Vessel Pad Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Work Order Performed By Report No.

4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse 4160145 Westinghouse Exam RE20 IWI EVT-1 RE20 iWI RE20 IVl RE20 IVl RE20 IVl RE20 IWI RE20 IVV RE20 IVl RE20 IWI RE20 IVl 4160145 Westinghouse RE20IVVI EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 Evr-1 EVT-1 EVT-1 IV-BWR-001 Revwl IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Revwl Procedure Results Commments/Corrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 24 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.19 BWRVIP: 41 VI NB AISI: 11.19 BWRVIP: 41 IVt NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVI NB AISI: 11.19 BWRVIP: 41 IVl NB AISI: 11.19 BWRVIP: 41 VI NB AISI: 11_19 BWRVIP: 41 Exam Location ID RB-2a-JP3&JP4 RB-2a-JP5&JP6 RB-2b-JPI&JP2 RB-2b-JP3&JP4 RB-2b-JP5&JP6 RB-2c-JPI&JP2 RB-2c-JP3&JP4 RB-2c-JP5&JP6 RB-2d-JPI&JP2 RB-2d-JP3&JP4 RB-2d-JP5&JP6 Discription Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Jet Pump Primary Riser Brace Leaf to Yoke Weld Vork Order Performed By F 4160145 Westinghouse 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Report No.

Exam RE20 IWI EVT-1 IV-BWR-001 Rev:l RE20 IVl EVT-1 IV-BWR-001 Rev:l RE20 IWI EVT-1 IV-BWR-001 Rev:l RE20 IVl EVT-1 IV-BWR-001 Rev:l RE20 IWI EVr-1 IV-BWR-001 Rev:l RE20 IWI EVT-1 IV-BWR-001 Rev:1 RE20 iWI E.VT-1 IV-BWR-001 Rev.l RE20 IWI EV-r-1 IV-BWR-001 Rev:l RE20 IVV EVF-1 IV-BWR-001 Rev:l RE20 IVVI EVT-1 IV-BWR-001 Rev:l "RE20 IVVI EVT*-1 IV-BWR-001 Revl1 Procedure Results CommmentslCorrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 25 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System VI NB AISI: 11.22 BWRVIP: 41 VI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.22 BWRVIP: 41 IVi NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVi NB AISI: 11.22 BWRVIP: 41 IV[

NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.22 BWRVIP: 41 Exam Location ID RS-1-JP1&JP2 RS-1-JP3&JP4 RS-1-JP5&JP6 RS-1-JP7&JP8 RS-1-JPg&JPIO RS-2-JPI&JP2 RS-2-JP3&JP4 RS-2-JP5&JP6 RS-2-JP7&JP8 RS-2-JP9&JP10 RS-3-JPI&JP2 Discription W

Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld BWRVIP-41 Location RS-1 Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Recirc Thermal Sleeve to Jet Pump Riser Elbow Weld Jet Pump Riser Elbow to Riser Pipe Weld BWRVIP-41 Location RS-2 Jet Pump Riser Elbow to Riser Pipe Weld Jet Pump Riser Elbow to Riser Pipe Weld Jet Pump Riser Elbow to Riser Pipe Weld Jet Pump Riser Elbow to Riser Pipe Weld "Jet Pump Riser Pipe to Transition Piece Weld BWRVIP 41 Location RS-3

'ork Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVl EVT-1 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 WIl RE20 IWI RE20 IVl RE20 IVl RE20 IVl RE2O WIl RE20 WIw RE20 lWI RE20 IWI EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 4160145 Westinghouse RE20 IV l EVT-1 IV-BWR-001 Rev:l Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:1 NRI IV-BWR-001 Revl NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:i NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 26 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11-22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Exam Location ID RS-3-JP3&JP4 RS-3-JP5&JP6 RS-3-JP7&JP8 RS-3-JP9&JP10 RS-6-JPI&JP2 RS-6-JP3&JP4 RS-6-JP5&JP6 RS-7-JPI&JP2 RS-7-JP3&JP4 RS-7-JPS&JP6 RS-8-JPI&JP2 Discription A

Jet Pump Riser Pipe to Transition Piece Weld Jet Pump Riser Pipe to Transition Piece Weld Jet Pump Riser Pipe to Transition Piece Weld Jet Pump Riser Pipe to Transition Piece Weld BWRVIP Location RS-6 Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld BWRVIP Locarion RS-7 Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld Jet Pump Riser Pipe to Restrainer Bracket Circ. Weld Jet Pump Riser Pipe to Primary Riser Brace Circ. Weld Vork Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVVI EVF-1 4160145 westinghouse RE20 Iwi EVT-1 4160145 Westinghouse RE20 IWI EVT-1 4160145 Westinghouse RE20 WIi EVT-1 4160145 Westinghouse RE20 IVVI EVT-1 4160145 Westinghouse RE20 Ivvi EVT-1 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVVI EVT-1 RE20 WI EVT-1 RE20 WI..

EVT-1 RE20 IVVI EVT-1 Westinghouse RE20 IWI EVT-1 Procedure Results CommmentslCorrective Measures IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:i NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 27 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.22 BWRVIP: 41 IVI NB AISI: 11.22 BWRVIP: 41 Ivi NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 Ivi NB AISI: 11.21 BWRVIP: 41 IV]

NB AISI: 11.21 BWRVIP: 41 Exam Location ID RS-8-JP3&JP4 RS-8-JP5&JP6 RS-9-JPI&JP2 RS-9-JP3&JP4 RS-9-JP5&JP6 WD-1-JPI WD-1-JPIO WD-1-JP11 WD-1-JP12 WD-1-JPi3 WD-1-JP14 Discription Work Orde Jet Pump Riser Pipe to Primary 4160145 Riser Brace Circ. Weld Jet Pump Riser Pipe to Primary Riser Brace Circ. Weld Jet Pump Riser Pipe to Primary Riser Brace Circ. Weld Jet Pump Riser Pipe to Primary Riser Brace Circ. Weld Jet Pump Riser Pipe to Primary Riser Brace Circ. Weld Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area 4160145 4160145 4160145 4160145 4160145 "4160145 4160145 4160145 4160145 er Performed By R Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse "westing1house Westinghouse Westinghouse Westinghouse Report No.

Exam Procedure RE20 IWI EVT-1 IV-BWR-001 Rev:i RE20 W'Al RE20 IVVI RE20 IVVI RE2O WI RE20 IWI RE20 IWI RE20 IVVI RE20 IWI RE20 I'Ai 4160145 Westinghouse RE20 IVVI EVr-1 EVT-1 EVT-1 EVT-1 VT-i VT-i VT-i IV-BWR-001 Rev:1 iV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l I*-BWR-001 Rev:1 IV-BWR-001 Rev:I IV-BWR-001 Rev:1 IV-BWR-001 Rev:l VT-1 IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 28 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System VI NB AISI: 11.21 BWRVIP: 41 VI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IV]

NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 IVI NB AISI: 11.21 BWRVIP: 41 VI NB AISI: 11.21 BWRVIP: 41 VI NB AISI: 11.21 BWRVIP: 41 Exam Location ID WD-1-JP15 WD-1-JP16 WD-1 -JPI 7 WD-1-JP18 WD-1-JP19 WD-1-JP2 WD-1-JP20 WD-1-JP3 WD-1-JP4 WD-1-JP5 WD-1-JP6 Discription Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Work Order Performed By Report No.

4160145 Westinghouse RE20 IVl 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IWI RE20 IWI RE20 IVVI RE20 IVVI RE20 IWI RE20 IWI RE20 IWI RE20 IVVI RE20 Ivvi RE20 IVVI Exam Procedure VT-i IV-BWR-001 Rev:il VT-i IV-BWR-001 Rev:l VT-i IV-BWR-001 Rev:l VT-i IV-BWR-001 Rev:l VT-i IV-BWR-00i Rev:l VT-1 IV-BWR-001 Revwl VT-1 IV-BWR-001 Rev:l VT-i IV-BWR-001 Rev:l VT-i IV-BWR-001 Rev:i VT-i IV-BWR-001 Rev:l VT-i IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 29 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVl NB AISI: 11.21 BWRVIP: 41 Ivi NB AISI: 11.21 BWRVIP: 41 Ivi NB AISI: 11.21 BWRVIP: 41 Exam Location ID WD-1-JP7 WD-1-JP8 WD-1-JP9 Discription Jet Pump Wedge Bearing Surface Area Jet Pump Wedge Bearing Surface Area Work Order Performed By Report No.

