NRC 2004-0020, Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R26 and 33rd Year Tendon Surveillance and Concrete Examination

Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R26 and 33rd Year Tendon Surveillance and Concrete Examination

ML040560544
Person / Time
Site:	Point Beach
Issue date:	02/19/2004
From:	Vanmiddlesworth G Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2004-0020
Download: ML040560544 (136)

Text

NMCh Committed to Nuclear Excellence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC February 19, 2004 NRC 2004-0020 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Filing of Owner's Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U2R26 and 33rd Year Tendon Surveillance and Concrete Examination Nuclear Management Company, LLC, (NMC) is submitting Inservice Inspection Summary Reports for inspections conducted prior to and during the Point Beach Nuclear Plant (PBNP) refueling outage U2R26 that concluded on November 21, 2003.

The enclosed Class 1 and 2 report is submitted pursuant to the requirements of subarticle IWA-6240 of the 1998 Edition with addenda through 2000 of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

The IWE Class MC and IWL Class CC reports are submitted pursuant to the requirements of subarticle IWA-6240 of the 1992 Edition with addenda through 1992 of ASME Section Xl.

The enclosed summary report includes Form NIS-1, the Owner's Report for Inservice Inspections, and Form NIS-2, the Owner's Reports for Repair/Replacement Activities.

These reports include the first outage of the first period of the fourth ten-year interval for Class 1 and 2 systems, the second outage of the second period of the first ten-year interval for Class MC at PBNP Unit 2, and the 33rd year concrete and tendon surveillances of Class CC components for both PBNP units.

Gary Van Middlesworth Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosures 6590 Nuclear Road

• Two Rivers, Wisconsin 54241 Telephone: 920.755.2321

Document Control Desk Page 2 cc (with enclosures):

Administrator, Region 111, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW Mike Verhagen, State of Wisconsin

NIS-1 Inservice Inspection Summary Report for U2R26 Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 2 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Service Date: October 1, 1972 USNRC Docket Number: Unit 2: 50-301 Report Date: February 11, 2004

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company LLC 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 2

4. Owner Certificate of Authorization: N/A

5. Commercial Service Date: October 1, 1972

6. National Board Number for Unit: N/A

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

Reactor Pressure Combustion 69101 U009973 NB-21009 Vessel Engineering Regenerative Heat NB-0361 Exchanger Sentry 3996A3-7 N/A NB-0362

_____ _____ _____N B -03 63 Steam Generator B Westinghouse SG2L-12173 U009975 NB-0060 Accumulator T-34A Delta Southern Co. 41036-69-1 U009976 N/A Accumulator T-34B Delta Southern Co. 41036-69-2 U009977 N/A Class 1 Piping Westinghouse/ N/A N/A N/A Class____2__Piping __ Bechtel Class 2 Piping Westinghouse/ N/A N/A N/A

_ _ _ _ _ _ I__ B echtel _ _ __ _ _ _I__ _ _ I__

8. Examination Dates: July 1, 2002 to November 21, 2003

9. Inspection Period Identification: First Period from July 1, 2002 to June 30, 2005

10. Inspection Interval Identification: Fourth Interval from July 1, 2002 to June 30, 2012

11. Applicable Editions of Section XI: 1998 Edition, 2000 Addenda

12. Date/Revision of Inspection Plan: May 29, 2003, revision 1 Page 1 of 5

Nuclear Management Company LLC Commercial Service Date: 10/in2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A

13. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for the Inspection Plan:

An Inservice Examination of selected Class 1 and 2 components and piping systems of Nuclear Management Company's (NMC) Point Beach Nuclear Plant (PBNP) Unit 2 was performed during the time period of July 1,2002 to November 21, 2003, which included the Unit 2 Refueling Outage 26 (U2R26). This was the first outage of the first period of the fourth ten-year interval.

The components and piping systems examined were selected in accordance with the Fourth Ten Year Inservice Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1998 Edition with addenda through 2000, and applicable relief requests. In addition, augmented examinations were performed on the Safety Injection Accumulators and Reactor Pressure Vessel in accordance with various commitments.

Snubber functional testing and visual examinations were conducted in accordance with the OM Code, 1987 Edition with OMa-1988. We Energies, NMC, and Lambert, MaGill, Thomas Inc.

(LMT) personnel performed the examinations. See Attachment 2 for test results and the ISI Examination Tables for examination results of Section XI classified snubbers.

Manual ultrasonic, visual, radiographic, and liquid penetrant non-destructive techniques were used to examine components, piping, and their supports. We Energies and NMC personnel supported by examiners supplied by LMT, Inc. and Professional Welding Associates (PWA), performed the examinations. See Attachment 3 for the listing on Class I and 2 components examined.

System pressure testing was conducted by the plant to ASME Section XI and applicable plant procedures. We Energies, NMC, LMT, and PWA personnel performed the examinations. Minor leakage was noted at mechanical connections. See the attached tables for a summary of examinations.

Repairs and replacements were performed on Class 1 and 2 Section XI components since the previous outage. The NIS-2 reports are included with this report. NIS-2 reports are also filed at the plant in the permanent record system.

The following Code Cases were used during the reporting period and the U2R26 outage:

Code Case Title N-460 Alternate Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1 N-498-4 Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 1, 2, and 3 Systems,Section XI, Division 1 N-522 Pressure Testing of Containment Penetration Piping,Section XI, Division 1 N-566-1 Corrective Action for Leakage Identified at Bolted Connections N-623 Deferral of Inspections of Shell-to-Flange and Head to Flange Welds of a Reactor Vessel Page 2 of 5

Nuclear Management Company LLC Commercial Service Date: 10/o172 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A

14. Abstract of Results of Examinations and Tests:

See Attachment 1 for numbers and percentages of examinations or tests completed.

Every indication noted was accepted as-is by evaluation. However, most indications were addressed by Work Orders to return the component to its design configuration where needed.

For leakage at mechanical connections, Work Orders were initiated to correct the leakage. On valve stem leakage, operations or engineering personnel adjusted the packing so leakage was stopped or slowed down to an acceptable limit. Leakage collection systems were operational in each case.

Class I Systems Reactor Pressure Vessel Visual examinations were performed on various portions of the RPV, including the vessel, upper head, and closure head bolting. Remote ultrasonic examinations were performed on the CRDM tubes. Direct and remote bare metal visual examinations were performed on the upper and lower head penetrations to detect evidence of leakage. No reportable indications were noted.

The interior of the reactor vessel was examined using remote visual equipment on accessible areas to the extent practical. No relevant indications were noted.

Pressurizer Visual examinations were performed on the manway bolting. Eight of the bolts exhibited evidence of minor corrosion, nicks, and gouges. All were replaced as a conservative measure.

Auxiliary Coolant Volumetric examinations were performed on selected auxiliary coolant welds. No indications were noted.

Reactor Coolant Volumetric examinations were performed on selected reactor coolant welds. No indications were noted.

Visual and surface examinations were performed on supports and welded attachments. One support was noted as being in contact with scaffold. When the scaffold was removed, the support was acceptable. Another spring support was found to contain debris and the load plates were missing. An evaluation showed the load to be correct and the debris was a housekeeping issue. It was determined the debris would not interfere with the function of the support.

Safety Injection Volumetric examinations were performed on selected Safety Injection welds. No indications were noted.

Page 3 of 5

Nuclear Management Company LLC Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A Visual and surface examinations were performed on supports and welded attachments. No indications were noted.

Three welds were removed from service in order to replace a valve. Three new welds were installed and preservice examinations were performed with no indications noted.

Charging System Visual examinations were performed on supports. No indications were noted.

Chemical Volume Control System Visual examinations were performed on supports. No indications were noted.

Surface examinations were performed on select welds. No indications were noted.

Pressure Tests The Reactor Coolant system leakage test and other Class I pressure tests were conducted.

These tests met the requirements for periodic pressure testing. Evidence of leakage was noted at several mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.

Class 2 Steam Generator One snubber was examined. It was noted that several bolts had inadequate thread engagement. This was accepted as-is by engineering evaluation.

Main Steam System Visual examinations were performed on selected supports. No indications were noted.

Auxiliary Feedwater A direct visual examination was performed on the inside surface of one weld. This examination revealed a linear indication. After removing the piping for additional access, minor surface conditioning was performed. The indication was found to be a normal part of the weld root, which is an acceptable condition. Baseline examinations were performed on the new weld.

Pressure Tests Pressure tests were conducted on Class 2 systems. These tests met the requirements for periodic pressure testing. Evidence of leakage was noted at several mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.

15. Abstract of Corrective Measures.

The auxiliary feedwater weld was investigated further upon detection of the linear indication.

This involved removing the pipe next to the weld and performing a direct visual and liquid penetrant examination, which showed the indication to be a normal part of the weld root.

Page 4 of 5

Nuclear Management Company LLC Commercial Service Date: 101o172 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: NIA During the performance of pressure tests, evidence of leakage was noted at mechanical connections. These were corrected using normal maintenance work procedures.

Several component supports were noted as having a discrepancy with the design drawings.

In each case, these were accepted as-is by engineering evaluation. The indications were either left in place as-is, work orders were written to restore them to their design configuration, or a drawing change was initiated to show the as-built configuration.

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 Authorization No. (if applicable): N/A Expiration Date: N/A Date:  ;//7/7Oo' Signed: Nuclear Management Co. by .2?e,, . v Owner CERTIFICATE OF lNSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by Hartford Steam Boiler of Hartford, Connecticut, have inspected the components described in this Owner's Report during the period July 1, 2002 to November 21, 2003, 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 Owner'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.

Commissions WI 247972 Inspe o s ignature National Board, State, Province, and Endorsements Date A-

, _ ,e-,VM/

Page 5 of 5

Nuclear Management Company LLC Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: NIA Attachment 1 Status of Examinations for the Period/Interval

Nuclear Management Company LLC Commercial Service Date: 1/I /7n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) to Examination Required for Credited for this Credited (%) Date for the Category the Interval Period for the Period Interval Remarks B-A 6 0 0 0 Partial deferral permissible B-B 7 0 0 0 B-D 25 0 0 0 B-F See Remarks Part of Risk-Informed ISI Program, see Category R-A B-G-I 6 [ 17 17 B-G-2 8 3 38 38 B-1 See Remarks Part of Risk-Informed ISI Program, see Category R-A B-K 4 2 50 50 B-L-I 0 0 0 0 Deferred to the end of the interval B-L-2 0 0 0 0 Examined only if disassembled formaintenance, repair, or volumetric examination B-M-1 0 0 0 0 Scheduled for the third interal B-M-2 0 0 0 0 Examinations will be performed when valves are opened B-N-I 3 1 33 33 Accessible portions of the vessel internal surface B-N-2 0 0 0 0 Deferred to the erd of the interval B-N-3 0 0 0 0 Deferred to the end of the interval B-0 2 0 0 0 Deferred to the end of the interval B-P 6 1 17 17 Pressure tests cross class boundaries B-Q 0 0 0 0 Examined in accordance with plant Technical Specifications C-A 6 0 0 0 _______________________________

C-B 7 0 0 0 C-C 12 0 0 0 C-D 0 0 0 0 There are no class 2 bolts greater than 2" at PBNP C-F-I See Remarks Part of Risk-Informed ISI Program, see Category R-A C-F-2 See Remarks Part of Risk-Informed ISI Program, see Category R-A C-G I 0 0 0 Scheduled for the third interal C-l _Pressure I tests cross class boundaries F-A 125 10 8 8 Class I and 2 component supports R-A137 19 14 14 Risk-informed welds, includes class I and 2 piping welds Note: all numbers rounded to the nearest 1%.

Nuclear Management Company LLC Commercial Service Date: 10/in72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A Attachment 2 Snubber Functional Testing The following snubbers were functionally tested:

Snubber System Manufacturer Code Results-Date Number Class HS-26 SI Grinnell I SAT - 10/8/2003 HS-27 RC Grinnell I SAT - 10/8/2003 HS-36 MS Ankor-Holth 2 SAT - 10/5/2003

Nuclear Management Company LLC Commercial Service Date: 10/17n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A Attachment 3 Class 1 and 2 Examination Tables

Nuclear Management Company LLC Commercial Service Date: 10/1 72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit2 National Board Number for Unit: N/A Examination Results Guide DATE: 2/16/04 POINT BEACH NUCLEAR PLANT UNIT 2 PAGE: 00 (A) INSERVICE INSPECTION RESULTS

SUMMARY

(C)

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBR COMPONENTS (B)

Reactor Pressure Vessel (D)

N I 0

-STATUS G N G T R S E H Remarks

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET C G M R WO Number System ID - R-1, Drawing No. ISI-1101 (E) 001000 RPV-14-683 (G) (J) B-A C UT 5 168-0001 - - - X 9/19/2003 - UT complete.

(F) Shell to Flange (H) (K) B1.21 (L) UT 11 168-0001 - - - X Geometric Reflectors from UT 18 168-0001 - - - X the flange radius.

(M) (N) (P)

WO 0213402 (R)

(A) Date the report table was printed (B) Specific outage and report information (Note: Class "P" components are for pressure tests. Many of the systems cross class boundary's, requiring a multiple class designation.)