Exam 4160145 Westinghouse RE20 IVl VT-1 4160145 Westinghouse RE20 IWI VT-1 BWRVIP Location WD-1 Jet 4160145 Westinghouse RE20 IVVI Pump Wedge Bearing Surface Area VT-i Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Revwl NRI

NIS-1, Table1.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 30 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Exam Location ID Discription Work Order Performed By Report No.

XMA-VIP47 Category Components Examined Equal:

36 VI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 VI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 CRGT-1-(06-35)

CRGT-1-(10-19)

CRGT-1-(10-35)

CRGT-1-(14-23)

CRGT-1-(14-31)

CRGT-1-(18-15)

CRGT-1-(22-23)

CRGT-1-(22-39)

CRGT-i-(30-15)

CRGT-1-(34-15)

CRGT-1 -(34-35)

Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld 4160145 Westinghouse 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVl RE20 IWI RE20 IVVI RE20 IwV RE20 IWI RE20 IVl RE20 IVl RE20 WIV RE20 IWI RE20 IVl RE20 IVl Exam VT-3 VT-3 Vr-3 vr-3 VT-3 VT-3 VT-3 VT-3 Vr-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures IV-BWR-001 Revwl IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XA examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section X1 examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 31 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 VI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 VI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 VI NB AISI:

BWRVIP: 47 IVI NB AISI:

BWRVIP: 47 Exam Location ID CRGT-1-(38-23)

CRGT-I-(42-19)

CRGT-2-(10-19)

CRGT-2-(10-35)

CRGT-2-(22-39)

CRGT-2-(34-15)

CRGT-2-(38-23)

CRGT-3-(10-19)

CRGT-3-(10-35)

CRGT-3-(22-39)

CRGT-3-(34-15)

Discription A

control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Guide Tube to Aligment Lug Weld Control Rod Drive Gudie Tube Assembly Upper Circ Weld Control Rod Drive Gudie Tube Assembly Upper Circ Weld Control Rod Drive Gudie Tube Assembly Upper Circ Weld Control Rod Drive Gudie Tube Assembly Upper Circ Weld Control Rod Drive Gudie Tube Assembly Upper Circ Weld Control Rod Drive Gudie Tube Assembly Lower Circ Weld Control Rod Drive Gudie Tube Assembly Lower Circ Weld control Rod Drive Gudie Tube Assembly Lower Circ Weld Control Rod Drive Gudie Tube Assembly Lower Circ Weld Work Order Performed By Report No.

Exam 4160145 Westinghouse 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse "Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 IVVI VT-3 RE20 IVl RE20 IVVI RE20 IWI RE20 IVl RE20 iWI RE20 IWlV RE20 iwi:

RE20 IWI RE20 IVVI RE20 IWI VT-3 EVT-1 EVT-1 EVr-I EVT-1 EVT-I EVT-1 EVT-1 EVr-I EVr-1 Procedure Results IV-BWR-001 Rev:1 NRI iV-BwR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:

N I

IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:i NRI IV-BWR-001 Rev:l NRI IV-BWR-001 Rev:1 NRI IV-BWR-001 Rev:1 NRI Commments/Corrective Measures Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

"Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section Xl examination.

Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

NIS-1, Table1.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 32 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System IVI NB AISI:

BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 VI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 LVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 Exam Location ID CRGT-3-(38-23)

FSIGT-APRIN-1-(10-35)

FSlGT-APRIN-1-(22-23)

FSIGT-APRIN-l-(22-39)

FS/GT-ARPIN-1-(06-35)

FS/GT-ARPIN-l-(10-19)

FS/GT-ARPIN-1-(14-23)

FSIGT-ARPIN-1-(14-31)

FS/GT-ARPIN-1 -(18-15)

FS/GT-ARPIN-1-(30-15)

FSIGT-ARPIN-1-(34-15)

Discription Control Rod Drive Gudie Tube Assembly Lower Circ Weld Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Work Order Performed By Report No.

4160145 Westinghouse 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse Exam RE20 IVVI EVT-1 RE20 IVl RE20 IVl RE20 IVl RE20 Iwi RE20 IVl RE20 IVl RE20 IVVI RE20 IVl RE20 IVVI RE20 IVVI VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures IV-BWR-001 Rev:l IV-BWR-001 Rev:1 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:1 IV-BWR-001 Rev:I IV-BWR-001 Rev:l IV-BWR-001 Rev:l NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI NRI Did not remove at this time. Examined from interior of Guide Tube in the weld area in conjunction with ASME Section XI examination.

Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section Xl examination.

Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section X1 examination.

Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section XI examination.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 33 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Exam Location ID IVI NB FSIGT-ARPIN-1-(34-35)

AISI: 11.24 BWRVIP: 47 IVI NB FS/GT-ARPIN-1-(38-23)

AISI: 11.24 BWRVIP: 47 IVI NB AISI: 11.24 BWRVIP: 47 FS/GT-ARPIN-1 -(42-19)

Discription Work Order Performed By Report No.

Exam Anti-Rotational Pin and Pin to 4160145 Westinghouse RE20 IWI VT-3 Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to 4160145 Westinghouse RE20 IVVI VT-3 Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Anti-Rotational Pin and Pin to 4160145 Westinghouse RE20 IWI VT-3 Core Plate Weld for Control Rod Drive Guide Tube Alignment Lug and Fuel Support Casting Procedure IV-BWR-001 Rev:l Results Commments/Corrective Measures NRI Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section Xl examination.

IV-BWR-001 Rev:1 NRI Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section XI examination.

IV-BWR-001 Rev:1 NRI Did not remove Orificed Fuel Support Casting or Guide Tube at this time. Examined in conjunction with ASME Section Xl examination.

NIS-1, Table1.3, RE20: RPV In-Vessel Visual Inspections (IVVI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Exam Location ID Discription XMAUG Category Components Examined Equal:

13 Page 34 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

Exam Procedure Results Commments/Corrective Measures RICSIL NB JPI>JPIO-ADJSCR-GAPS AISI: 11.21 BWRVIP:

RICSIL NB JP11>JP20-ADJSCR-GAPS AISI: 11.21 BWRVIP:

SIL 420 NB JPI>JP20-SENSLINE AISI: 11.13 BWRVIP:

SIL 420 NB JPI>JP20-SENSLINE-BKTWLDS AISI: 11.13 BWRVIP:

SIL 462 NB SSAHC-0-UT AISI: 11.7 BWRVIP:

SIL 462 NB SSAHC-180-UT AISI: 11.7 BWRVIP:

SIL 462 NB SSAHC-180-VT AISI: 11.7 BWRVIP:

SIL 462 NB SSAHCH-0-VT AISI: 11.7 BWRVIP:

SIL 465 NB JPI>JPIO-NOZMIX-INLET AISI: 11.6 BWRVIP:

SIL 465 NB JP11>JP-20-NOZMIX-INLET AISI: 11.6 BWRVIP:

Jet Pump Adjusting Screw Gaps 4160145 Jet Pump Adjusting Screw Gaps Jet Pump Sensing Lines Jet Pump Sensing Line Bracket Wleds Core Shroud Access Hole Cover to Core Shroud Support Plate 4160145 4160145 4160145 4160142 Core Shroud Access Hole Cover 4160142 to Core Shroud Support Plate Core Shroud Access Hole Cover to Core Shroud Support Plate Core Shroud Access Hole Cover to Core Shroud Support Plate Jet Pump Inlet Nozzle and Mixer Region (Welds and Crud Buildup)

Jet Pump Inlet Nozzle and Mixer Region (Welds and Crud Buildup) 4160145 4160145 4160145 4160145 Westinghouse Westinghouse Westinghouse Westinghouse Westinghouse RE20 WIl VT-3 RE20 IW[

RE20 IVl RE20 IWI AHCEDS#-I Westinghouse AHCEDS#-2 Westinghouse Westinghouse Westinghouse Westinghouse RE20 IWI RE20 IWI RE20 IWI RE20 IVI VT-3 VT-3 VT-3 UT IV-BWR-001 Rev:l IV-BWR-001 Rev:i IV-BWR-001 Rev:l IV-BWR-001 Rev:l CPRI-ISI-350 Rev OCI NRI See RE20 IWI Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NRI NRI NRI NRI UT CPRI-ISI-350 Rev 0C1 Rl EVT-1 EVT-1 VT-3 VT-3 IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:l IV-BWR-001 Rev:1 NRI NRI NRI NRI See RE20 IVl Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

UT examinations performed utilizing 45S and phased array 0 to 80L search units.

Examinations were not performed at 305 to 20 and 120 to 190 degrees due to configuration limitations. Visual exam per WO 4160145 (ref.

RE20 WI report).

UT examinations performed using the 45S and phased array 0 to 80 L search units. Indication identified at 222 to 239 degrees using phased array search unit. Indication appeared to be weld "suck up" or undercut and is not indicative of IGSCC therefore SAT.

Examined areas that were inaccessable by UT.

NIS-1, Tablel.3, RE20: RPV In-Vessel Visual Inspections (IWI)

Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 35 of 35 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System SIL 474 NB AISI: 11.5 BWRVIP:

Exam Location ID Steam Dryer-Drain Channels SIL 574 NB JPI>JP10-ADJSCR-TACWLDS AISI: 11.21 BWRVIP:

SIL 574 NB JP11>JP20-ADJSCR-TACWLDS AISI: 11.21 BWRVIP:

Discription Work Order Performed By Report No.

Exam Steam Dryer Channnel Welds 4160145 Westinghouse RE20 IVVI VT-3 Jet Pump Adjusting Screw Tack 4160145 Westinghouse RE20 Iwi VT-3 Welds Jet Pump Adjusting Screw Tack 4160145 Westinghouse RE20 IWI VT-3 Welds Procedure IV-BWR-001 Rev:i Results Commments/Corrective Measures RI RI's documented in Notification 10125591 and dispositioned as SAT for at least one more cycle of operation.

IV-BWR-001 Rev:1 NRI See RE20 IWI Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

IV-BWR-001 Rev:1 NRI See RE20 IVl Report, Section 3, Tab 3 under each Jet Pump section for inspection results.

NIS-1, Table 1.4, RE20: PRESSURE TESTING Owner: NPPD P.O. Box 499, Columbus, NE 68302 Plant: Cooper Nuclear Station, P.O. Box 98, Brownville, NE 68321 Plant Unit: No. 1 Commercial Service: July 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Cd CoeCompletion Cmet Code Code Exam Procedure Rev tComments System Cat Item Date ASME Class 2 C7.30, VT-2 Pressure testing performed in accordance CS-A Core spray C-H C7.50, 40 6.1CS.501 5

06/2001 to ASME Section XI, 1989 Edition and all System, Loop A C7.70 month applicable procedure sections.

ASME Class 2 C7.30, VT-2 Pressure testing performed in accordance CS-B Core spray C-H C7.50, 40 6.2CS.501 4

06/2001 to ASME Section XI, 1989 Edition and all System, Loop B C7.70 month applicable procedure sections.

Ca20 V--2Pressure testing performed in accordance HPCI HPCI System C-H C7.70 40 6.HPCI.502 0

01/2002 to ASME Section Xl, 1989 Edition and all month applicable procedure sections.

ASME Class 1 VT-2 Pressure testing performed in accordance NBI Vessel Flange BP B15.50 Each 7.0.8.1 12 12/2001 to ASME Section XI, 1989 Edition.

Leak Detection refuel Reference PM 10606 and WO 4184927 for Line outage completion of work.

ASME Class 3 VT-2 Pressure testing performed in accordance NBI Nuclear Boiler D-A &

D1.10 40 6.NBI.501 6

10/2001 to ASME Section XI, 1989 Edition and all Instrumentation D-B D2.10 month applicable procedure sections.

System ASME Class 2 C7.30, VT-2 Pressure testing performed in accordance RCIC Reactor Core C-H C7.50, 40 6.RCIC.501 5

10/2001 to ASME Section XI, 1989 Edition and all Isolation Cooling C7.70 month applicable procedure sections.

System ASME Class 2 VT-2 Pressure testing performed in accordance RCIC Reactor Core C-H C7.30, 40 6.RCIC.502 0

01/2002 to ASME Section X1, 1989 Edition and all SstemCmonth applicable procedure sections.

System ASME Class 3C7.10, Reactor C-H &

C7.30, VT-2 Pressure testing performed in accordance Equipmento

-B C7.50, 40 6.REC.501 6

09/2001 to ASME Section XI, 1989 Edition and all Equing C7.70, month applicable procedure sections.

Cooling D2.10 Page 1 of 2

NIS-1, Table 1.4, RE20: PRESSURE TESTING Owner: NPPD P.O. Box 499, Columbus, NE Plant: Cooper Nuclear Station, P.O. Box 98, Plant Unit: No. 1 68302 Brownville, NE 68321 Commercial Service: July 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Code Code

~Completion Cmet Code Code Exam Procedure Rev tComments System Configuration Cat Item Date Pressure testing performed in accordance ASME Class 2 C7.10, VT-2 12/2001 to ASME Section Xl, 1989 Edition and all RHR Residual Heat C-H C7.30, 40 6.1RHR.501 601/2001 applicable procedure sections. Shut down Removal System C7.70 month cooling piping performed during outage, C7.70 balance performed post outage.

ASME Class 2 VT-2 Pressure testing performed in accordance SW-A Service Water DB D2.10 40 6.1SW.501 8

01/2001 to ASME Section XI, 1989 Edition and all System Month applicable procedure sections ASME Class 2 VT-2 Pressure testing performed in accordance SW-B Service Water DB D2.10 40 6.2SW.501 7

01/2001 to ASME Section XI, 1989 Edition and all System month applicable procedure sections 815.10 ASME Class 1 815.50 System Leakage B15.50 Pressure testing performed in accordance NB&

Test.

815.70 Each to ASME Section XI, 1989 Edition and all rEfuel6.MISC.502 loCi 12/2001 applicable procedure sections.

CR0 Includes Class 2 refuel Miscellaneous non-code leaks identifed portions of CRD C-H C7.10 outage and corrected.

System C7.30 SysimC7.70 Page 2 of 2

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Page 1 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A Plant Unit: 1 National Board Number for Unit: 20762 Item No. System Component ID Snubber Type Work Order Performed By ReportNo.

Exam Procedure 2 1/2 x 5 Type Snubbers Examined and or Tested Equal: 52 10 MS MS-SI6B 2 1/2 x 5 4164747 CNS 4164710 VT-3 7.2.34.1 VT-3 7.2.34.2 FUNCTEST 7.2.34.7 11 MS MS MS MS MS MS MS MS REC MS-S19 MS-S2 MS-S23 MS-S25 MS-S3 MS-S4 MS-S7A MS-S7B Rcc-s20 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2x5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS cNS CNS 4164747 Vr-3 4164747 4164747 4164747 4164747 4164747 4164743 4164747 4164747 VT-3 V'-3 VT-3 VT-3 Vr-3 VT-3 VT-3 FUNCTEST VT-3 VT-3 Results SAT, OP SAT, OP SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.7 SAT, OP 7.2.34.1 7.2.34.1 SAT, OP SAT, OP Commments/Corrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164710 removed snubber S/N 10046 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber SIN 8101.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, Reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164743 removed snubber SIN 8542 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 7744.

Work Order 4164747 Visual Examiantion only, reference Relief Suveillance Procedure 6.SNUB.601 and Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O.

Plant Unit: 1 Item No. System 28 29 cs REC REC RHR RHR RHR RHR RHR RHR RHR RHR Component ID cs-si I RCC-S21 RCC-S22 RH-S20 RH-822 RH-S24 RH-S25 RH-S25A RE-S26 RH-S27A RH-S30A Box 98, Brownville, NE 68321 Snubber Type 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2x5 2 1/2 x 5 2 1/2 x5 2 1/2 x 5 Page 2 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS CNS Exam 4164747 Vr-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 VT-3 Vr-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System 3

30 31 cs RHR RHR Page 3 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Work Order Performed By Report No.