(C) Page number (D) System description (E) System / ISI drawing number (F) Summary number of the record (unique, for computer tracking only)

(G) Component or Component Support identification (H) Component or Component Support Description (J) ASME Code category (K) ASME Code item number (L) Shows status of examination P - Partial examination A - Augmented examination C - Code completed, greater than 90% coverage L - Limited code complete, less than or equal to 90% coverage E - Expanded (additional) sample examination B - Baseline (Preservice exam)

R - Removed from service O - Other examination N - No examination If no Code, this is for information only (Other codes may be used as necessary)

(M) NDE methods (N) Data sheet number (P) Types of indications found (R) Remarks and Work Order Number

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 1 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Reactor Pressure Vessel STATUS N I 0 0 NO T R SE H

SUMMARY

EXAMINATION AREA CATOY EXAM E IG E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # CO M R WO NUMBER System ID - N/A, Drawing No. ISI-2101 003900 RPV Interior Surface B-N-1 L VT-3 756-0001 X - - - 10/16/2003 - VT-3 performed, no Vessel Interior B13.10 recordable indications. Examined Surfaces upper internals and accessible areas of the core barrel. No examination of interior areas due to core barrel in place and flange guard installed.

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 2 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Reactor Pressure Vessel Closure Head N I 0 STATUS O N S T R S E H

SUMMARY

EXAMINATION AREA CATOY EXAM E I O E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - R-1, Drawing No. ISI-2103 004500 RPV Closure Head Studs B-S-1 P UT 0 169-0001 X - - - 10/3/2003 - UT performed, no Studs 1 thru 48 B6.30 recordable indications. Examined studs 1 through 16.

WO 0212617 004600 RPV Closure Head Nuts B-O-1 P VT-i 750-0002 X - - X 10/12/2003 - VT-1 performed, no Nuts 1 thru 48 B6.10 recordable indications. Examined nuts 1 throught 16.

WO 0212616 004700 RPV Closure Head B-G-1 P VT-1 750-0003 X - - - 10/12/2003 - VT-1 performed, no Washers B6.50 recordable indications. Examined Washers 1 thru 48 washers 1 through 16.

WO 0212618

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 3 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Pressurizer I 0 STATUS N 0 N U T R S E H

SUMMARY

EXAMINATION AREA CATOY EXAM E I O E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C 0 M R WO NUMBER System ID - T-001, Drawing No. ISI-2104 005000 PZR Manway Bolts B-U-2 C VT-1 750-0001 - - - x 10/10/2003 - VT-1 performed, bolts Bolts 1 thru 16 B7.20 IDR 2003-004 1, 2, 4, 6, 8, 11, 15, and 16 had no VT-i 750-0110 x - - -

recordable indications. Bolts 3, 5, 7, 9, 10, 12, 13, 14 contained various indications with the appearance of corrosion or mechanical damage. Bolting was replaced as good measure.

10/24/2003 - Baseline VT-1 performed on new bolting.

WO 0213387

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 4 1NSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Safety Injection Loop B Injection STATUS N I 0 O N G T R S E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I O E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - Pipe SI 2501R-01, Drawing No. ISI-2124 036700 AC-10-SI-2001-12 R-A C THICK 109 -0011 10/16/2003 - UT performed, no Pipe to Elbow R1.20 UT OL 109-0011 X - - - recordable indications.

UT 45 173-0001 X - - -

WO 0213389 036800 AC-10-SI-2001-13 R-A C THICK 109-0012 - - - - 10/16/2003 - UT performed, no Elbow to Pipe R1.20 UT OL 109-0012 X - - - recordable indications.

UT 45 173-0002 X - - - WO 0213389 037100 AC-10-SI-2001-14 R-A C THICK 109-0013 - - - - 10/16/2003 - UT performed, no Pipe to Tee R1.20 UT OL 109-0013 X - - - recordable indications. Limited UT 45 173-0003 X - - - examination due to tee configuration limiting access.

WO 0213389 037200 AC-10-SI-2001-15 R-A C THICK 109-0014 - - - - 10/16/2003 - UT performed, no Tee to Pipe R1.20 UT OL 109-0014 X - - - recordable indications. Limited UT 45 173-0004 Xexamination due to tee configuration limiting access.

WO 0213389 037600 AC-10-SI-2001-17 R-A L THICK 109-0015 - - - - 10/16/2003 - UT performed, no Elbow to Valve Rl.ll UT OL 109-0015 X - - - recordable indications. Limited 2SI-867B UT 45 173-0005 X examination due to valve configuration limiting access.

WO 0213389

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 5 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Residual Heat Removal to Loop B STATUS NI 0 0 N G T R S E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - SI-2501R-02, Drawing No. ISI-2125 040500 SIS-10-SI-2002-11 R-A C THICK 109-0010 - - - - 10/16/2003 - UT performed, no Pipe to Tee R1.20 UT OL 109-0010 X - - - recordable indications. Limited UT 45 173-0006 X - - - examination due to tee configuration.

WO 0213389

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 6 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Reactor Vessel Injection STATUS 0 NI T R S E H

SUMMARY

EXAMINATION AREA CATOY EXAM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - SI-2501R-05, Drawing No. ISI-2128 046300 SI-2501R-5-2SI-13 F-A C VT-3 754-0004 X - - - 10/06/2003 - VT-3 performed, no Rigid Support F1.10B recordable indications.

WO 0213390 046400 SI-2501R-5-2SI-13-IWA B-K C PT 451-0017 X - - - 10/16/2003 - PT performed, no Welded Attachment B10.20 recordable indications.

WO 0213390

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 7 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS I PACLEBRN COMPONENTS Pressurizer Relief to PORV's STATUS 0 N G T R S E H

SUMMARY

EXAMINATION AREA CATOY EXAM E I 0 E REMARXS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - RC-2501R-02, Drawing No. ISI-2137 078300 HS-2501R-43 F-A C VT-3 2-PT-SS-1 - - - X 10/15/2003 - VT-3 performed for Snubber F1.10S IDR 2003-0007 - - - - snubber program. Snubber was found CAP 051296 to be in a cold position outside the normal specifications. Accepted as-is by evaluation as the snubber would perform its intended function.

WO 0208938

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 8 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Loop A RTD Bypass STATUS N 0 0 N O T R SE H

SUMMARY

EXAMINATION AREA CATOY EXAM E I 0E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G MR WO NUMBER System ID - Pipe RC 2501R-14, Drawing No. ISI-2138 084700 RC-03-BP-2001-06 R-A C THICK 109-0006 10/10/2003 - UT performed, no R1.20 UT OL 109-0006 X - - -

recordable indications.

Pipe to Elbow x - - -

UT 45 173-0008 x - - -

WO 0213391 UT 70 173-0008 X - - -

084800 RC-03-BP-2001-07 R-A C THICK 109-0007 - - - - 10/10/2003 - UT performed, no Elbow to Pipe R1.20 UT OL 109-0007 X - - - recordable indications.

UT 45 173-0009 X - - - WO 0213391 UT 70 173-0009 X - - -

084900 RC-03-BP-2001-08 R-A C THICK 109-0008 - - - - 10/10/2003 - UT performed, no Pipe to Elbow R1.20 UT OL 109-0008 X - - - recordable indications.

UT 45 173-0010 X - - - WO 0213391 UT 70 173-0010 X - - -

085000 RC-03-BP-2001-09 R-A C THICK 109-0009 - - - - 10/10/2003 - UT performed, no Elbow to Pipe R1.20 UT OL 109-0009 X - - - recordable indications.

UT 45 173-0011 X - - - WO 0213391 UT 70 173-0011 X - - -

085200 RC-2501R-14-2H2 F-A C VT-3 754-0018 - - - X 10/15/2003 - VT-3 performed, spring Dual Spring Hanger Fl.lOC IDR 2003-0009 - - - - can indicator is in contact with 2"x2" tube steel which is used to support lead blankets; spring can has moderate corrosion inside can housing and light corrosion on spring and upper portion of rod.

The tube is part of the scaffold and was removed. The corrosion was accepted as-is by evaluation.

WO 0213392 085300 RC-2501R-14-2H2-IWA B-K C PT 451-0020 X - - - 10/16/2003 - PT performed, no Welded Attachment B10.20 recordable indications.

WO 0213393

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 9 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Loop B RTD Bypass STATUS N I 0 O N G T R S E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - Pipe RC 2501R-14, Drawing No. ISI-2139 090700 RC-03-BP-2002-06 R-A C THICK 109 0001 10/06/2003 - UT performed, no Pipe to Elbow R1.20 UT OL 109-0001 X - - - recordable indications.

UT 45 173 -0012 X - - -

NO 0213393 UT 60 173 -0012 X - - -

090800 RC-03-BP-2002-07 R-A C THICK 109-0002 - - - - 10/6/2003 - UT performed, no Elbow to Pipe R1.20 UT OL 109-0002 X - - - recordable indications.

UT 45 173-0013 X - - - HO 0213393 UT 70 173-0013 X - - -

090900 RC-03-BP-2002-08 R-A C THICK 109-0003 - - - - 10/6/2003 - UT performed, no Pipe to Elbow R1.20 UT OL 109-0003 X - - - recordable indications.

UT 45 173-0014 X - - - WO 0213393 UT 70 173-0014 X - - -

091000 RC-03-BP-2002-09 R-A C THICK 109-0004 - - - - 10/3/2003 - UT performed, no Elbow to Pipe R1.20 UT OL 109-0004 X - - - recordable indications.

UT 45 173-0015 X - - - WO 0213393 UT 70 173-0015 X - - -

091200 RC-2501R-14-2H1 F-A B VT-3 754-0017 - - - X 10/17/2003 - Baseline VT-3 Dual Spring Hanger F1.10C IDR 2003-0010 - - - - performed, debris noted inside spring can and no load plates on either spring can. Accepted as-is by evaluation.

WO 0206026

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 10 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Reactor Coolant Pump A Seal Injection STATUS N I 0 O NG T R SE H

SUMMARY

EXAMINATION AREA CATGY EXAM E IO E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C GM R WO NUMBER System ID - Pipe CH 2501R-01, Drawing No. ISI-PRI-2146 118000 24-PH P-A C VT-3 7S4-0003 X - - - 10/6/2003 - VT-3 performed, no Spring Hanger Fl.lOC recordable indications.

WO 0213394

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 11 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Reactor Coolant Pump B Seal Injection STATUS N I 0 0 NG T RS E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I0 E REMARRS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C GM R WO NUMBER System ID - Pipe CH 2501R-01, Drawing No. ISI-PRI-2148 122800 CVC-02-PSI-2002-21-FB B-0-2 C VT-1 750-0007 X 10/17/2003 - VT-1 performed, no Flange Bolting B7.50 recordable indications. Examined bolts in place under tension.

WO 0213395 123300 CVC-02-PSI-2002-25 R-A C PT 451-0001 X - - - 10/17/2003 - PT performed, no Pipe to Elbow R1.20 recordable indications.

WO 0213397 123400 CVC-02-PSI-2002-26 R-A C PT 451-0002 X - - - 10/17/2003 - PT performed, no Elbow to Pipe R1.20 recordable indications.

WO 0213397 123500 CVC-02-PSI-2002-27 R-A C PT 451-0003 X - - - 10/17/2003 - PT performed, no Pipe to Tee R1.20 recordable indications.

WO 0213397 124100 CVC-02-PSI-2002-30-FB B-G-2 C VT-1 750-0006 X - - - 10/24/2003 - VT-1 performed, no Flange Bolting B7.50 recordable indications. Exained in place under tension.