4164747 CNS Component ID CS-S2 RH-S30B RH-S34 RH-S37 RH-S40 RH-S41 RH-S42 RH-S43 RH-S44A RH-S44B RH-S48A Snubber Type 2 1/2 x 6 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2x5 2 1/2x5 2 1/2 x 5 2 1/2 x 5 2 1/2 x5 Exam 4164747 Vr-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS CNS Procedure Results 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.7 SAT, OP 4164747 4164716 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 vr-3 VT-3 VT-3 FUNCTEST V'-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 CommmentslCorrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request Rl-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164716 removed snubber SIN 10050 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber SIN 7730.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6-SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 32 33 34 35 36 37 38 39 SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP RHR RHR RHR RHR RHR RHR RHR RHR

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component ID Snubber Type Work Order Perform 4

cs CS-S3 21/2 x 5 4164747 CNS 40 RHR RH-S48B 2 1/2 x 5 4164747 CNS 41 42 43 44 45 46 47 48 49 RHR RHR RHR RHR RHR RHR RHR RHR RHR RH-S52 RH-S54 RH-S55 RH-S57 RH-S59 RH-S76A RH-S76B RH-S77 RH-S78A 2 1/2x5 2 1/2 x 5 2 1/2 x5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 2 1/2 x 5 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS Page 4 of 21 med By Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Report No.

Exam Procedure 4164747 VT-3 7.2.34.1 4164747 VT-3 7.2.34.1 4164747 4164747 4164747 4164747 4164718 4164747 4164747 4....1..64747 4164747 VT-3 vr-3 VT-3 Vr-3 Vr-3 Vr-3 vr-3 FUNCTEST VT-3 vr-3 S.........W 3......

VT-3 VT-3 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.2 7.2.34.7 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 Results Commments/Corrective Measures SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB-601 and Relief Request RI-13.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

SAT, OP Work Order 4164747 Visual Examiantion only, SAT, Op reference Suveillance Procedure 6.SNUB.601 and SAT, OP Relief Request RI-13. Work Order 4164718 removed snubber SIN 8096 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber SIN 8132.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 5 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 5

CS Component ID CS-S6 Snubber Type 2 1/2 x 5 Work Order Performed By Report No.

Exam 4164747 CNS 4164747 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164740 VT-3 VT-3 FUNCTEST 4164747 Vr-3 4164747 VT-3 4164747 Vr-3 4164717 VT-3 VT-3 FUNCTEST 4164747 Vr-3 4164747 VT-3 "4164747 Vr-3 7.2.34.1 7.2.34.2 7.2-34.7 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164740 removed snubber SIN 8165 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber SIN 8079.

50 RHR 51 RHR 52 RHR 53 RHR 6

cs 7

HPCI 8

MS 9

MS RH-S78B RH-S80 RH-S96A RH-S98 CS-S7 HP-S15 BS-SI 16A BS-S116B 2 1/2 x 5 2 1/2 x5 2 1/2 x 5 2 1/2 x5 2 1/2 x 5 2 1/2 x 5 21/2 x 5 2 1/2 x 5 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, OP Reference Suveillance Procedure 6.SNUB.601 and 7.2.34.7 SAT, OP Relief Request RI-13. Work Order 4164717 removed snubber S/N 10061 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 10051.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component ID Snubber Type Work Order Perform PSA-10 Type Snubbers Examined and or Tested Equal: 89 1

Cs CS-SI PSA-10 4164747 CNS 100 101 102 103 104 105 106 107 108 MS MS MS MS MS MS MS MS MS VR-H64D VR-S1 VR-SIO VR-Sl1 VR-S14 VR-S2 VR-S23A VR-S23B VR-S24A PSA-10 PSA-10 PSA-10 PSA-i0 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 CNS CNS CNS CNS CNS CNS CNS CNS CNS Page 6 of 21 ned By Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Report No.

Exam Procedure 4164747 VT-3 7.2.34.1 4164747 4164747 4164747 4202891 4164747 4164747 4164747 4164747 4164747 Vr-3 Vr-3 Vr-3 Vr-3 Vr-3 FUNCTEST Vr-3 VT-3 Vr-3 VT-3 VT-3 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 Results SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP Commments/Corrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205891 removed snubber SIN 477 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 487.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB-601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 7 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 109 MS 110 111 112 113 114 115 116 117 118 MS MS MS MS MS MS MS MS MS 119 MS Component ID VR-S24B VR-S26 VR-S3 VR-S30 VR-S32 VR-S4 VR-S42A VR-S42B VR-S61 VR-S6 VR-S62A Snubber Type PSA-10 PSA-10 PSA-10 PSA-10 PSA-il0 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 Work Order Performed By Report No.

4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS 4164747 CNS Exam 4164747 VT-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 VT-3 Vr-3 VT-3 Vr-3 Vr-3 VT-3 Vr-3 Vr-3 Vr-3 4164747 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only.

reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 8 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 120 MS 121 MS 122 MS 123 MS 124 M S 125 MS 126 MS 127 MS 128 MS 129 MS Component ID VR-S62B VR-S71A VR-S71 B VR-S74 VR-S8 VR-S81 VR-S83A VR-S83B VR-S84 VR-S85 Snubber Type PSA-10 PSA-10 PSA-Il0 PSA-Il0 PSA-Il0 PSA-10 PSA-lI0 PSA-10 PSA-i0 PSA-10 Work Order Performed By 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS Report No.

Exam 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164390 Vr-3 VT-3 FUNCTEST 4164395 VT-3 Vr-3 FUNCTEST 4164747 Vr-3 4164747 VT-3 4164747 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, Op reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-13. Work Order 4164390 removed snubber S/N 449 as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber S/N 7019.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, Op reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-13. Work Order 4164395 removed snubber S/N 464M as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber S/N 15147.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34A1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 9 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 130 MS 131 MS 132 MS 133 MS 134 MS 135 RF 136 RF 137 RF 138 RF Component ID VR-S86A VR-S86B VR-S87A VR-S87B VR-S88 RF-S10 RF-S11 RF-S12 RF-S14 Snubber Type PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-1 0 PSA-10 PSA-lO PSA-10 Work Order Performed By Report No.

4164747 CNS 4205892 4164747 CNS 4164747 CNS 4164747 cNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS Exam VT-3 Vr-3 FUNCTEST 4164747 VT-3 4164747 VT-3 4164386 VT-3 Vr-3 FUNCTEST 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164613 Vr-3 VT-3 FUNCTEST 4164747 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order4164747 Visual Examiantion only, 7.2.38.2 SAT, OP reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-13. Work Order 4205892 removed snubber S/N 479 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 5217.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3. Work Order 4164386 removed snubber SIN 473 as part of 10% Test Sample, perfomed as found and as left VT-3, performed functional test, and replaceed with with identical snubber SIN 401.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2-34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164613 removed snubber SIN 472 as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber SIN 17205.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 10 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 139 RF 140 141 142 143 144 145 146 147 148 149 RF RF RF RF RF RHR RHR RHR RHR RHR Component ID RF-S15 RF-S16 RF-S17 RF-S18 RF-S19 RF-S8 RH-S11 RH-S14 RH-SI4A RH-S5 RH-S6 Snubber Type PSA-10 PSA-10 PSA-1O PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-lO PSA-10 Work Order Performed By Report No.

4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS CNS Exam 4164701 Vr-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164617 V--3 FUNCTEST VT-3 VT-3 VT-3 VT-3 VT-3 Vr-3 VT-3 VT-3 VT-3 Vr-3 VT-3 FUNCTEST Procedure Results 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.8 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, oP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.8 SAT, OP Commments/Corrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164701 removed snubber S/N 6281 as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber SIN 470.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3. Work Order 4164617 removed snubber S/N 481 as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber S/N 17204.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 11 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 150 151 152 153 154 155 156 157 158 159 60 RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR PC Component ID RH-S67 RH-S68 RH-S69A RH-S69B RH-S70 RH-S71 RH-S73 RH-S8A RH-S8B RH-S8C PV-SIAA Snubber Type PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 Work Order Performed By 4164747 cNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS CNS Report No.

Exam 4164747 VT-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4205995 4164747 4164747 V'r-3 VT-3 VT-3 vF-3 VT-3 Vr-3 V-r-3 Vr-3 V-r-3 FUNCTEST VT-3 Vr-3 Procedure Results 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.8 SAT, OP 7.2.34.1 7.2.34.1 SAT, OP SAT, OP Comm ments/Corrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747-Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205995 removed snubber S/N 8145M due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber SIN 7003.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System 61 PC RHR RHR RHR RHR RHR RHR MS MS MS Component ID PV-SIAB RH-S21 RH-S29 RH-S3A RH-S45 RH-S49 RH-S58 MS-S22 SS-B2 SS-B3 Snubber Type PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-1o PSA-10 PSA-10 PSA-10 PSA-10 Work Order Performed By 4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS cNS CNS Page 12 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Report No.

Exam 4164747 VT-3 4164747 4164747 4164747 4164747 4202850 4164747 4164747 4164747 4164747 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 FUNCTEST Vr-3 VT-3 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4202850 removed snubber S/N 476 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 394.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 13 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 82 MS 84 MS 85 MS 86 MS 87 MS 88 MS 89 MS 90 MS 91 MS 92 MS 93 MS Component ID SS-C2 VR-55-9-Y VR-55-9-Z VR-56-12-Y VR-58-12-Y VR-59-7-X VR-59-7-Z VR-60-7-X VR-60-7-Z VR-61-8-X VR-62-17-X Snubber Type PSA-10 PSA-10 PSA-10 PSA-10 PSA-1o PSA-10 PSA-i0 Work Order Performed By Report No.

4164747 CNS 4164392 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS PSA-10 PSA-10 PSA-10 PSA-10 Exam VT-3 Vr-3 FUNCTEST 4164747 Vr-3 4164747 VT-3 VT-3 4164747 VT-3 4164747 Vr-3 4164391 VT-3 VT-3 FUNCTEST 4164747 Vr-3 4164747 VT-3 4164747 Vr-3 4164747 Vr-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, OP reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-1i3. Work Order 4164392 removed snubber S/N 448 as part of 10% Test Sample, performed as found and as left VT-3, and replacement with with identical snubber S/N 447.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164391 removed snubber S/N 465M as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber S/N 478.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, Reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 14 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 94 MS 95 MS 96 MS 97 MS 98 MS 99 MS Component ID VR-62-8-X VR-H61 D VR-H62B VR-H62C VR-H63B VR-H63C Snubber Type PSA-1O PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 Work Order Performed By 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS Report No.

Exam 4164747 VT-3 4164393 V--3 VI-3 FUNCTEST 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164747 Vr-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 VisualiExamiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, OP reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-13. Work Order 4164393 removed snubber S/N 457M as part of 10% Test Sample, perfomed as found and as left VT-3, and replacement with with identical snubber S/N 402.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Item No. System Component ID Snubber Type Work Order Performed By Page 15 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Ur Report No.

Exam Pr PSA-3 Type Snubbers Examined and or Tested Equal: 15 54 CS MS MS RHR 58 RHR MS MS MS MS MS CS-VE7 MS-S149B MS-S16 RH-S65A RH-S65B MS-S21 MS-S63 VR-S31 VR-S43 VR-S5OA PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 4164747 CNS 4164747 4164747 4164747 CNS CNS CNS 4164747 CNS 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS 4164747 Vr-3 55 56 57 4164747 4164747 4164382 4164385 4164747 4164747 4164747 4164747 4164747 nit: 20762 rocedure Results 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.1 SAT, OP 7.2.34.2 SAT, OP 7.2.34.8 SAT, OP VT-3 VT-3 Vr-3 VT-3 FUNCTEST VT-3 VT-3 FUNCTEST Vr-3 Vr-3 VT-3 VT-3 Vr-3 SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP Commments/Corrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6-SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13 Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164382 removed snubber S/N 843 as part of the 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber SIN 8378.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R I-13. Work Order 4164385 removed snubber S/N 8374 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 458.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 69 70 71 72 73

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 16 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 74 MS 75 RF 76 RHR 77 RWcu 78 RWCU Component ID VR-S5OB RF-S9 RH-S15 CU-S3A CU-S3B Snubber Type PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 Work Order Performed By 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS Report No.

Exam 4164747 Vr-3 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164747 Vr-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 17 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System Component ID Snubber Type PSA-35 Type Snubbers Examined.and or.Tested Equal: 4 160 MS 161 MS 162 MS 163 MS 164 MS 165 MS 166 MS SS-A2 SS-D2 SS-A3 SS-D3 VR-55-23-X VR-55-26-Z VR-56-24-X PSA-35 PSA-35 PSA-35 PSA-35 Work Order Performed By Report No.

Exam 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS PSA-35 PSA-35 PSA-35 4164709 V[F-3 Vr-3 FUNCTEST 4164703 Vr-3 VT-3 FUNCTEST 4205999 Vr-3 VT-3 FUNCTEST 4164706 Vr-3 Vr-3 FUNCTEST 4164704 Vr-3 VT-3 FUNCTEST 4205998 VT-3 VT-3 FUNCTEST 4205997 VT-3 VT-3 FUNCTEST Procedure 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 7.2.34.1 7.2.34.2 7.2.34.8 Results Commments/Corrective Measures SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13. Work Order 4164709 removed snubber S/N 6437 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 12983.

Work Order 4164747 Visual Examiantion only.

reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164703 removed snubber S/N 5315 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 5299.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205999 removed snubber S/N 9907 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 5319.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 Relief Request RI-13. Work Order 4164706 removed snubber S/N 5327 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 12979.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164704 removed snubber S/N 5316 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber SIN 5320.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205998 removed snubber S/N 8925 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber SIN 5310.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205997 removed snubber S/N 8920 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 10797.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 18 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 167 MS 168 MS 169 MS 170 MS 171 MS 172 MS 173 MS 174 MS 175 MS Component ID VR-61-17-X VR-61-8-Z VR-62-8-Z VR-S12 VR-S20 VR-S21 VR-S22 VR-S25 VR-S27 Snubber Type PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 Work Order Performed By 4164747 ONS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS Report No.

Exam 4164747 Vr-3 4164747 Vr-3 4164747 VT-3 4205992 VT-3 VT-3 FUNCTEST 4164747 VT-3 4164747 VT-3 4164747 VT-3 4164747 VT-3 4205990 VT-3 Vr-3 FUNCTEST Procedure Results 7.2.34.1 SAT, OP CommmentslCorrective Measures Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3. Work Order 4205992 removed snubber SIN 6866 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 5323.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3. Work Order 4105990 removed snubber S/N 5321 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 345.

4164747 CNS 4164747 VT-3 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

176 MS VR-S40 PSA-35

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 19 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 177 MS 178 MS 179 180 181 182 183 184 185 186 187 MS MS MS MS MS MS MS SRF RHR Component ID VR-S41 VR-S60 VR-S61 VR-S63 VR-S72 VR-S73 VR-S7A VR-S7B VR-S82 RF-S13 RH-S9 Snubber Type PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 Work Order Performed By Report No.

Exam 4164747 CNS 4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS 4164747 Vr-3 4205988 VT-3 VT-3 FUNCTEST 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 Vr-3 VT-3 VT-3 Vr-3 VT-3 VT-3 VT-3 Vr-3 VT-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request R1-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, 7.2.34.2 SAT, OP reference Suveillance Procedure 6.SNUB.601 and 7.2.34.8 SAT, OP Relief Request RI-13. Work Order 4205988 removed snubber SIN 5318 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 5301.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6-SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 20 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 188 RHR 189 RHR 190 RHR 191 RHR 192 RHR 193 RHR 194 RR 195 RR 196 RR 197 RR Component ID RH-Sl0 RH-S16 RH-S17 RH-S18 RH-S19 RH-S72A SSolA SS-lB SS-2A SS-2B Snubber Type PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 Work Order Performed By Report No.

Exam 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 CNS 4164747 VT-3 4205982 VT-3 Vr-3 FUNCTEST 4164747 Vr-3 4164747 Vr-3 4205986 VT-3 VT-3 FUNCTEST 4164747 VT-3 4164747 VT-3 4164702 Vr-3 Vr-3 FUNCTEST 4164747 VT-3 4164747 Vr-3 Procedure Results Commments/Corrective Measures 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205982 removed snubber SIN 5304 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber SIN 339.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4205986 removed snubber SIN 5307 due to Service Life Monitoring, performed as found and as left VT-3, performed Functional Test, and replaced with with identical snubber S/N 5302.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

7.2.34.1 7.2.34.2 7.2.34.8 SAT, OP SAT, OP SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13. Work Order 4164702 removed snubber S/N 5303 as part of 10% Test Sample, performed as found and as left VT-3, performed Functional Test, and replacement with with identical snubber S/N 6878.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

NIS-1, Table 1.5, RE20: Snubber Visual Examinations and Test Results Owner: NPPD P.O. Box 499 Columbus, NE 68602 Plant: Cooper Nuclear Station P.O. Box 98, Brownville, NE 68321 Plant Unit: 1 Page 21 of 21 Commerical Service Date: July, 1974 Owner Certificate of Authorization: N/A National Board Number for Unit: 20762 Item No. System 198 RR 199 200 201 202 203 204 205 59 68 83 RR RR RR RR RR RR RR MS MS MS Component ID SS-3A1 SS-3A2 SS-3B1 SS-3B2 SS4A SS-4B SS-5A SS-5B BS-S2A BS-SIB&R sS-c3 Snubber Type PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 Work Order Performed By Report No.