WO 0213395

~~~~~~~~~~~~~~~~~~~...............................

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 12 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Cold Leg Injection Loop A STATUS N I 0 0 N G T R SE H

SUMMARY

EXAMINATION AREA CATGY EXXM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C SM R WO NUMBER System ID - Pipe SI 2501R-06, Drawing No. ISI-2149 125150 SIS-02-SI-2004-07A R-A R 10/12/2003 - Weld removed from Valve 2SI-845A to Pipe R1.20 service due to replacement of valve 2SI-845A.

WO 0206562 125160 SIS-02-SI-2004-07B R-A B PT 450816 X - - - 10/12/2003 - Baseline PT performed, Valve 2SI-845A to Pipe TBD no recordable indications. New weld due to replacement of valve 25I-845A. Shown as weld SW-2 on data sheet.

WO 0206562 125250 SIS-02-SI-2004-08B R-A R 10/12/2003 - Weld removed from Pipe to Coupling R1.20 service due to replacement of valve 25I-845A.

WO 0206562 125260 SIS-02-SI-2004-08C R-A B PT 450844 X - - - 10/9/2003 - Baseline PT performed, Pipe to Coupling TBD no recordable indications. New weld added to database due to replacement of valve 25I-845A. Shown as weld FW-6 on data sheet.

WO 020656 126200 2SI-878D-6 F-A C VT-3 754-0002 - - - X 10/04/03 - VT-3 performed, gaps Rigid Support F1.1OB IDR 2003-002 - - - - found between base plate and wall.

Accepted as-is by evaluation.

WO 0213398 System ID - Pipe SI 2501R-06, Drawing No. ISI-2150 128000 2SI-878D-10 F-A C VT-3 754-0009 X - - - 10/6/2003 - VT-3 performed, no Rigid Support F1.1OB recordable indications.

WO 0213399

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 13 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Letdown from Loop B Cold Leg STATUS N I 0 O NO T R SE H

SUMMARY

EXAMINATION AREA CATGY E I0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C GM R WO NUMBER System ID - Pipe RC 2501R-10, Drawing No. ISI-2152 134500 RC-2501R-10-21PS F-A C VT-3 754-0005 X - - - 10/6/2003 - VT-3 performed, no Pipe Support F1.10B recordable indications.

WO 0213382 134700 29-PRE F-A B VT-3 754-0006 - - - X 10/06/03 - Baseline VT-3 performed, Spring Hanger F1.10C IDR 2003-003 - - - - missing bolt on upper base plate, spring can out of plumb, lateral support skewed, lack of full thread engagement bolts 1 and 2, and missing nut on bolts 1 and 2.

Accepted as-is during prevous outage evaluation.

WO 0213382

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 14 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 1 PACLEBRN COMPONENTS Excess Letdown to Chemical and Volume Control N I 0 STATUS O N a T R S E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - Pipe RC 2501R-13, Drawing No. ISI-2153 136100 RC-02-DR-2002-02A N Weld does not exist. Verified Pipe to Elbow during U2R26.

WO 0213401 136200 RC-02-DR-2002-02B N Weld does not exist. Verified Elbow to Pipe during U2R26.

WO 0213401 136900 RC-2501R-13-55 F-A B VT-3 754-0010 X - - - 10/14/2003 - Baseline VT-3 Guide F1.10B performed, no recordable indications.

WO 0213401 137200 RC-2501R-13-56 F-A B VT-3 754-0011 X - - - 10/14/2003 - Baseline VT-3 Guide F1.10B performed, no recordable indications.

WO 0213401 137900 RC-2501R-13-S9 F-A B VT-3 754-0012 X - - - 10/14/2003 - Baseline VT-3 Guide F1.10B performed, no recordable indications.

WO 0213401 138300 RC-2501R-13-S10 F-A B VT-3 754-0013 X - - - 10/14/2003 - Baseline VT-3 Guide F1.10B performed, no recordable indications.

WO 0213401

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 15 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS I PACLEBRN COMPONENTS Letdown from Loop B Cold Leg STATUS STAUSNI 0 N 0 0 T

SUMO(ARY EXAMINATION AREA CATGY EXAM FR E S E I 0 E H

REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - Pipe RC 2501R-10, Drawing No. ISI-2158 152000 RC-08-DR-2001-01 R-A L UT 45 173-0016 X - - - 10/9/2003 - UT performed, no Branch Connection to R1.20 UT 60 173-0016 X - - - recordable indications. Limited Pipe ex-aination due to branch connection configuration limiting access.

NO 0213400 152100 RC-08-DR-2001-02 R-A C THICK 109-0005 - - - - 10/8/2003 - UT performed, no Pipe to Reducer R1.20 UT OL 109-0005 X - - - recordable indications.

UT 45 173-0017 X - - - WO 0213400 UT 60 173-0017 X - - -

DATE: 02/11/04 POINT.BEACH NUCLEAR PLANT - UNIT 2 PAGE: 16 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE I (U2R26)

CLASS 2 PACLEBRN COMPONENTS Steam Generators STATUS O NI T C R S E H

SUMMARY

EXAMINATION AREA CATGY EXME I 0 E REMARXS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C 0 M R WO NUMBER System ID - 2HX-1B, Drawing No. ISI-PRI-2201 203600 HS-40 F-A A VT-3 2-PT-SS-1 - - - X 10/6/2003 - Angled bolting noted on Snubber F1.20S CAP 050997 _ - - -

two of 12 locations on support.

IDR 2003-0005 Evaluation performed by civil engineering determined these to be acceptable.

WO 0208938

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 17 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 2 PACLEBRN COMPONENTS Loop B Main Steam Inside Containment STATUS 0 N I T

SUMMARY

EXAMINATION AREA CATOY F ETHO R

E S E I 0 H

E REMARKS NUMBER IDENTIFICATION ITEM NO MEHDDATA SHEET # C 0 M R WO NUMBER System ID - HS-34, Drawing No. ISI-2245 291500 EB-1-HS-34 F-A C VT-3 2-PT-SS-1 - - - x 10/15/2003 - VT-3 performed for Snubber F1.20S IDR 2003-0006 snubber program. Inadequate thread CAP 051062 engagement noted. Accepted as-is by evaluation.

WO 0208938

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 18 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 2 PACLEBRN COMPONENTS Loop B Main Steam Outside Containment STATUS N I 0 0 NG T R SE H

SUMMARY

EXAMINATION AREA CATGY EXAM E I0 E REMARKS NUMBER IDENTIFICATION ITEM NO MESHOD DATA SHEET # C GM R WO NUMBER System ID - Piping EB-01, Drawing No. ISI-2248 308900 EB-1-2HB F-A C VT-3 754-0001 X - - - 10/4/2003 - VT-3 performed, no Rigid Support Fl. 2 0A IDR 2003-001 - - - - recordable indications. Wrong bolting noted on pipe clamp.

Accepted as-is by evaluation. A drawing change has been initiated.

WO 9950783

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 19 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 2 PACLEBRN COMPONENTS Feedwater Loop A STATUS STAUSNI 0 N G 0 T

SUMMARY

EXAMINATION AREA CATGY F EXE R S E I 0 H

E REMARKS NUMhBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C G M R WO NUMBER System ID - EB-09, Drawing No. ISI-2250 321350 FW-16-FW-2001-28BC R-A A VT-1 NDE-750 - - - X 10/21/2003 - VT-1 performed, linear 3" Branch Connection R1.11 PT NDE-451 - - - X indication noted at the weld root.

Examination performed in response to Operating Experience at Kewaunee where cracking was seen on the inside surface of the inner radius section. PT found several rounded indications. All were acceptable.

WO 0305887

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 20 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 2 PACLEBRN COMPONENTS Cold Leg Injection Header STATUS N I 0 O N 0 T R S E H

SUMMARY

EXAMINATION AREA CATGY EXAM E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C O M R WO NUMBER System ID - SI-2501R-06, Drawing No. ISI-2268 394900 SIS-02-SI-2017-09 R 10/12/2003 - Weld removed from Elbow to Pipe service due to replacement of valve 25I-845A.

WO 0206562 394910 SIS-02-SI-2017-09A R-A B PT 450844 X - - - 10/9/2003 - Baseline PT performed, Elbow to Pipe TED no recordable indications. New weld due to replacement of valve 25I-845A. Shown as weld FW-9 on data sheet.

WO 0206562 395100 SIS-02-SI-2017-11 R 10/12/2003 - Weld removed from Elbow to Pipe service due to replacement of valve 2SI-845A.

WO 0206562 395110 SIS-02-SI-2017-llA R-A B PT 450844 X - - - 10/9/2003 - Baseline PT performed, Elbow to Pipe TED no recordable indications. New weld due to replacement of valve 25I-845A. Shown as weld FW-7 on data sheet.

WO 0206562 395300 SIS-02-SI-2017-12A R-A R 10/12/2003 - Weld removed from Pipe to Valve 25S-845A R1.20 service due to replacement of valve 25I-845A.

WO 0206562 395400 SIS-02-SI-2017-12B R-A B PT 450816 X - - - 9/25/2003 - Baseline PT performed, Pipe to Valve 25I-845A TED no recordable indications. New weld due to replacement of valve 25I-845A. Shown as weld SW-1 on data sheet.

WO 0206562

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 21 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS 2 PACLEBRN COMPONENTS Auxiliary Feedwater to Steam Generator A STATUS N I 0 0 NO T R SE H

SUMMARY

EXAMINATION AREA CATOY EXAM E I0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C GM R WO NUMBER System ID - Pipe EB-10, Drawing No. ISI-2281 SH 2 444700 AP-03-AFW-2001-99 R 10/24/2003 - Weld removed from Pipe to Branch service due to removal of pipe to Connection examine inside of Branch Connection weld.

WO 0306491 444800 AF-03-AFW-2001-99A R-A B RT RT-2-NMC REV 2 X - - - 10/23/2003 - Baseline RT performed, Pipe to Branch TBD no recordable indications.

Connection WO 0306491

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 22 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS P PACLEBRN COMPONENTS Pressure Test STATUS N I 0 O N a T R S E H

SUMMARY

EXAMINATION AREA CATOY EXAM E I O E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C a M R WO NUMBER System ID - Auxiliary Feedwater, Drawing No. N/A 700100 2-PT-AF-1 P C VT-2 2-PT-AR-1 - - - X 11/11/2003 - VT-2 performed, leakage Auxiliary Feedwater noted at mechanical connections.

Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208861 System ID - Feedwater System, Drawing No. N/A 700300 2-PT-CS-1 P C VT-2 2-PT-CS-1 X - - - 10/4/2003 - VT-2 complete. No Feedwater (Condensate) recordable indications.

System WO 0208862 System ID - Main Steam, Drawing No. N/A 701100 2-PT-MS-2 P C VT-2 2-PT-MS-2 X - - - 10/4/2003 - VT-2 complete. No Main Steam Inside recordable indications.

Containment WO 0208866 System ID - Residual Heat Removal, Drawing No. N/A 701600 IT-536 P C VT-2 IT-536 - - - X 10/18/2003 - VT-2 performed.

Containment Sump Leakage noted at mechanical connections. Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208868 System ID - Safety Injection, Drawing No. N/A 701700 2-PT-SI-i P C VT-2 2-PT-SI-i - - - X 10/3/2003 - VT-2 complete. Leakage Safety Injection noted at mechanical connections.

Outside Containment Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208869 701800 2-PT-SI-2 P C VT-2 2-PT-SI-2 - - - X 10/24/2003 - VT-2 performed, Safety Injection evidence of leakage noted at Outside Containment mechanical connections. Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208870 System ID - Chemical Volume Control, Drawing No. N/A

DATE: 02/11/04 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 23 INSERVICE INSPECTION RESULTS

SUMMARY

INTERVAL 4, PERIOD 1, OUTAGE 1 (U2R26)

CLASS P PACLEBRN COMPONENTS Pressure Test STATUS N I 0 ON S T R S E H

SUMMARY

EXAMINATION AREA CATSY EXAM E I O E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD DATA SHEET # C a M R WO NUMBER System ID - Chemical Volume Control, Drawing No. N/A 703100 2-PT-CV-1 P C VT-2 2-PT-CV-1 - - - X 11/11/2003 - VT-2 performed, CVCS Inside/Outside evidence of leakage noted at Containment mechanical connections. Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208863 703200 2-PT-CV-2 P C VT-2 2-PT-CV-2 - - - X 11/11/2003 - VT-2 performed, CVCS Outside evidence of leakage noted at Containment mechanical connections. Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0208876 System ID - Reactor Coolant, Drawing No. N/A 705200 2-PT-RCS-1 B-P C VT-2 2-PT-RCS-1 - - - X U2R26 - Performed VT-2 on RCS RCS System Leakage system. Leakage noted at mecahnical Test connections. Accepted as-is by evaluation. These will be corrected under plant procedures.

WO 0216320

UNIT 2 REFUELING 26

SUMMARY

LIST FOR FORM NIS-2

This report includes a listing of Unit 2 NIS-2 reports and a copy of the forms for the time period of May 14, 2002 through November 21, 2003.

RR Activity Component Dated Work Order No.

2002-0037 SI-150IR-2, SI-1501R-3 April 30, 2002 9914721 2002-0113 MS-05958 October 11, 2002 0206087 2002-0114 MS-05959 November 15, 2002 0206088 2002-0115 SI-00870A December 11, 2002 9934409 2003-0025 SI-00871B May 5, 2003 0216629 2003-0027 SI-00845A July 7, 2003 0206562 2003-0031 SI 0301R-03 June 24, 2003 9610973 2003-0035 C-I-DIV June 24, 2003 9926799 2003-0036 C-1-DIV June 24, 2003 9926799 2003-0037 C-2-D1V June 24, 2003 9926780 2003-0038 C-2-D1V June 24, 2003 9926780 2003-0039 SI-00853A September 10, 2003 0215082 2003-0040 SI-00853B September 10, 2003 0215083 2003-0041 SI-00853C September 10, 2003 0215084 2003-0042 SI-00853D September 10, 2003 0215085 2003-0046 CC-00721D July 21, 2003 0202312 2003-0049 Piping EB-01-SP August 8, 2003 0303659 2003-0050 Piping EB-01 SP August 8, 2003 0303684 2003-0053 PS RC 2501R-14-2H1 August 27, 2003 0206026 2003-0055 RH-00715C August 29, 2003 9937799 2003-0057 Piping SI 015IR September 20, 2003 0300621 2003-0058 SI-00854A July 7, 2003 0206562 2003-0059 RC-00434 October 7, 2003 0216385 2003-0060 C-2 outer vent October 10, 2003 9926780 2003-0060-1 C-2 outer vent October 10, 2003 9926780 2003-0061 T-01 Bolting October 10, 2003 9945681 2003-0062 RH-00861C October 11, 2003 0200287 2003-0064 T-013 Immersion Heater B October 15, 2003 0203158 2003-0065 C-2 inner vent October 10, 2003 9926780 2003-0066 RH-00715C August 29, 2003 9937799 2003-0066-1 RH-00715C August 29, 2003 9937799 2003-0067 SI-00871B May 5, 2003 0216629 2003-0068 SI-00851A October 16, 2003 9948308 2003-0070 HX-OO1A October 16, 2003 0200102 2003-0071 AF-00100 October 16, 2003 0200225 2003-0072 RH-00716A October 15, 2003 0216258 2003-0076 T-013 Immersion Heater B October 18, 2003 9917877 2003-0077 Piping EB-9, Piping EB-10 October 19, 2003 0306491 2003-0078 RC-2501R-2-RC15 October 28, 2003 0309658 2003-0079 CPP-56 October 28, 2003 0213485 2003-0083 VNPSE-03212 November 8, 2003 0310051,

_ __ 0310053 Page 2 of 3

Class 3 RR Activities:

RR Activity Component Dated Work Order No.

2001-0078 Piping DB-03 May 31, 2002 9914184 2002-0061 AF-00114 August 2, 2002 0210898 2003-0005 2RO-04003 April 1, 2003 0213452, 0215080 2003-0012 2RO-04003 April 1, 2003 0213452, 0215080 2003-0044 Piping HB-19 December 15, 2003 9946700, 9941615 2003-0063 HX-0015A8 November 19,2003 0301204 2003-0084 Piping HB-19 November 18, 2003 0310113 Page 3 of 3

FORM NIS-2 OWN'NER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9926780 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Bechtel Spec 6118-C-8

5. (a) Applicable Construction Code ASME Sec. 111, 19 65 Edition, 67 Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1992 Edition, 1992 Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached .

7. Description of Work: Replacement of ball valves and weld replacement support plate.

8. Tests Conducted: Hydrostatic El Pneumatic Z Nominal Operating Pressure al Exempt El Other Dl Pressure 66.0 psi Test Temp. Ambient OF

9. Remarks RR 2003-0037, 2003-0038, 2003-0060, 2003-0060-1, Bechtel Spec 6118-C-8; CAP053794 Applicabic Manufactueres Data Reports to be attached.

CERTIFICATE OF CONIPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date z/

Ownecr or Ownets Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 8. 2003 to November 18, 2003, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any varranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer §Aall be liable in any manner for any personal injury or property damage or a loss of any kind ar~is n co cc d with this inspection.

///W~ Commissions WI-247972

'/ Inspctors'Signature National Board, State, Province, and Endorsements Date: / -/Gt 2-16 I PBF-7050 Revision 2 12/02/02 SEM 7..11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9926780 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Bechtel Spec 6118-C-8

5. (a) Applicable Construction Code ASME Section III 19 65 Edition, 67 Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1992 Ed; 1992 Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Namc of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

C-2-D IV W-K-M Valve N/A N/A N/A Unknown Removed No Division of ACF Industries C-2-DIV Trentec Inc. EQD-2-UP- N/A N/A Unknown Installed No 001 C-2-D2V W-K-M Valve N/A N/A N/A Unknown Removed No Division of ACF Industries C-2-D2V Trentec Inc. EQD-2-DN- N/A N/A Unknown Installed No 004 C-2 Pittsburgh Des NIA N/A N/A Unknown Corrected No Moines Steel Co.

PBF-7050a Revision2 12/02/02 SEN 7.1 1.1

FORMI NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMIENT ACTIT11'1' As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date August 2, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0210898 Rcpair/Rcplacemcnt Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Auxiliary Feedwater ANSI Spec B16.5; West 676241

5. (a) Applicable Construction Code B31.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Rcmoved or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

AF-00 114 Rockwell Mfg. N/A NIA AF-1 14 Unknown Corrected No Co.

7. Description of Work: Buffed out linear indication on valve body.

8. Tests Conducted: Hydrostatic a Pneumatic Ea Nonninal Operating Pressure El Exempt ED Other E Pressure psi Test Temp. OF

9. Remarks RR 2002-0061 Applicable Manufacturer's Data Reports to be attached.

CERTIFICATE OF CONMPLIANCE I certify that the statements made in the report are correct and that this conformns to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed .;i ,2- - G o ISI Coordinator Date 112 /041 7 Owner or Owncers Dcsintee, Title I

- CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period Julv 29. 2002 to August 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

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

>,/ /. 4 Commissions WI-100128 Inspector's Sigsaturc National Board, State, Province. and Endorsements Date: %T4A) ' P7Z z:3 PBF-7050 Revision 2 12/02102 SENM 7.1 1.1

FORMN NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date May 31, 2002 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9914184 Repair Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A

4. Identification of Systemr Auxiliary Feedwater Bechtel Spec 6118-M-78

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No. Identification Built Replacement (Yes or No)

Piping DB-03 Unknown I N/A N/A NA Unknown- Repair No

7. Description of Work: Repaired to increase the size of the welds to meet Code requirements and improve resistance to vibration fatigue.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure a Other S Pressure _ _ psi Test Temp. _F None

9. Remarks RRM 2001-0078, CAP 028877, See RRM 2002-0061 WO 0210898 Applicable Manufacturees Data Reports to be attached.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed ISI Coordinator Date , 2AZ Owner or Owners Designee. Title l -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 Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period October 26. 2001 to May 30. 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 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 Ox ner'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.

Commissions WI-100128 Inspector's Sigidture National Board, State, Province, and Endorsements Date: o -

PBF-7050 Revision 1 05/17/02 SE?A 7.11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY Ho, !-cquitv Muoft1 v aulzu taiu Cvi ukut oSkvi;u11 A;

1. Owner Nuclear Management Corporation Date Novemb er 19. 2003 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0301204 Rcpair/Rcplacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Service Water PB-653

5. (a) Applicable Construction Code B31.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrccted, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

HX-0015A8 Unknown N/A N/A Bolting Unknown Removed No bolting HX-0015AS Nova MAchine N/A N/A Bolting Unknovn Installed No bolting Products Corp. I I I

7. Description of Work: Replacement of bolting.

8. Tests Conducted: Hydrostatic El Pneumatic R Nominal Operating Pressure El Exempt El Other Dl Pressure psi Test Temp: OF None Required

9. Remarks RR 2003-0063 Applicable Nlanufacturer's Data Repors to be attacled.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed I __,_7 , , ISI Coordinator Date /2 ///hc?

- Owner or Owner s Dcsignce. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 14. 2003 to November 19. 2003, 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 ASME Code,Section XI.

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

Commissions WI-247972 Inspector's Signature National Board. State, Province, and Endorsemcnts Date: /X-ti/9V3 PBF-7050 Revision 2 12102/02 SEM 7.1 1.1

FORM NIS-2 OWNNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date April 1, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, l 54241 WOs 0213452. 0215080 Rcpair/Replaccment Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Auxiliary Feedwater

5. (a) Applicable Construction Code 131.1. 19 67 Edition, No Addenda, N.o Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases N/A

6. Identification of Components ASME National a Corrcted, CodE Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturcr Serial No. No. Identification Built Installed (Yes or No) 2RO-04003 Byron Jackson N/A N/A RO-4003 Unknown Removed No Pump Div.

2RO-04003 Byron Jackson N/A N/A RO-4003 Unknown Installcd No Pump Div.

7. Description of Work: Replacement of restricting orifice to address plugging issues.

8. Tests Conducted: Hydrostatic El Pneumatic a Nominal Operating Pressure [R Exempt El Other E[ Pressure 1380 psi Test Temp. 46/52 OF

9. Remarks RR 2003-0005, 2003-0012, CAP 032045 Applicable Manufacturers Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed _1Z X.4 _ ISI Coordinator Date 7/,//: 6't) 3 Owner or Owncr's Designee. Title . . . '

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period February 27. 2003 to April 1. 2003, 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 ASMIE Code,Section XI.

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

< :5'. O Commissions W'I-100128 Inspector's Signature National Board. State, Province, and Endorsements Date: .23a Adz; PBF-7050 Revision 2 12/02/02 SENI 7.11.1

FORIM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMTENT ACTINGIT' As Requircd by the Provisions of the ASME Code Section XI

1. Owner Nuclear Managment iCorporation Date December 15. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9946700,9941615 RcpairlRcplacenient Organization P.O. No.. Joh No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Service Water Bechtel 6118-M-78

5. (a) Applicable Construction Code B31.1. 19 67 Edition No Addenda, No Code Case (b) Applicable Edition of Section Xl Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Namc of Manufacturer Board Othe r Removed or Stamped Componcnt Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

Piping HB-19 Unknown N/A N/A Piping Unknown Removed No Piping HB-19 Unknown N/A N/A Piping Unknown I Installed No

7. Description of Work: Replacement carbon steel piping with stainless steel piping.

8. Tests Conducted: Hydrostatic El Pneumatic n Nominal Operating IIressure X Exempt al Other El Pressure 49 psi Test T(-mp. 53 OF

9. Remarks RR 2003-0044 Apnlicable Mhanufacturer's Dta Renorts to be attachcd.

CERTIFICATE OF CONIPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed -i:wo >4 - - /- ISI Coordinator Date 1/-,. ., ./r Owner or Ownet's Desinee. Title / t CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period June 27. 2003 to December 15. 2003. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owrner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty. expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore. neither the Inspector nor his empl shall be liable in any manner for any personal injury or property damage or a loss of any kind arn or o ected with this inspection.

Commissions WI- 247972

'ospcctor's-Stgnature National Board. State. Pro%ince, and Endorsements Date: 1 ZctO/

PIBF.7050 Revision 2 12!102(02' SEN1 ,.11 1.

• . * . .. _ _ of . by s Hat LJA CAc.a~.t eb.L SAc eA my_-n* tel S Sft AS I S *

• As Rcquired by the Provisions oftthe ASMIE Codc Section XI

1. Uwner iNuclear Mvianagement L orporation Vate November 1o, M(U3 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant - -Point Beach Nuclear Plant ' ' - Unit: 2 - -

6610 Nuclear Road, Two Rivers, WI 54241 WO 0310113 Rcpair/Replaccment Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Service Water Spec M-78; Design Guide DG-NM03

5. (a) Applicable Construction Code 331.1. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASIME National Corrected, Code Name of Name of Manufacturer Board Other Ycar Removed or Stamped Component Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

Piping HB-19 Unknown N/A N/A piping Unknown Removed No Piping HB-19 Energy & Process N/A N/A piping Unknown Installed No I C orp I _ _ _I__ _ _ I__ _ _ I__ _ I__ _ _ _ _ _ _ _

7. Description of Work: Replacement of 2' of piping due to leak.

8. Tests Conducted: Hydrostatic 2 Pneumatic a Nominal Operating Pressure 0 Exempt a Other f Pressure psi Test Temp. OF

9. Remarks RR 2003-00S4 Applicable Manufacturer's Dab Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signedr't-. , ISI Coordinator Date / ., /

O%%i~cr or Ownecr's Des ivicc. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Ownler's Report during the period November 11, 2003 to November 18. 2003, 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 ASME Code,Section XI.

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

AE:P Inspector's Signature Commissions \N'l-247972 National Board. State. Province, and Endorsements Date: __ _ _ _ _ _ _ _ _ _

I'PBF-70i0 Revision 2 12/02/02 SEM 7.It.I

FORMI NIS-2 OWNNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY ()/ A?

-3 A, A&8i AC;

%A 0 I A AC U %$.IuSib UA, .A.. -A.aE.L uuc 3.' lII A%

1. Owner Nuclcar Management Corporation Date November 13, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9610973 RcpaiT/Replacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec. G-676262; Bechtel M-78

5. (a) Applicable Construction Code RaL.L. 19 67 Edition, N/A Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section Xl Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

SI 0301 R-03 Unknown N/A N/A None Unknown Corrected No Support

7. Description of Work: Corrected pipe support to reduce line vibration.

8. Tests Conducted: Hydrostatic a3 Pneumatic ED Nominal Operating Pressure a3 Exempt El Other E Pressure psi Test Temp. OF None required.

9. Remarks RR 2003-0031 Applic3ble Nlanufacturces Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed r Tibi ISI Coordinator Date f7  ;

Owner or 0%net's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned holding a v'alid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period June 24, 2003 to November 13. 2003, 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 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 Ownmer'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 a or ed with this inspection.

Commissions N\'1-247972

'I' -Tn'spec knature National Board, State. Province, and Endorscnients Date: //Wflxz....

PBF-7050 Revision 2 12/02/02 SEM 7.11.1

C ITs sO. Irnrf Vss`%.Tn Bo nrea, nIn rrar .- IT, . r-.S VI-S I'%&%-IL, V VI !IL.

W s A .3 I'V L WA% A 1'JL% A.1 *1J11 .&%.I;, t A "I.' A A A I I As Required by the Provisions of the ASME Codc Section XI I. awnTer iNuclear Imlanagenment Lorporation L)ate LDecemrer lo . 2UUi 700 First Street, Hudson, WI 54016 Sheet: I of I 2; Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9945681 Repair/Replaccment Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WVI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant West 676440 Rev. 5

5. (a) Applicable Construction Code B31.1 /Sec. Ill. 19 68 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National C code Name of Name of Maanufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Bolting Westinghouse Unknown N/A None Unknown Removed No Bolting Nova/Jos Dyson Unknown N/A Nonc Unknown Installed No

& Sons

7. Description of Work: Replacement of bolting.

8. Tests Conducted: Hydrostatic El Pneumatic D Nominal Operating Pressure El Exempt E Other E Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0061 Applicabic Xianufacturcrs Data Rcpons to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ,;v7 *e ISI Coordinator Date

-/ Z ;Z -- fad Owner or Owers Dcsignec. Title 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 10, 2003 to December 16. 2003, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Ovner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arisi !co d wvith this inspection.

~i/

VCommissions W'.-247972 t7 s SW= National Board. State, Province, and Endorsemcents Date:___ ___ _ _

PB3F-7050 Revision 2 12/02/02 SEM 7.11.1

FORMI NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date January 9, 2004 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0306491 Rcpair.tReplacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Condensate System and Auxiliary Feedwater System Bechtel 6118-M-78

5. (a) Applicable Construction Code B31.I. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components National Corrected, Code Name of Namc of Manufacturcr Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Piping EB-9 Unknown N/A N/A N/A Unknown Corrected No Piping EB-10 Unknown N/A NIA N/A Unknown Corrected No

7. Description of Work: Removed and reinstalled piping.

8. Tests Conducted: Hydrostatic EJ Pneumatic El Nominal Operating Pressure 0 Exempt El Other El Pressure psi Test Temp. OF System Leakage Test (2-PT-AF-I)

9. Remarks RR 2003-0077, CAP 052701, CAP 051234 Applicable Manufacture's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISICoordinator Date //, r/7 1/

Owner or Ownces Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 19. 2003 to January 9, 2004, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owrner's Report in accordance with the requirements of ASME Code,Section XI.

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

Signatr Commissions WI-247972

/ inspector's signature National Board, State, Province, and Endorsements Date:___________

PBF-7050 Revision 2 12/02/02 SEM 7.11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMNIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date January 9, 2004 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, Wl 54241 WO 0206562 Repair/Rcplacement Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp NIA name 6610 Nuclear Road Authorization No. N/A TTwo Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spect G-676262, West Spec G-677264, DG-M02

5. (a) Applicable Construction Code B31.1, 19 67 Edition, N/A Addenda, N/ACode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached

7. Description of Work: Replacement of check valve and associated piping.

8. Tests Conducted: Hydrostatic E Pneumatic El Nominal Oi perating Pressure l Exempt El Other a Pressure 2235 psi Test Temp. 535 OF System Leakage Test

9. Remarks RR 03-0058. 2003-0027 Applicable Manufacturer's Dat Rcports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed A: x K,-'~ ISI Coordinator Date

/ ZZ 2 - .7 V -

Owner or Owner's Dcsignce. Tittc 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period July 7. 2003 to January 9. 2004, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his emlloyer l be liable in any manner for any personal injury or property damage or a loss of any kind on cd with this inspection.