4164747 CNS 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 CNS CNS CNS CNS CNS CNS CNS CNS CNS CNS Exam 4164747 VT-3 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 4164747 VT-3 VT-3 VT-3 Vr-3 Vr-3 VT-3 VT-3 VT-3 VT-3 Vr-3 Procedure Results Commments/Corrective Measures 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 7.2.34.1 SAT, OP Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP SAT, OP Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-13.

Work Order 4164747 Visual Examiantion only, reference Suveillance Procedure 6.SNUB.601 and Relief Request RI-1i3.

Total Snubbers Equal: 205

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI

1.

Owner: Nebraska Public Power District P.O. Box 98 Brownville, Nebraska 68321

2.

Plant:

Cooper Nuclear Station P.O. Box 98 Brownville, Nebraska 68321

3.

Work Performed by:

NPPD P.O. Box 98 Brownville, Nebraska 68321 Date:

April 2, 2002 Sheet I

of 8

Unit One N/A Repair Organization, P.O. No., Job No., etc.

Type Code Symbol Stamp N/A Authorization No.

N/A Expiration Date N/A

4.

Identification of System

5.

(a) Applicable Construction Code As shown in the Attached Table As shown in the Attached Table (b) Applicable Edition of Section XI Utilized for Repairs or Replacements:

1989 Edition including 1989 Addenda & 1992 Edition including 1992 Addenda (IWE)

6.

Identification of Components Repaired or Replaced and Replacement Components:

As shown in the Attached Table

7.

Description of Work:

8.

Tests Conducted:

As shown in the Attached Table As shown in the Attached Table

9.

Remarks: The following Code Cases listed in the Third Ten-Year Interval Program were used for Repairs and Replacements:

N-416-1 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and these repairs and replacements conform to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Certificate of Authorization No.

N/A Expiration Date N/A Signed 6L (

-ClA.,

i Date I-

\\-

I-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State ofNebraska and Employed by Hartford Steam Boiler Inspection and Insurance Company ofConnecticut of Hartford, Connecticut have inspected the components described in this Owner's Report during the period May 30, 2000 to January 2, 2002, 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 Owners's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

xzv 7

ins jfctor's Signature "t

nsrctor'sSignature Date

//*'

2,*

~*

Commissions,/(,t_04/7,# A/

ýA National Board, State, Province, a'nd Endorsements o,

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

Cl Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 99-3174(2)

SW SW-P-A N/A 3

Byron Jackson N/A Replaced both lower columns B31.1-1967 1969 Replaced N/A 99-402 Div/Borg-Warner and bowl assembly 99-3303 SW SW-P (Part 19127)

N/A 3

Byron Jackson N/A Weld repair flange mating B31.1-1967 1969 Repaired N/A N/A Div/Borg-Wamer surface.

99-3535 SW SW-AOV-850AV N/A 3

Hills-McCanna N/A Replaced valve.

B31.1-1967 1969 Replaced N/A 00-051 00-0003 SW SW-P (Part 10484 &

N/A 3

Byron Jackson N/A Weld repair eroded areas Of the B31.1-1967 1969 Repaired N/A N/A 10487)

Div/Borg-Wamer columns and flanges.

00-0460 SW SW-P-BPA N/A 3

Byron Jackson N/A Replace Pump, Remove and B31.1-1967 1969 Replaced N/A 00-216 Div/Borg-Warner reinstall pump support 00-0469(2)

SW SW-P-BPC N/A 3

Byron Jackson N/A Replace Pump, Remove and B31.1-1967 1969 Replaced N/A 00-249 Div/Borg-Warner reinstall pump support, Grind pump pedestal 00-2466 SW SW-CV-13CV N/A 3

Atwood & Morrill N/A Replace Valve B31.1-1967 1969 Replaced N/A 00-270 00-2466 SW SW-EXPJ-SWPD N/A 3

Garlock N/A Replace expansion joint B31.1-1967 1969 Replaced N/A 00-270 00-2466(2)

SW SW-P-D N/A 3

Byron Jackson N/A Replace Pump Complete and the B31.1-1967 1969 Replaced N/A 00-270 Div/Borg Warner 32 studs in intermediate column 00-3104 SW SW-P-BPB N/A 3

Byron Jackson N/A Replace Pump & Remove and B31.1-1967 1969 Replaced N/A 01-029 Div/ Borg-Warner repalce pump support 00-3682 SW SW-P (Part 01466)

N/A 3

Byron Jackson N/A Replace top case and drill new B31.1-1967 1969 Repaired N/A N/A Div/ Borg-Warner holes for new wear ring 4158132 REC REC-Hx-A 27030 3

Southwestern N/A Repair Eroded Areas by ASME VIII 1969 Repaired YES01-041, N-416-1 Engineering Co.

Welding 1968 Edition 4158133 REC REC-Hx-B 27031 3

Southwestern N/A Repair Eroded Areas by ASME VIII 1969 Repaired YES01-042 Engineering Co.

Welding 1968 Edition 4159595 REC FC-R-I J N/A 3

American Air N/A Replace Fan Coil and add B31.1-1967 1969 Replaced N/A 00-238,00-239 Filter nipples to inlet/outlet 4159596 REC FC-R-1E N/A 3

American Air N/A Replace Fan Coil B31.1-1967 1969 Replaced N/A 01-196,01-525 Filter 4159603 RCC RCC pipe weld W51 N/A 3

NPPD N/A Repair cracked weld B31.1-1967 1969 Repaired N/A 01-169, N-416-1 4159614 SW SW-Pipe N/A 3

NPPD N/A Replace pipe B31.1-1967 1969 Replaced N/A 01-052,N-416-1 Page 2 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

Cl Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4159615 SW SW -Pipe Cap N/A 3

NPPD N/A Replace Pipe Cap B31.1-1967 1969 Replaced N/A 01-053, N-416-1 4159623 PC Vent Ring Header C-4448 2

Chicago Bridge &

N/A Repair weld bum through ASME 1In, 1969 Repaired YES 6.PC.503 Iron 1965 Edition, w/ W. 67' Add.

4159624 PC Torus Support C-4448 2

Chicago Bridge &

N/A Repair indication in weld ASME II, 1969 Repaired YES N/A Iron 1965 Edition, w/ W. 67' Add.

4159629 PC Vent Ring Header C-4448 2

Chicago Bridge &

N/A Repair weld bum through ASME I, 1969 Repaired YES 6.PC.503 Iron 1965 Edition, w/ W. 67' Add.

4159767 HPCI HPCI-CV-10CV N/A 2

Anchor Darling N/A Replaced tack weld on disc nut B31.1-1967 1969 Replaced N/A 01-004 4159884 CRD CRD-02-27 N/A I

General Electric N/A Replaced CRD flange & bolts ASME I 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 1966 Add.

4159899 SW SW-Piping N/A 3

Power Cutting Inc.

N/A Fab Replacement spools B31.1-1967 1969 Replaced N/A 01-266, N-416-1 4159899 SW SW-Piping N/A 3

Power Cutting Inc.

N/A Install Replacement spools B31.1-1967 1969 Replaced N/A 01-266, N-416-1 4159899 SW SW-Piping Supports N/A 3

Power Cutting Inc.

N/A Replace Piping supports B31.1-1967 1969 Replacement N/A N/A 4159899 SW SW-Piping N/A 3

Power Cutting Inc.

N/A Repair piping local thin areas B31.1-1967 1969 Repaired N/A 01-266, N-416-1 4159899 SW SW-H164 N/A 3

Power Cutting Inc.

N/A Replace pipe support B31.1-1967 1969 Replaced N/A N/A 4159899 SW SW-H163 N/A 3

Power Cutting Inc.

N/A Replacejam nut on pipe support B31.1-1967 1969 Replaced N/A N/A 4159899 SW SW-S98 N/A 3

Power Cutting Inc.