Conunissions WI-247972 oSigi ~rc National Board, State, Province, and Endorsements Date:__________

PBF-7050 Revision 2 12/02/02 SENI 7.1 1.1

FORXI NIS-2 OWNN"ER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASMIE Code Section Xi

1. Owner Nuclear Management Corporation Date January 9, 2004 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0206562 Rcpair/Rcplacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec G-676262, West Spec G-677264, DG-M02

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrccted, Code Name of Name of Manufacturcr Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

SI-00S54A Aloyco Inc. Unknown NIA SI-854A Unknown Removed No SI-00854A Aloyco Inc. Unknown N/A SI.854A Unknown Installed No Sl-00S54A Unknown . Unkpown . N/A S1-854A Unknown Removed No Piping Pipng SI-00854A Unknown Unknown NIA SI-854A Unknown Installed No Piping Piping I

I I

I I

I I I I - 1 I PBF-7050a Revision 2 12/02/02 SENI 7.1 1.1

r'AIVI 1ita lo-h v rb a zrrUtjr rieUK VLLrAirjmtLrLML1r.L1I At- P.II II As Required by the Provisions of the AS,%IE Code Section XI

1. Owner Nuclear Management Corporation Date December 16. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0206088 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Main Steam Spec PB-109

5. (a) Applicable Construction Code Section 111 19 80 Edition, W80 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME Nationaled, Code Name of Name of Manufacturer Board Other Ycar Removed or Stamped Component Mlanufacturer Serial No. No. Identification Built Installed (Yes or No)

MS-05959 Copes Vulcan N/A N/A MS-5959 Unknown Removed No Div.

MS-O5959 Copes Vulcan N/A N/A MS-5959 Unknown Installed No Div.

7. Description of Work: Replacement of valve trim.

8. Tests Conducted: Hydrostatic E[ Pneumatic 0 Nominal Operating Pressure E] Exempt E Other 3 Pressure psi Test Temp. OF ORT-54, IT-745

9. Remarks RR 2002-0114, CAP 052961 Applicable iarnurjcturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section Xl.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ,, e ISI Coordinator Date / X7 r I- ; -

Owner or oWners Designec Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period November 15, 2002 to December 16. 2003, 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 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 Ovner's Report. Furthermore, neither the Inspector nor his employI ll be liable in any manner for any personal injury or property damage or a loss of any kind ar ___ed with this inspection.

Commissions WI-247972

,/ spctor's'Signature National Board. State. Province, and Endorscments Date: _ _ _ _ _ _ _ _ _ _

1'BF-7050 Revision 2 12/02!027 SENI 7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMNENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 18,2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0206087 Repair/Replaccment Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Main Steam Spec PB-109

5. (a) Applicable Construction Code SectionI11I 19 80 Edition, W80 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs./Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National C ctodE Namc of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

MS-05958 Copes Vulcan 8120-94532-1 N/A MS-5958 Unknown Removed No Div.

MS-05958 Copes Vulcan 8120-94532-1 1 N/A MS-5958 Unknown Installed No Div. III

7. Description of Work: Replacement of trim assembly.

8. Tests Conducted: Hydrostatic Ea Pneumatic E Nominal Operating Pressure El Exempt El Other 3 Pressure psi Test Temp. OF ORT-54, IT-745

9. Remarks RR 2002-0113, CAP 052731 Applicable ManurtctureT's Daa Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date NIA Signed  ;,;e7>e'e~ >1115 ISI Coordinator Date //

Owner or Owncrs Designee. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 11. 2002 to November 18. 2003, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owvner's Report in accordance with the requirements of 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 Owvner's Report. Furthermore, neither the Inspector norms employe all be liable in any manner for any personal injury or property damage or a loss of any kind arisi r co e ed xxwith this inspection.

Commissions WI-247972

/ o~ Sitture National Board. State. Province, and Endorsements Date:______ ____

PRiF-7050 Revision 2 12/02/02 SEt 0 7.1 1.1

FOR1I NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMNIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date December 16, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0215083 RepairlReplacemcnt Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A namc 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676241

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

SI-00853B Vclan Valve N/A N/A SI-S53B Unknowvn Corrected No

_ _ _ __ _ _ _ _ _ ~Corp._ _ _ _ _ _ _ _ _ _ _ _ _ _

7. Description of Work: Seal welded to prevent boric acid leakage.

8. Tests Conducted: Hydrostatic ED Pneumatic C] Nominal Operating Pressure El Exempt El Other E Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0040 Applicable Manufacturcrs Data Rcports to be atuched.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed 2=;7-q'A- _<

. - IS1 Coordinator Date ,//q"A'r-) 'I Opener or Oncr's Designee Title /

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 10. 2003 to December 16. 2003, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his emplo;r shall be liable in any manner for any personal injury or property damage or a loss of any kind ansi r ryoected with this inspection.

Cornmissions WI-247972 Inspecto ssnaturc National Board, State. Province, and Endorsements Date: /-___- ____

PBF-7050 Rcvision 2 I 02/2!02 SEMR 7.1 1.1

FORIM INIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMNIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date December 16. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0215084 Repair/Replaccment Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Twvo Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676241

5. (a) Applicable Construction Code B31.1. 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASIME National ar Cre Name of Narnc of Mianufacturcr Board Other R'mar reoved or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

SI-00853C Velan Valve N/A N/A Sl-853C Unknown Corrected No Corp.  :

7. Description of Work: Seal welded to prevent boric acid leakage.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure a Exempt E Other El Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0041 Applicable N13nufacturces Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date ,//.,

O0Iieiror Ownie's Desige.Title~

CERTIFICATE OF INSERV'ICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owvner's Report during the period September 10. 2003 to December 16. 2003, and state that to the best of my knoweledge and belief, the Owvner has performed examinations and taken corrective measures described in this Owner's Report in accordance atith the requirements of 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 Ownmer's Report. Furthermore, neither the Inspector nor hemployer s be liable in any manner for any personal injury or property damage or a loss of any kind arisinP %onvted'ith this inspection.

Commissions WI1-247972

/Insp-tors Signature National Board. State, Province, and Endorsemcnts Date: /-/-f-PBF-7050 Revision 2 12/02!02 SENI 7..11.1

FORNM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY' As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date December 16, 2003 700 First Street, Hudson, WI 54016 Sheet: 1 of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WVO 0215085 Rcpair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676241

5. (a) Applicable Construction Code 131.1. 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME Nationaled, Code Name of Name of Manufacturer Board Other Year Removced or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

SI-00553D Velan Valve N/A N/A SI-853D Unknown Corrected No Corp.__ _ _ __ _ _ _

7. Description of Work: Seal welded to prevent boric acid leakage.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other E1 Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0042 Applicable Manufacturer's Data Rcports to be attached.

CERTIFICATE OF COMIPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed  ; , -- ISI Coordinator Date ///e / .'9l

- OA;icrorOwtier's Dcsignce.Title / /

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owiner's Report during the period September 10. 2003 to December 16. 2003, 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 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 Owxner's Report. Furthermore, neither the Inspector nor his employer s be liable in any manner for any personal injury or property damage or a loss of any kind arising fi nne ted ith this inspection.

,&,Dt ,4Commissions WI-247972 sft Signature National Board. State, Province, and Endorsements Date: _ _ _ _ __,

P13F-7050 Revision 2 12/02/02 SEM 7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIREREPLACEMENT ACTIV'ITY As lRcquircd by the Provisions of the ASIME: Code Section Xl I. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WOs 0310051. 0310053 Rcpair/Rcplacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6 610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Purge and Supply Exhaust Heating and Ventillation Bechtel Spec 6118-M-189

5. (a) Applicable Construction Code AWWA C-504-66,19 N/A Edition, None Addenda, None Code Case (b) Applicable Edition of Section Xl Used for Repairs/Replacement Activity 1992 Ed. 1992 Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Ya orce, Cd Name of Name of Manufacturer Board Other Ymear reoved or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached

7. Description of Work: Replace butterfly valves with blank flanges.

8. Tests Conducted: Hydrostatic 01 Pneumatic 0 Nominal Operating Pressure . El Exempt D Other E Pressure 63 psi Test Temp. ambient OF

9. Remarks RR 2003-0083 Applicable Manufacturefs Data Rerns to be attcteCd.

CERTIFICATE OF CO'MPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code, Section Xl.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed (' ] Coordinator Date ISI / ^ ,

V..

OUTICTor Owner's Dcsrgnce. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period November 8. 2003 to November 18. 2003, and state that to the best of my knowledge and belief, the Owvner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code, Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arisi rnni0r c tcied with this inspection.

Iispector'sSignature Commissions WI-247972 National Board, State. Provirce, and Endorsements Date: I> / .,

PfIF-7050 Rcision 2 12102/02 SEM 7..11.1

FORIl NIS-2 OWNER'S REPORT FOR REPAIR;RREPLACEM IENT ACTIVITY (CONTINUATION)

As Required by the Protisions of the ASMtIE Code Section XI I. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WOs 0310051, 0310053 Rcpair/Rcplacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Purge and Supply Exhaust Heating and Ventillation Bechtel Spec 6118-M-189

5. (a) Applicable Construction Code AWWA C-504-66 19 N/A Edition, None Addenda, None Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1992 Ed. 1992 Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components AS ME National Correctcd, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturcr Serial No. No. Identification Built Installed (Yes or No)

VNPSE-03212 Continental 131834 NIA VNPSE-3212 Unknown Removed No and bolting Equipment Company VNPSE-03212 Dubosc National' NA N/A N/A Unknown Installed No blind flange and Energy Services bolting VNPSE-03244 Continental 13 1835 N/A VNPSE-3244 Unknown Removed No and bolting Equipment Company _

VNPSE-03244 Dubose National N/A N/A N/A Unknown Installed No blind flange and Energy Services bolting 4- 1- 4 *1- 4 4 +

4. 1 I .4. 4 4 I I

+ 4 4 4- 4 & 4 1- 4 4 4- 4 4 4 1 4 4- 1 4 4 4 I.

4 4 4 1 4 4-I

_ _I I _ _I PBF-.70SQ0 Rcvisinn 2 12/02102 SEM 7.11 1.

FORMI NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date November 13, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WVO 0216629 Rcpair1Rcplaccment Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676258

5. (a) Applicable Construction Code B31.I/USAS 16.5. 19 67/66 Edition, No Addenda, No Code Case (b) Applicable Edition of Section Xi Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASMIE National Corrected, Code Name of Namc of Manufacturer Board Other Year Removed orStamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached.

7. Description of Work: Seal welded valve and replaced damaged bolting.

8. Tests Conducted: Hydrostatic E Pneumatic El Nominal Operating Pressure El Exempt E Other al Pressure psi Test Temp. - OF None required

9. Remarks RRs 2003-0025, 2003-0067 Applicable Manufacturer's Data Reports to beattached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ,terorOwners_6- ISI Coordinator Date /, 7 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period May 5. 2003 to November 13. 2003, 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 ASME Code,Section XI.

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

.,. *..>/

-' I Commnissions; Wl-247972

/ Inspectoris Signature National Board. State. Province, and Endorsements Date: 1/-

l'BF-7050 Revision 2 12/02/02 SEM 7. 11.1

FORMN NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 13, 2003 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0216629 Repair/Replacement Organization P.O. No., Job No. Bc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676258

5. (a) Applicable Construction Code B31.1 /USAS 16.5 19 67/66 Edition, NIA Addenda, NIA Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Sl-OOS71 B Darling Valve N/A N/A SI-871B Unknown Corrected No and Mfg. Co.

SI-00871 B Unknown N/A N/A Bonnet Studs Unknown Removed No Bonnet Studs S1-0087 1B Nova N/A NIA Bonnet Studs Unknown Installed No Bonnet Studs I- 4- 4 4- 4 1 4- 4- 4- 4 1 4 4 .4. 1 4 4 4 4 + 4 4 4 4 4 1 + I 4- 4 4 4 1 4- 4 4- 4 4 t I I I I I PBF-7050a Revision 2 12102/02 SEM 7.1 t .1

FORI NIS-2 OWNER'S REPORT FOR REPAIRIREPLACENIENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date December 15, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0200225 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Auxiliary Feedwater Bechtel 6118-M-78; DG M03

5. (a) Applicable Construction Code 1331.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

AF-00100 Encrtech 10740 N/A AF-100 Unknown Removed No AF-00100 Encrtcch 10741 N/A AF-100 Unknown Installed No

7. Description of Work: Replacement of checkvalve.

8. Tests Conducted: Hydrostatic a Pneumatic El Nominal Operating Pressure El ExemPt El Other El Pressure

• psi Test Temp. OF None Required

9. Remarks RR 2003-0071 Applicable Manufacturees Data Reports to be attached CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date Owner or Ownxers Dcsignee. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 16. 2003 to December 15. 2003, 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 ASME Code,Section XI.

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

/ , / Commissions WI-247972

/;nspector SigTature National Board, State, Province, and Endorsements Date:___________

PBr-7050 Revision 2 12/02/02 SEEM7.11.1

Ci-in Solutionsfor Today...Standardsfor Tomorrow (714) 528-2301 2950 Birch Street, Brea, CA 92821-6235 FAX (714) 528-0128 Curtiss-Wright Flow Control Corporation Certificate of Conformance Date: July 2, 2003 Customer Purchase Order No. P031538 Customer. Nuclear Management Company, LLC Enertech Project No. 500043 Site: Point Beach Nuclear Plant Enertech certifies that the parts referenced hereon were produced in accordance with the purchase order cited above and that Enertech has on file the required data to substantiate conformance to applicable procurement specifications.

Enertech further certifies that all tests and inspections required by the customers purchase order(s) have been performed and that all items supplied herewith conform to the specified requirements.

P.O. Item No. Part Number Description 001 I PD99532 VALVE, NOZZLE CHECK MODEL: 3"-600 ANSI DRV-Z S/N: 10741 Additional Requirements:

This item is provided in accordance with the Enertech Quality Assurance Manual, Fourth Edition, Rev. 4 dated April 16, 2003.

The above item was returned on Enertech RMA# 3045. The item conforms to the Enertech Seismic Qualification Report PA99540 Rev A. Further, the Item described herein is designed in compliance with the requirements of USAS B31.1.0 - 1967, and ASA B16.5-1961.

NOTE: Supporting documentation, material test reports, etc. have been previously provided.

Stnature David E. Whitaker Name Quality Assurance Engineer Tle Performance of installation and associated service required by a certified Enertech technician.

4268_1

FORNI NIS-2 OWNER'S REPORT FOR REPAIRIREPLACELNIENT ACTIVITY As Required by the Provisions of the AS.NIE Code Section XI

1. Owner Nuclear Management Corporation Date December 15, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

' - 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9937799 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Residual Heat Removal WEST 77264

5. (a) Applicable Construction Code B16.34/B31.1, 19 NA/67 Edition, Unknown/NA Addenda, No/No Code Case (b) Applicable Edition of Section Xl Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASNIE National C ctode Name of Name of Manufacturer Board Other YRar Cemoved or Stamped Component Manufacturer Seral No. No. Identification Built Installed (Yes or No)

RH-00715C Henry Vogt Unknown N/A RH-715C Unknown Removed No Machine Co.

RH-00715C Henry Vogt 2-230216 N/A RH-715C Unknown Installed No Machine Co.

7. Description of Work: Replacement of valve.

8. Tests Conducted: Hydrostatic ED Pneumatic El Nominal Operating Pressure 1 Exempt a Other E Pressure psi Test Temp. NOT OF

9. Remarks RRs 2003-0055, 2003-0066, 2003-0066-1 Applicablc Manufacturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed A -y ISI Coordinator Date //y/.  : ./

Owner or Owner's Des ignee. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 29. 2003 to December 15. 2003, 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 ASME Code,Section XI.

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

Commissions WI'1-247972 rmbpedtor's S'iture National Board. Statc. Province, and Endorsements PBF-7050 Revision 2 12/02/02 SE N1I7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASIME Code Section XI

1. Owner Nuclear Management Corporation Date December 15. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0202312 Rcpair/Replacerncnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Component Cooling Water MR 84-158

5. (a) Applicable Construction Code B31 1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASNIE National - Corrected, Code Name of Name of Manufacturcr Board Other Year Removed or Stamped Component Mtanufacturer Serial No. No. Identification Built Installed (Yes or No)

CC-00721 D Unknown N/A N/A None Unknown Removed No bolting .

CC-00721 D Nova Machine N/A N/A None Unknowvn Installed No bolting Products Corp. I I_

7. Description of Work: Replacement of valve inlet and outlet bolting.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal OperatingPressure El Exempt E Other El Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0046 Applicable Nianuracturer's Data Reports to be attiched.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed -; , ' ISI Coordinator Date {/ / (

Owner or OnerscDesignee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period July 21. 2003 to December 15, 2003, and state that to the best of my knowledge and belief. the Owner has performed examinations and taken corrective measures described in this Owrner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his emplo all be liable in any manner for any personal injury or property damage or a loss of any kind aris o nne ed with this inspection.

Commissions WI-247972 7/-c ctoes Senaturc National Board. State, Province, and Endorsements Date: /-!/3-_ _

PBF-7050 Revision 2 12/02/02 SE NI 7.1 1.1

FORMI NIS-2 O'WNER'S REPORT FOR REPAIR/REPLACEMNIENT ACTIVITY As Required by the Provisions of the ASMNIE Code Section XI

1. Owener Nuclear Management Corporation Date December 16. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610INuclear Road, Two Rivers, WI 54241 WO 0203158 Rcpair/Replacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection Bechtel Spec M-21

5. (a) Applicable Construction Code API 650, 19 65 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National ar Cre Name of Namc of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

T-013 Immersion Chromalox Unknown N/A T-13 Unknown Removed No Heater B T-013 Immersion Chromalox Unknown N/A T- 13 Unknown Installed Yes Heater B

7. Description of Wor~k: Replacement of immersion heater.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure aJ Exempt a Other E Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0064 Applicable Manufacturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASMIE Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ;7r,,, Dc ISI Coordinator Date Z/ 2Z'l

. ~OwNer or Oznefs Ocsipnce. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 15. 2003 to December 16. 2003, and state that to the best of my knowledge and belief, the Owvner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

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

Commissions WI-247972

/ Inspectors STinaturc National Board. State, Province, and Endorsements Date: /-/-i s IPBF-7050 Revision 212/02102 SEM '7.71 1.1

FORNI NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI I. Owner Nuclear Management Corporation Date January 9, 2004 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, Wl 54241 WO 9917877 Repair/Replacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection Bechtel Spec M-21

5. (a) Applicable Construction Code API 650 19 65 Edition, N/A Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

T-013 Immersion Chromalox Unknown No T- 13 Unknown Rcmonoed No Heater B T-O13 Immersion Chromalox Unknown No T- 13 Unknown Installed Yes Heater B

7. Description of Work: Replacement of immersion heater.

8. Tests Conducted: Hydrostatic El Pneumatic E Nominal Operating Pressure El Exempt El Other 2 Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0076, CAP 051021 Applicable Manuracturers Dta Reports to be atuched.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A lSign ISI Coordinator Date / , g /

O0iner or Owncr~s Designee. Titlec CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Ownrer's Report during the period October 18. 2003 to January 9, 2004, 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 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 Ovner'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 or c n cted with this inspection.

Commissions WI-247972 I TipectorA Signature National Board. State. Province, and Endorscments Date: / /4-A @

Plr-7050 Revision 2 12/02.02 SE.Nt 7.1 1.1

FOR I NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0200102 Repair/Replaccmcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WVI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant WEST412A72

5. (a) Applicable Construction Code Section III. 19 86 Edition, N/A Addenda, N/A Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National , Corrccted, Code Name of Name of Manufacturer Board Other \ cr orectmed, Cod Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

HX-OOIA bolting Westinghouse N/A N/A Bolting Unknown Removed No HX-OOIA bolting Wcstinghouse N/A N/A Bolting Unknown Installed No

7. Description of Work: Replaced bolting due to galling.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt El Other El Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0070 Applicabic N13nunacturcr's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed o ISI Coordinator Date / I/ /

• Owner or 0% :tcrs Dcsigncee. Titlc 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 16. 2003 to November 18. 2003, 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 ASME Code,Section XI.

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

I,2J)D 'Commissions WI'-247972 ns' ectorS C snaturs National Board, State, Province, and Endorsements Date: /_-//- .-vcf PBF-7050 Rcvision2 12!0J202 SEM 7..11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY s Riequireu Uy the i'tUv Is IIib Ui mtIC sl L UU ati t ta Al

1. O.ner Nuclear Management Corporation Date November 1C), 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0216258 Repair/Repblcement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec 676241

5. (a) Applicable Construction Code 1331.1, 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section Xl Code Cases

6. Identification of Components ASME Nationalcode Name of Namc of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

RlH-00716A Unknown N/A N/A None Unknown Removed No Bolting RH-00716A Nova N/A N/A None Unknown Installed No Bolting I I I

7. Description of Work: Replaced stud

8. Tests Conducted: Hydrostatic D Pneumatic l Nominal Operating Pressure El Exempt i Other .g,4- Pressure _ psi Test Temp. - OF None required.

9. Remarks RR 2003-0072 Applicablc Manuracturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed _o.A _/ .,- ISI Coordinator Date / ,,

Owner or Owncr's Designec. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 16. 2003 to November 10 2003, 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 ASME Code,Section XI.

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

Commissions WI-247972

/ n!spector's tig~aurc National Board. State. Province, and Endorsements Date: /2-2e- &O; PBF-7050 Revision2 12/02/02 SENt 7.1 1.1

FORNI NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMIENT ACTIVITY As Required by the Provisions of the ASNIE Code Section XI

1. Owner Nuclear Management Corporation Date April 22, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9934409 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West. 676258

5. (a) Applicable Construction Code B311. 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases e4N t

6. Identification of Components ASME National Corrected, Coe Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached Page__ _ _ _ _ _ _ __ _ _ _ __ _ _ _ _

7. Description of Work: Installed seal weld and replaced body-to-bonnet bolts and nuts.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt '

Other E Pressure psi Test Temp. OF None

9. Remarks RR2002-0115 Applicable Manufacturees Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed rid 4 ' ISI Coordinator Date 74Ill Owner or Onmet's Designee. Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period December 11. 2002 to April 22, 2003, 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 ASME Code,Section XI.

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

l / Commissions WI-100128 Inspector's s'gnature National Board, State, Province, and Endorsements Date: S'-2 °3 PBF-7050 Revision 2 12/02/02 SEM 7..11.1

FORMI NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEAIENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date April 22, 2003 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9934409 Repair/Replacernent Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676258

5. (a) Applicable Construction Code B31.1 19 67 Edition, N/A Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

SI-00870A Aloyco 69-R5117 N/A SI-870A Unknown Installed No SI-00870A Unknown. Unknown N/A Bolts Unknown Removed No Bolting SI-00870A Nuts Unknown Unknown N/A Nuts Unknown Removed No SI-00870A Mackson Inc. Unknown N/A Bolts Unknown Installed No Bolting SI-00870A Nuts Mackson Inc. Unknown N/A Nuts Unknown Installed No PBF-7050a Revision 2 12/02/02 SEM 7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASMNIE Code Section Xi

1. Owner Nuclear Management Corporation Date October 23, 2003 700 First Street. Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2

____________6610.Nuclear.RoadTwoRivers,WI 54241 WO 0303659 Repair/Rcplacement Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date NIA address

4. Identification of System: Main Steam Bech. 61 18-M-01 (West 676262)

5. (a) Applicable Construction Code B3 1 1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Ycar f

Name of Namc of Manufacturcr Board Other Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Piping EB-01-SP Unknown None N/A N/A Unknown Corrected No

7. Description of Work: Ensure a rounded radiuson inlet to safety valve MS-2010.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operatin g Pressure El Exempt Et Other El Pressure _psi Test Termp. `F None

9. Remarks RR 2003-0049 AmPicable Mlanuracttrer's Data ReDorts to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASMIE Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed - .. 'o , ISI Coordinator Date A /, / i Owner or O%ner's Designee. Title / /

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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 8. 2003 to October 23. 2003, 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 ASME Code,Section XI.

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

Commissions WI-247972 tixck r's gigSc National Board. State. Province, and Endorsements Date: /° .fO- 60 PBF-7050 Revision 2 12/02/02 S EMs7.1 1.1

FORM NISI2 OWNER'S REPORT FOR REPAIR/REPLACEMIENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date November 6, 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road. Two Rivers, WI 54241 WO 0213485 Rcpair/Replacemcnt Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Containment

5. (a) Applicable Construction Code 'B31.1I 19 67 Edition, N/A Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1992 Ed. 1992 Addenda (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National. CodE Name of Name of Manufacturer Board Other ' ear Removed orStamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

CPP-56 Stud Unknown N'/A NA N/A Unknown Removed No CPP-56 Stud Accutech N/IA N/A N/A 1997 Installed No

7. Description of Work:- Replacement of galled stud.

S. Tests Conducted: Hydrostatic [l Pneumatic C] Nominal Operating Pressure Dl Exempt ,

dther a1 Pressure psi Test Temp. OF None required.

9. Remarks RR 2003-0079 Appticable htanufacturer's Data Reports to beattaeced.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date NIA Signed ISI Coordinator Date ,,

Owner or OA ner's Dsignec. Title (

CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 28, 2003 to November 6. 2003, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind ari m onnected with this inspection.

/g~ tCommissions WI-247972 Inspector's Signature National Board. State. Province. and Endorsements Date: _ /0__-,_C

_ __3 PDIF-7050 Revision 2 12/02/02 SFM 7.12.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY As Required by the Provisions of the ASIME Code Section XI

1. Owner Nuclear Management Corporation Date November 6, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, W1 54241 WO 0300621 Rcpair/Replacement Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date NIA address

4. Identification of System: Safety Injection West G-676262