N/A Replace nut, bolt & spacer B31.1-1967 1969 Replaced N/A N/A 4159946 RHR RHR-MOV-MO39B N/A 2

Anchor Darling N/A Drill hole in valve disc, plug, B31.1-1967 1969 Repaired N/A 01-273, 6.PC.501 drill new hole through disc 4159947 HPCI HPCI-MOV-MO58 N/A 2

Anchor Darling N/A Drill hole in valve disc B31.1-1967 1969 Repaired N/A 01-274, 6.PC.501 4159954 MS MS-MO-MO77 N/A 3

Anchor Valve Co.

N/A Replace valve by welding B31.1-1967 1969 Replaced N/A 01-689, N-416-1 4159962 RCIC RCIC-CV-20CV N/A 2

Crane-Aloyco N/A Replace disc stud locking nut B31.1-1967 1969 Replaced N/A N/A 4159978 RHR RHR-MOV-MO39A N/A 2

Anchor Darling N/A Drill hole in valve disc B31.1-1967 1969 Repaired N/A 01-272, 6.PC.501, 4159978 RHR RHR-MOV-MO39A N/A 2

NOVA Mach. Prd.

N/A Replace bonnet studs B31.1-1967 1969 Replacement N/A 01-272 Page 3 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

Cl Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4159995 SW RHR-HX-B 27052 3

Southwestern N/A Repair divider plate edge and ASME VIII 1969 Repaired YES01-459, N-416-1 Engineering Co.

closure head groove 1968 Edition 4159996 SW RHR-HX-A 27051 3

Southwestern N/A Repair divider plate edge and ASME VIII 1969 Repaired YES01-460 Engineering Co.

closure head groove 1968 Edition 4160040 HPCI HPCI-CV-15CV N/A 2

Anchor Darling N/A Replace valve and add new B31.1-1967 1969 Replaced N/A 01-487,N-416-1, piping 6.PC.501 4160113 SW SW-Pipe N/A 3

NPPD N/A Replace Piping B31.1-1967 1969 Replaced N/A 01-309,01-315,01-217 4160127 SW SW-CV-19CV-SPARE N/A 3

NPPD N/A Repair by adding lugs B31.1-1967 1969 Repaired N/A N/A 4160286 SW SW-Pipe N/A 3

NPPD N/A Repair Tee, Replace pipe flange, B31.1-1967 1969

Repaired, N/A 01-111, N-416-1 reducer, and pipe Replaced 4160511 RHR RHR-MOV-MO38A N/A 2

Anchor Darling N/A Repair by removing tack weld B31.1-1967 1969 Repaired N/A 01-281 4160517 SW SW-V-145 N/A 3

POSI-SEAl INTL.

N/A Replace Valve B31.1-1967 1969 Replaced N/A 01-158 4160573 REC REC-MOV-713MV N/A 3

Henry Pratt Co.

N/A Replaced valve with a new valve B31.1-1967 1969 Replaced N/A 99-257 4160574 REC REC-MOV-712MV N/A 3

Henry Pratt Co.

N/A Replaced valve with a new valve B31.1-1967 1969 Replaced N/A 99-256 4160595 REC REC-V-181 N/A 3

Edward - Vogt N/A Replace Valve and fittings B31.1-1967 1969 Replaced N/A 00-276 4160626 REC REC-V-18 N/A 3

Henry Pratt N/A Replaced valve B31.1-1967 1969 Replaced N/A 99-253 4160627 REC REC-V-19 N/A 3

Henry Pratt N/A Replaced valve B31.1-1967 1969 Replaced N/A 99-252 4160631 REC REC-V-20 N/A 3

NOVA Machine N/A Replaced flange to body bolting B31.1-1967 1969 Replaced N/A 99-254 4160631 REC REC-V-20 N/A 3

Henry Pratt N/A Replaced valve B31.1-1967 1969 Replaced N/A 99-254 4160632 REC REC-V-21 N/A 3

Henry Pratt N/A Replaced valve B31.1-1967 1969 Replaced N/A 99-255 4163338 SW SW-P (Part 19127)

N/A 3

Byron Jackson N/A Repair eroded areas by welding B31.1-1967 1969 Repaired N/A N/A Div/Borg Warner 4163338 SW SW-P (Part 10486)

N/A 3

Byron Jackson N/A Weld repair eroded areas and B31.1-1967 1969 Repaired N/A N/A Div/Borg-Wamer machine fits to original dimens.

4163338 SW SW-P (Part 10485)

N/A 3

Byron Jackson N/A Weld repair eroded areas and B31.1-1967 1969 Repaired N/A N/A Div/Borg-Warner machine fits to original dimens.

4163338 SW SW-P (Part 10484)

N/A 3

Byron Jackson N/A Weld repair eroded areas and B31.1-1967 1969 Repaired N/A N/A Div/Borg-Warner machine fits to original dimens.

Page 4 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

CI Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4163338 SW SW-P (Part 10483)

N/A 3

Byron Jackson N/A Weld repair eroded areas and B31.1-1967 1969 Repaired N/A N/A Div/Borg-Warner machine fits to original dimens.

4163678 (2)

RHR RHR-RV-17RV N/A 2

Consolidated N/A Replaced valve & piping B31.1-1967 1969 Replaced N/A 00-123 4163949 (2)

SW SW-MOV-651MV N/A 3

Henry Pratt Co.

N/A Replace the valve & valve disk B31.1-1967 1969 Replaced N/A 00-248 4164382 RHR RH-S65A 8378 2

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4164385 RHR RH-S65B 458 2

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164386 MS VR-S87B 401 1

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164390 MS VR-S81 7019 3

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164391 MS VR-59-7-Z 478 3

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164392 MS SS-C2 447 1

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164393 MS VR-H61D 402 3

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164395 MS VR-S83A 15147 3

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164613 RF RF-S12 17205 3

Pacific Scientific N/A Replaced Snubber B31.l-1967 1969 Replaced N/A N/A 4164617 RHR RH-S6 17204 1

Pacific Scientific N/A Replaced Snubber B31.l-1967 1969 Replaced N/A N/A 4164701 RF RF-S15 470 1

Pacific Scientific N/A Replaced Snubber B31.l-1967 1969 Replaced N/A N/A 4164702 RR SS-1B 6878 1

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164703 MS SS-D2 5299 1

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164704 MS VR-55-23-Z 5320 3

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164706 MS SS-D3 12979 1

Pacific Scientific N/A Replaced Snubber B31.l-1967 1969 Replaced N/A N/A 4164709 MS SS-A2 12983 1

Pacific Scientific N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164710 MS MS-S16B 8101 2

Grinnell N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164716 RHR RH--34 7730 2

Grinnell N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164717 CS CS-S7 10051 2

Grinnell N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164718 RI-IR RH-S59 8132 2

Grinnell N/A Replaced Snubber B31.l-1967 1969 Replaced N/A N/A Page 5 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

CI Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4164738 MC PENT-XIB C4448 MC CB & I N/A Replaced swing bolt & nut ASME 111, 1969 Replaced YES 6.PC.501 1965 Edition w/ W. 67' Add.

4164740 RHR RH-S78B 8079 2

Grinnell N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4164743 MS MS-S7A 7744 2

Grinnell N/A Replaced Snubber B31.1-1967 1969 Replaced N/A N/A 4180095 RHR RHR-MOV-MO16B N/A 2

Anchor Darling N/A Replaced B/B studs/nuts B31.1-1967 1969 Replaced N/A 01-219 4181190 SW SW-PIPING N/A 3

Power Cutting Inc.

N/A Fab Replacement spools B31.1-1967 1969 Replaced N/A 01-267, N-416-1 4181190 SW SW-Piping N/A 3

Power Cutting Inc.

N/A Replaced SW Piping B31.1-1967 1969 Replaced N/A 01-267,N-416-1 4181190 SW SW-Piping Supports N/A 3

Power Cutting Inc.

N/A Remove/Replace pipe supps.