5. (a) Applicable Construction Code B3 1.1. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASIME National Corrected, Code Name of Name of Manufacturcr Board Other Ycar Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Sce Attached

7. Description of Work: Removed and reinstalled piping and added new coupling.

S. Tests Conducted: Hvdrostatic E] Pneumatic a Nominal Operating Pressure Z Exempt D Other 0VE r4l.4 Pressure_ psi Test Temp. Ambient OF System Leakaoe Test performed

9. Remarks RR 2003-0057 Applicabe hmanufacturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code.

Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ;74, ,t.;  : ISI Coordinator Date // /7 ';

Owner or Owner's Designee, Title 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 30. 2003 to November 6, 2003, 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 ASME Code,Section XI.

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

A&ME Commissions WX'I-247972 Inspector's Signaturc National Board. State, Province. and Endorsements Date: /0- XLU,.

PBF-7050 Revision 2 1202/02E SEMt 7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIRJREPLACEMIENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASNIE Code Section XI

1. Owner Nuclear Management Corporation Date November 6. 2003 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0300621 Repair/Rcplacement Organization P.O. No., Job No. Etc.

3. --Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date NIA address

4. Identification of System: Safety Injection WEST G-676262

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 19!98 Ed. Addenda thru 20,00 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected. Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Piping SI 0151 R Unknown N/A NIA Piping Unknown Removed No Piping SI 0151R Unknown N/A N/A Piping Unknown Installed No Coupling Alloy Stainless N/A N/A N/A Unknown Installed No Products Company Inc.

___- ___= -_ __ __

PBF-7050a Revision 2 12102/02 SEM1 7.1 1.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date October 23, 2003 700 First Street, Hudson, WI 54016 Shlet: I of I -

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Taco Rivers. W'I 54241 WO 0303684 RcpairlRcplacemcnt Oqranization 1'.0. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 66 10 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Main Steam Bech. 61 1S-M-01 (West 676262)

5. (a) Applicable Construction Code B3J1.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components AS.ME National Corrected, Code Name of Name of Manufacturer Board Other Year emovd or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Piping EB-01-SP Unknown None N/A N/A Unknown Corrected No

7. Description of Work: Ensure a rounded radius on inlet to safety valve MS-2005.

8. Tests Conducted: Hydrostatic E1 Pneumatic 2 Nominal Operating Pressure E Exempt , 3 Other EJ Pressure psi Test Temp. OF None

9. Remarks RR 2003-0050 Applicable Mlanufacturers Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed g, w, ISI Coordinator Date /,//;b .

Owncr or Owner'sa Nsaignce. Title (f 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 8. 2003 to October 23, 2003, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any, personal injury or property damage or a loss of any kind arisi fy r c9 n4cted with this inspection.

Commissions WI-247972 e tosnaiure National Board. State. Province. and Endorsements Date: ,

PBF-7050 Revision 2 12/02102 SE?Al7.11.1

FORMI NIST2 OWNER'S REPORT FOR REPA JR/REPLACEMNENT ACTI VITY As Required by the Provisions of the ASMIE' Code Section XI

1. Owner Nuclear Management Corporation Date October 24. 2003 700 First Street. Hudson. WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, To oRivers, WI 54241 WO 994S30S Repair/Replacement Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West Spec. 676258

5. (a) Applicable Construction Code USAS 16.5. 19 1966 Edition, No Addenda. No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASNIE Nationalected. Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yies or No)

S1-0085 IA nut Unknown N/A N/A nut Unknown Remove No SI-0085IA nut Unknown N/A N/A nut Unknown Installed No

7. Description of Work: Replacement of body to bonnet nut associated with SI-00851 A.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt Other El Pressure psi Test Temp. OF None

9. Remarks RR 2003-0068 Applicable Mlanufactur's Data Repots to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISICoordinator 1- Date /,,, 2 7 Owner or O%ners Designee. Title 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 WVisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 16. 2003 to October 24. 2003, 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 ASME Code, Section Xl.

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

} . .tg ~ ted Commissions WN'I-247972 1sp-cctorls tinature National Board. State, Province. and Endorsements lDate: // AC  ;

PBF-7050 Revision 2 12/02/02 SEM 7. 11.1

FORNI NIS.2 OWNER'S REPORT FOR REIPAIRIREPLACENIENT ACTIVITY As Required by the Provisions of the ASMNE Code Section XI

1. Owner Nuclear Management Corporation Date October 2'3. 2003 700 First Street. Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0200287 Repair/Rcptacemcent Organization P.O. No.. Job No. Etc.

3. Work Performed By: -We Energies Type Code Symbol Stamp N/A 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Residual Heat

5. (a) Applicable Construction Code ASME 111. 19 71 Edition, Winter 1971 Class 2 Addenda. No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National. Code Name of Name of Manufacturer Board Other Ymear Reoved or Stamped Component Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

RH-OOS61C Crosby N56225000- N/A RH-S6IC 1972 Removed Yes 0002 RH-00861C Crosby N56225 N/A Rif-861C 2003 Installed Yes I 0003 1

7. Description of Worki Replacement of relief valve.

8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Exempt l Other E Pressure _ psi Test Temp. OF None

9. Remarks RR 2003-0062 Applicable Nlanufacnrcr's Data Repons to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date /a/

0' /)

OwAner or Owner's Designee. Title 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 of 'isconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 11. 003 to October 23. 2003, 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 ASME Code, Section Xl.

By sioning this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arijs)) or co0 eted with this inspection.

Commissions WI-247972

'Inspector's Signature Nationa! Board. State. Province, and Endorsements Date: //~ S W':

P11F-7050 Revision 2 12102/02 SEM 7.11 1.

FORMNI NIS-2 OWNER'S REPORT FOR REPAIR/REP'LACEMIENT ACTIVITY As Required by the Provisions of the ASM E Code Section XI

1. Owner Nuclear Management Corporation Date November-7 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0206026 Repair/Replaccment Organization P.O. No.. Job No. Etc.

3. Work Performed By: We EnerLies Type Code Symbol Stamp NIA nitne 6610 Nuclear Road Authorization No. N/A TwVo Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant West G-676262; Bech 6118-M-78

5. (a) Applicable Construction Code B31.1. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASMI National Corrected, Code Name of Namc of Manufacturer Board Other Ycar Removcd or Stamped Component Manufacturer Scrial No. No. Identification Built Installed (Yes or No)

PS RC 2501 R- Grinnell N/A N/A None Unknown Removed No 14-21-1I Clevis Pin PS RC 2501 R- Anvil NIA NIA None Unknown Installed No 14-2H I Clevis International Inc.

Pin

7. Description of Work: Replaced the clevis pin.

8. Tests Conducted: Hydrostatic El Pneumatic [1 Nominal Operating Pressure El Exempt f3 Other El Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0053 Applicable Manufacturer's Data Repons to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ,7 &,< - >_ ISI Coordinator Date I/ A Z Owner or Owners Designee. Title (/,

CERTIFICATE OF INSER VICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 27. 2003 to November 7. 2003. 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 wvith the requirements of ASME Code. Section Xl.

By signing this certificate, neither the Inspector nor his employer makes any Warranty, expressed or implied.

concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nW his emplo r shall be liable in any manner for any personal injury or property damage or a loss of any kinordccted with this inspection.

//.p.j ^Commissions WI-247972 ein-pector's SNgnature National Board. State. Province. and Endorsements PBF-7050 Revision 2 12102/02 SEMS7.1 1.1

FORMI NIS-2 OWNER'S REPORT FOR REPAIR/REPLACENIENT ACTIVITY As Required by the Provisions of the ASNME Code Section XI

1. Owner Nuclear Management Corporation Date November 6. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 W\'O 0309658 Rcpair/Replaccmcnn Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers. WI 54241 Expiration Date N/A address

4. Identification of System: Reactor Coolant Bechtel 61 18-M-78 Rev. 6

5. (a) Applicable Construction Code B31.1, 19 67 Edition, N/A Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASM E National ar CrE Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

Support RC- Unknown N/A NIA None Unknown Removed No 250IR-2-RCI5 Support RC- Unknown N/.A N/A None Unknown Installed No 250IR-2-RC15

7. -Description-of Work: Replacement of threaded rod.

8. Tests Conducted: Hydrostatic al Pneumatic El Nominal Operating Pressure Dl Exempt E Other E Pressure psi Test Temp. OF None Required.

9. Remarks RR 2003-0078 Applicable Mtanufacturers Data Reports to be attached.

CERTIFICATE OF COMIPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ;7 ,. ZZ. t\ ISI Coordinator Date // /7 / -,

Owner or Owner's Designee. Title I f 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 Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 28. 2003 to November 6. 2003, 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 ASME Code,Section XI.

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

wnnected

,2kcc~in d Commissions WI-247972

>Inspectors Signature National Board. State. Province, and Endorsements Date: 1 //An%t'Lf PBF-7050 Revision 2 12/02/02 SEM 7.1 1.I

FORM NIS-2 OWNER'S REPORT FOR REPAIRIREPLACEMNENT ACTIVITY As Required by the Provisions of the ASMIE Code Section XI

1. Owner Nuclear Management Corporation Date December 16. 2003 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0215082 RcpairiReplacemcnt Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection West 676241

5. (a) Applicable Construction Code B31.1. 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

S-100S53A VCoan Valve N/A N/A SI-853A Unknown Corrected No Corp.__ _ _ _

7. Description of Work: Seal welded to prevent boric acid leakage.

8. Tests Conducted: Hydrostatic El Pneumatic .El Nominal Operating Pressure al Exempt .

Other El Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0039, CAP 52831 Applicable Manufacture's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed , c ISI Coordinator Date / ,//;'*ar.7' Owner or Owmcr's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period September 10, 2003 to December 16. 2003, 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 ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer hall be liable in any manner for any personal injury or property damage or a loss of any kind arns c d with this inspection.

Commissions WI-247972 e; n nature National Board, State, Province. and Endorsemcnts Date: 3- tatz

'2S-PBF-7050 Revision 2 12/02/02 SEM 7 .11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date July20, 2003 700 First Street, Hudson, WI 54016 *Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 1 6610 Nuclear Road, Two Rivers, WI 54241 WO 0213015 Repair/Replacernent Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A nare 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Safety Injection Bechtel Spec M-78

5. (a) Applicable Construction Code B31.1. 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

HS-16 Grinnell Co. 3150 N/A None Unknown Removed No HS-16 Crinnell Co. 3150 N/A None Unknown Installed No

7. Description of Work: Like-for-like replacement due to worn fitting connections.

8. Tests Conducted: Hydrostatic ] Pneumatic a3 Nominal Operating Pressure E Exempt CK Other [3 Pressure psi Test 1['emp. OF

9. Remarks RR 2003-0034 Applicable Manufacurets Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ze ,_, Ie ISI Coordinator Date *7 A 0 /ito Oner or Ownes Designee, Title 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 of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period June 18. 2003 to July 20. 2003 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 ASME Code,Section XI.

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

Commissions WI-100128 Inspector's S iature National Board, State, Province, and Endorsernents Date: ,-4_- 0 PBF-7050 Revision 2 12/02/02 SEM 7.1 1.1

FORM NIS-2 OWNVER'S REPORT FOR REPAIRIREPLACEMIENT ACTIVITY As Required by the Provisions of the ASNIE Code Section XI

1. Owvner Nuclear Management Corporation Date December 16, 2003 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0216385 Rcpair/Rcplaccrncnt Organization P.O. No., Job No. Etc.

3. Work Performned By: We Energies Typc Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A addrcss

4. Identification of System: Reactor Coolant PB-247 Rev. 3

5. (a) Applicable Construction Code Section ITT 19 68 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1998 Ed. Addenda thru 2000 (c) Applicable Section Xl Code Cases None

6. Identification of Components ASME National Corrected, Codc Name of Name of Mianufacturcr Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

RC-00434 Crosby N82732 N/A RC-434 N/A Removed Yes 0001 RC-00434 Crosby XX5950 175 IN/A RC-434 N/A Installed Y-es

7. Description of Work: Replacement of valve.

8. Tests Conducted: Hydrostatic 5 Pneumatic a Nominal Operating Pressure C Exempt 5 Other E Pressure psi Test Temp. OF None Required

9. Remarks RR 2003-0059 Applicable lanuracitrer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASMIE Code,Section XI.

Type Code Symbol Stamp: NI/A Certificate of Authorization No. Expiration Date N/A Signed .,__ __ __ __ ___I_

O*^c C151.T ISI Coordinator Date -2 nror O-iicr's Designce. Title O /

CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commiIssion issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by IISBCT have inspected the components described in this Owner's Report during the period October 7. 2003 to December 16. 2003, and state that to the best of my knowledge and belief, the Ow\ner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied.

conceming the examinations and corrective measures described in this Owvner's Report. Furthermore, neither the Inspector n his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arjs ffrrcopied with this inspection.

Commissions N\'I-247972

/ ilrp~c lorts S~t~ac Naitiona: Board, S:;ut[. Provincc. and Endorsements Date:__________

PIBF-7050 Re\ ision 2 12'!02 '02 SEM L.1 11.1

FORM NVR-I REPORY OF REPAIR E'*1ODIFICATION EOR. FI3I`LACENE:NT,7 OF NUCLEAR PRESSURE RELIEF DlEVICES

.- i-.--

I Wo:k rer.follucd by Crane Nucelear, Inc. L'i/O fc-2679 /VAa4AJ 21825 Cobb Internsuion a] Bvd., K~en nessw, GA 30152-43 52

2. Work pirrormcd for- dqrCLEAI tA ;jA61,6M 6jT Co~,tic

3. Ownetr U/c)1CaPJ~1AI &LCWC-/ iEr  % ______

4. Nsame, address, and idenzificic:ion offrnuclear powier plant /Jg 16(U EiAe Pe.4 S. z: Refailr pre Ssure relief cdevice: ____________________

b: Name of manufactarer: C4SBY -

c: IdentiFyin3 uos. 413 Seo

--T, j, j.

4 *f AlqAn -