B31.1-1967 1969 Replaced N/A N/A 4183975 RF RF-CV-16CV N/A I

Anchor Darling N/A Replace hinge cover studs B31.1-1967 1969 Replaced N/A 01-605, 6.PC.501 4184038 RCIC RCIC-RD-S240 N/A 2

Black Sivalls &

N/A Replaced rupture disc B31.1-1967 1969 Replaced N/A 01-387 Bryson 4184060 HPCI HPCI-RD-S241 N/A 2

Black Sivalls &

N/A Replaced rupture disc B31.1-1967 1969 Replaced N/A 01-388 Bryson 4184060 HPCI HPCI-RD-S241 N/A 2

NOVA Machine N/A Replaced studs B31.1-1967 1969 Replaced N/A 01-388 4187057 (2)

MS MS-RV-71ARV 376, 376 1

Target Rock N/A Replaced valve body & pilot, &

B31.1-1967 1969 Replaced N/A 6.MISC.502 hex nuts with splined nuts 4189197 CRD CRD-06-23 N/A 1

General Electric N/A Replaced CRD flange & bolts ASME III 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189302 CRD CRD-26-27 N/A 1

General Electric N/A Replaced CRD flange & bolts ASME III 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189306 CRD CRD-14-47 N/A I

General Electric N/A Replaced CRD flange & bolts ASME III 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189309 CRD CRD-18-31 N/A I

General Electric N/A Replaced CRD flange & bolts ASME El1 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189312 CRD CRD-22-03 N/A I

General Electric N/A Replaced CRD flange & bolts ASME II 1969 Replaced N/A 6.MISC.502 1965 Edition, wv/Jan. 66' Add.

Page 6 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

C1 Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4189317 CRD CRD-26-07 N/A 1

General Electric N/A Replaced CRD flange & bolts ASME II 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189342 CRD CRD-26-51 N/A I

General Electric N/A Replaced CRD flange & bolts ASME III 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan 66' Add.

4189345 CRD CRD-30-39 N/A I

General Electric N/A Replaced CRD flange & bolts ASME I 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan 66' Add.

4189347 CRD CRD-34-51 N/A 1

General Electric N/A Replaced CRD flange & bolts ASME I 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189349 CRD CRD-38-19 N/A 1

General Electric N/A Replaced CRD flange & bolts ASME II 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4189356 CRD CRD-50-23 N/A I

General Electric N/A Replaced CRD flange & bolts ASME M 1969 Replaced N/A 6.MISC.502 1965 Edition, w/Jan. 66' Add.

4190074 MS MS-RV-7IBRV 380, 382 1

Target Rock N/A Replaced valve body & pilot B31.1-1967 1969 Replaced N/A 6.MISC.502 4190074 MS MS-RV-7IBRV 380 1

Target Rock Corp.

N/A Replace hex nut with splined nut B31.1-1967 1969 Replaced N/A 6.MISC.502 4190074 MS MS-RV-71BRV 380 1

Target Rock Corp.

N/A Machined inlet flange surfaces B31.1-1967 1969 Repaired N/A 6.MISC.502 4190075 MS MS-RV-7IDRV 378 1

Target Rock N/A Replaced Pilot Assy.

B31.1-1967 1969 Replaced N/A 6.1ISC.502 4190076 MS MS-RV-7IFRV 380 1

Target Rock N/A Replaced Pilot Assy.

B31.1-1967 1969 Replaced N/A 6.MISC.502 4190077 MS MS-RV-71CRV 386 1

Target Rock N/A Replaced Pilot Assy.

B31.1-1967 1969 Replaced N/A 6.MISC.502 4190078 MS MS-RV-71-ERV 383 1

Target Rock N/A Replaced Pilot Assy.

B31.1-1967 1969 Replaced N/A 6.MISC.502 4190079 (2)

MS MS-RV-71HRV 377, 377 1

Target Rock N/A Replaced valve body & pilot, B31.1-1967 1969 Replaced N/A 6.MISC.502

&hex nuts with splined nuts 4190100 MS MS-RV-71GRV 384 1

Target Rock N/A Replaced Pilot Assy.

B31.1-1967 1969 Replaced N/A 6.MISC.502 4195751 (2)

SW SW-P- (Part 01466)

N/A 3

Byron Jackson N/A Replaced top case & drilled B31.1-1967 1969 Replaced N/A N/A holes for wear rings & nuts 4200011 SW SW-P-BPD N/A 3

Byron Jackson N/A Replaced pump, removed and B31.1-1967 1969 Replaced N/A 01-466 1_

_1_replaced pedestal weld Page 7 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

Cl Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4200711 SW SW-MOV-MO89A N/A 3

Control N/A Replaced plug B31.1-1967 1969 Replaced N/A 01-541 Components, Inc.

4200712 SW SW-MOV-MO89B N/A 3

Control N/A Replaced Plug B31.1-1967 1969 Replaced N/A 01-543 Components, Inc.

4200917 RCIC RCIC-V-42 N/A 2

Velan, Anderson-N/A Replaced valve and added new B31.1-1967 1969 Replaced N/A 01-529, 6.PC.519 Greenwood valve 4201301 SW SW-Piping N/A 3

NPPD N/A Replaced elbow B31.1-1967 1969 Replaced N/A 01-517 4202840 SW SW-CV-10CV N/A 3

Atwood & Morrill N/A Replaced Valve B31.1-1967 1969 Replaced N/A 01-511 4202850 RHR RH-S49 394 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4203836 REC REC-weld 2848-2-W36 N/A 3

NPPD N/A Repaired crack by welding B31.1-1967 1969 Repaired N/A 01-546, N-416-1 4205325 SW SW-Piping N/A 3

NPPD N/A Replaced pipe B31.1-1967 1969 Replaced N/A 01-547, N-416-1 4205891 MS VR-S1l 487 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205892 MS VR-S86A 5217 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205982 RHR RH-S16 339 1

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205986 RHR RH-S19 5302 1

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205988 MS VR-S60 5301 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205990 MS VR-S27 345 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205992 MS VR-S12 5323 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205995 RHR R.H-S8B 7003 1

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205997 MS VR-56-24-X 10797 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205998 MS VR-55-26-Z 5310 3

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4205999 MS SS-A3 5319 1

Pacific Scientific N/A Replaced snubber B31.1-1967 1969 Replaced N/A N/A 4207739 SW DG-I Intercooler 3

Thermal Eng.

N/A Replaced intercooler head B31.1-1967 1969 Replaced N/A 01-588 4208434 SW SW-H138 N/A 3

NPPD N/A Replaced pipe support B31.1-1967 1969 Replaced N/A N/A 4208664 SW SW-Piping N/A 3

NPPD N/A Replaced Piping by welding B31.1-1967 1969 Replaced N/A 01-266 4208741 SW SW-$97 N/A 3

Grinnell N/A Replaced end paddle on strut B31.1-1967 1969 Replaced N/A N/A Page 8 of 9

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI Nebraska Public Power District, Cooper Nuclear Station, Unit 1, P.O. Box 98, Brownville, Nebraska 68321 MWR System Name of Mfgr.

CI Name of Nat'l Description of Applicable Year Repaired ASME Pressure Tests Component Serial Manufacturer Board Work Constr. Code Built or Code Conducted, No No.

Replaced Stamp Code Cases 4208973 SW RHR-HX-A 27051 3

Southwestern N/A Installed tube plugs ASME VIII 1969 Replaced YES N/A Engineering Co.

1968 Edition 4209379 SW SW-H196 N/A 3

Power Cutting Inc.

N/A Repair broken welds 13 31.1-1967 1969 Repaired N/A N/A 4210927 SW SW-MOV-651MV N/A 3

Atwood & Morrill N/A Replaced Valve B31.1-1967 1969 Replaced N/A 01-637 4211015

-PCI HPCI-MOV-15MO N/A 1

Anchor Darling N/A Repaired valve body by grinding B31.1-1967 1969 Repaired N/A 6.MISC.502 4211450 SW DG-2 Lft Bnk. Intercooler N/A 3

Perfex N/A Replaced left bank intercooler B31.1-1967 1969 Replaced N/A 01-645 4211549 SW DGLO-HX-LO2 N/A 3

American Std.

N/A Install tube plugs ASIMIE VIII 1969 Replaced YES N/A 1968 Edition 4211551 SW DGJW-HX-JW2 N/A 3

American Std.

N/A Install tube plugs ASME VIII 1969 Replaced YES N/A 1968 Edition 4216375 (2)

SW SW-P-D N/A 3

Byron Jackson N/A Replaced Pump bowl Assy. and B31.1-1967 1969 Replaced N/A N/A bolting at column(s)

P04500020 RIF RF-CV-Discs N/A I

Floserve N/A Repaired new discs by adding B3 1.1 -1967 1969 Replaced N/A N/A 233 hardfacing

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NLS2002040, Inservice Inspection Summary Report for Cooper Nuclear Station

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