~~~~~-

v 4 I

r -Xxts*z&tb AL 67es d: Construction Code: A506 SZQ - 16 xg!bJ^

IJJA

-I

/A ^/K

.,,,;AX;:t,;;

6. ASME Code Section XI appficalgSlcotionf ,W)A ,A)6p/

--- IoJ - 6"  ;,A 1,

7. ASIME Cod: Section XI used for repairs, modifications. or replacebments:

i: .I

_7 &,

86 1M7 -;

-J/ 2v7

--. M vk.T - "a,.IS

8. Constriction Code used for repairs, modtfications, or replacementi -I KSaA-LA ,,.,:

_ I

9. Design Responsibil iir, C90S5Y. _ ,

('*e-VC A-in 6u*eqA - Co.

10. Opening pressure: Ii A Blowdown (if anplicable) jLJLA °^'. Set pressure and Plowdown adjistment made at: _ L A/A - using ttff I l. Descriptio n of work: (include name and identifying number ofre acement parrs) 914j i36eVLe C&e7Wa0 1-AP2e Ro(-6P POLAc (

Ndt;Za P' J ' 791e K; _ _____60 12 Rscrarks-CERTIFICATE OF COMPLIANCE 1 L certify tha! to the best of rmy knowledge and be!iet the statements made in tMis report are correct and the repair. modfication or replacement of the pressure rel:el devices described above conforrrms to Section Xl of the ASME Code and the National Boaid Inspection Code 'VR and '1NR rules.

National Board Certilacate of Authonzation No. 473 to use the 'VR stamp expires July 22 20 05 Natio-al Board Certifizate o Authorization No S2 to use the NR stamexpires ____22 20 05

_Date 20 03 Crane Nuclear. Inc. Signe zi z uI misncij (nam e d . r; itilse)

CERTIFICATE OF INSPECTION I _. 1,?I5J;V 7u h~olding a valid commission issued by The Naliona! Board ot Boiier and Pressure Ve5se)

IrssPectors anrd ceert~cate of comneterncy issued by the junsdiclicn of 4... A5; ___ _ _ __ and emporYed L-L,.r J c 4,-... 2a ..Z Jv j. ,-j,..

di'J ^, a h I Inspected ltle renir. modification or replacemren described in this renort on _Z-_2?. 20 anottate :at -e3 best of my knov.iedge ana belief. this repair. rnocifitacion or replacement has been compteted it) accordance with Section Xl Ic! the ASTIE Code 3na the N ational Board Inspection Code 'VR' and NR' rules.

By signing tM:s certficaze. neitter the uncersigned nor my employer makes any warranty, expressed or implied, concerning the repanr. modifica!ion or replacement described in this repoh. Frthermore. neither the undersigned no! my employer shall Ite liable in any manrer fnr any personal injjry, property damage or loss of any kind 2rising from or connected w:tn t1-is

nspection.

IsDt-e 7-21 2D 3 S;gn.ed Ptt/t7AihJ' Conrussion {Is f 22 -AJI-Cd .St

,{;t~F^D, - -

• i , awpr.1 dz iov nn)8 r~;

i, I

FORM NIS-2 OWNNIER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date May 1, 2002 700 First Street, Hudson, WI 54016 Sheet: I of 1

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WOs 0203256, 0203257 Repair Organization P.O. No.. Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A

4. Identification of System: Safety Injection West Spec G676262, ASTM A-312

5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition No Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No. Identirication Built Replacement (Yes or No)

S-150IR-2 N/A N/A N/A N/A Unknown -Replacement No Sl-15011R-3 N/A N/A N/A N/A Unknown Replacement No

7. Description of Work: Modify the piping so that bigger holes can be used to thoroughly clean and examine piping.

8. Tests Conducted: Hydrostatic EJ Pneumatic al Nominal Operating Pressure ID Other El Pressure NOP psi Test Temp. NOT 0 F

System Leakage Test

9. Remarks RRM 2002-0037, ECR 2002-0074, Code Case N416-1.

Applicable hManufacturers Data Reports to be attached.

CERTIFICATE OF COMPLIANCE Wne certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or rcplacemcnt Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed  ; 2 ISI Coordinator Date 2//2/2 OdZ-/

Owner or Ownces Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSB CT have inspected the components described in this Owner's Report during the period May 1, 2002 to May 15. 2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Oxvner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector no loyer s be liable in any manner for any personal injury or property damage or a loss of any kind at 1 conn le 'iththis inspection.

Commissions Wl-247972 t'na National Board, State, Province, and Endorsements Date:____________

IPBF-7050 Revision 1 05/17/02 SEN 17.11.1

FORM NIS-2 OW'N'ER'S REPORT FOR REPAIRIREPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date January 9, 2004 700 First Street, Hudson, WI 54016 Sheet: I of I

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9926780 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Bechtel Spec 6118-C-8

5. (a) Applicable Construction Code ASME Section III. 19 92 Edition, 92 Addenda, No Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1992 Ed. Addenda thru 1992 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

C-2 support plate Unknown None N/A None Unknown Corrected No

7. Description of Work: Moved plate to accommodate new venting device.

8. Tests Conducted: Hydrostatic E Pneumatic D Nominal Oiperating Pressure El Exempt El Other El Pressure psi Test Temp. OF None required

9. Remarks RR 2003-0065; CAP 053794 Applicabte Manufacturers Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date ;1 //Z/ II I Owner orO ncer's Designcee Titlc /I CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period October 15. 2003 to Januarv 9. 2004, 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 ASME Code,Section XI.

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

Commissions WI-247972

/ Sttorks iinture National Board. State, Province, and Endorsements Date: _-___/_ _-___

PBF-7050 Revision 2 12/02/02 SEM 7.1 1.1

FORMT NIS-2 OWNER'S REPORT FOR REPAIRIREPLACENIENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date November 18, 2003 700 First Street, Hudson, WI 54016 Sheet: 1 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9926779 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment

5. (a) Applicable Construction Code , 19 Edition, _ Addenda, _Code Case (b) Applicable Edition of Section XI Used for Repairs/Replacement Activity 1992 Ed. Addenda thru 1992 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Namc of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

See Attached

7. Description of Work: Replacement of ball valves

8. Tests Conducted: Hydrostatic El Pneumatic 3 Nominal Operating Pressure El Exempt El Other El Pressure 66 psi Test Temp. 68 OF

9. Remarks RR 2003-0035, 2003-0036, Contruction Code Bechtel Spec 6118-C-8; CAP 053794 Applicable Manufacturer's Data Reports to be attached.

CERTIFICATE OF COMPLIANCE I certify that the statements made in the report are correct and that this conforms to the rules of the ASME Code,Section XI.

Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A Signed ISI Coordinator Date /,q Ace+

Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Wisconsin and employed by HSBCT have inspected the components described in this Owner's Report during the period August 8. 2003 to November 18. 2003, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owvner's Report in accordance with the requirements of ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer all be liable in any manner for any personal injury or property damage or a loss of any kind aris r co e 'ed with this inspection.

Commissions WI-247972 l tocc si~Qutc National Board, State, Province, and Endorsements PBF-7050 Revision 2 12/02/02 SEM 7 .11.1

FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY (CONTINUATION)

As Required by the Provisions of the ASME Code Section XI

1. Owner Nuclear Management Corporation Date January 13, 2004 700 First Street, Hudson, WI 54016 Sheet: 2 of 2

2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9926779 Repair/Replacement Organization P.O. No., Job No. Etc.

3. Work Performed By: We Energies Type Code Symbol Stamp N/A name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A address

4. Identification of System: Containment Bechtel Spec 6118-C-8

5. (a) Applicable Construction Code 19 _ Edition, Addenda, -CodeCase (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1992 Ed. Addenda thru 1992 (c) Applicable Section XI Code Cases None

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed or Stamped Component Manufacturer Serial No. No. Identification Built Installed (Yes or No)

C-I-DIV W-K-M Valve N/A N/A N/A Unknown Removed No Division of ACF Industries C-I-DIV Trcntec Inc. EQD-2-UP- N/A N/A Unknown Installed No 001 C-l-D2V W-K-M Valve N/A N/A N/A Unknown Removed No Division of ACF Industries C-l-D2V Trentec Inc. EQD-2-UP- N/A N/A Unknown Installed No 007 PBF-70SOa Revision 2 12/02/02 SEM 7.1 1.1

NIS-1 Inservice Inspection Summary Report for U2R26 IWE Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 2 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Operating Date: October 1, 1972 Report Date: February 11, 2004 Written by: e~lt- Date: 2-/7-oI Reviewed by: I f. /~ Date: 217/

Approved by: Date: Z/72

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company, 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 2 4. Owner Certificate of Authorization: Docket 50-301

5. Commercial Service Date: October 1, 1972 6. National Board Number for Unit: N/A

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

Containment Bechtel N/A U009972 N/A 4 $ +

4 4 + -t 4 4 4 4 4 4 + +

I I + +

I I + +

Bechtel Group, Inc.

2280 Bates Avenue Concord, CA 94520

8. Examination Dates: May 15, 2002 to November 14, 2003

9. Inspection Period Identification: Second Period

10. Inspection Interval Identification: First Interval

11. Applicable Edition of Section XI: 1992 Addenda 1992

12. Date / Revision of Inspection Plan: August 24, 2001 / rev. 0

13. Abstract of Examinations: Include a list of examinations and a statement concerning status of work required for current Interval.

An Inservice Examination of containment metallic liner Class MC components of Nuclear Management Company (NMC) Point Beach Nuclear Plant (PBNP) Unit 2 was performed during the time period of May 15, 2002 to November 14, 2003. This was the second period of the first ten-year interval.

Page 2 of 14

The containment liner was examined in accordance with the IWE Containment Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1992 Edition, 1992 Addenda in accordance with 10 CFR 50.55a.

No Code Cases were used in the performance of examinations, tests, and repairs and replacements.

Visual examinations were conducted in accordance with ASME Section XI. WE Energies, Nuclear Management Company, Raytheon, and Lambert MacGill Thomas, Inc. personnel performed the examinations. See Attachment 1 for examinations.

There were eight repair/replacements performed on Class MC components during this IWE exam report.

• RR 2003-0035 for 2C-1-DIV replacement of equipment airlock inner door equalizing vent valve with an equalizing vent flange to reduce maintenance.

• RR 2003-0036 for 2C-1-D2V replacement of equipment airlock outer door equalizing vent valve with an equalizing vent flange to reduce maintenance.

• RR 2003-0037 for 2C-2-DIV replacement of personnel airlock inner door equalizing vent valve with an equalizing vent flange to reduce maintenance.

• RR 2003-0038 for 2C-2-D2V replacement of personnel airlock outer door equalizing vent valve with an equalizing vent flange to reduce maintenance.

• RR 2003-0060-1 for 2C-2-D2V relocation of personnel airlock outer door equalizing vent support for installation performed in RR 2003-0036.

• RR 2003-0065-1 for 2C-2-D2V relocation of personnel airlock inner door equalizing vent support for installation performed in RR 2003-0037.

• RR 2003-0079 for 2CPP-56 to replace one flange bolt.

• RR 2003-0083 to replace containment isolation valve on purge supply and exhaust penetrations with blank flanges.

This exam meets the requirements of Inspection Program B of ASME Section XI with approximately 61% examination completed for the interval.

14. Abstract of Conditions Noted:

See Attachment 1 for a summary of examinations performed.

Containment Liner Plate One liner plate contained surface corrosion where paint had been removed as a result of repeated impact such as a scaffolding pole. No loss of base metal was noted.

Page 3 of 14

Process Piping Penetrations Two piping penetrations for the steam generator blowdown lines have noted corrosion starting on the coating. This is the start of a coatings failure and was identified during an augmented examination.

15. Abstract of Corrective Measures Recommended and Taken.

Containment Liner Plates Touch up painting to the affected area will be performed. Surface preparation for painting will remove the surface corrosion.

Process Piping Penetrations The process piping will be recoated at next available opportunity to maintain the corrosion protection of the coating.

Page 4 of 14

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 Authorization No. (if applicable): NRC Docket 50-301 Expiration Date: N/A Date: 7--/7-o ' Signed: Nuclear Management Co.. LLC by Z t 9ce..

Owner 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 or Province of Wisconsin and employed by Hartford Steam Boiler of Hartford Connecticut, have inspected the components described in this Owner's Report during the period May 16, 2002 to November 14, 2003, 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 Owner'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.

Commissions WI 247972 s ec-to1r's Signature National Board, State, Province, and Endorsements Date &/VI Page 5 of 14

Nuclear Management Company Commercial Service Date: 10/0o172 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Attachment 1 Unit 2 Refueling Outage 26 IWE Containment Inspection Program Examination Summary Page 6 ofl4

Nuclear Management Company Commercial Service Date: 10/01/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2C-I-DIV E-G E8.10 VT-I 2003-0035 WO 9926779 2C-I-D2V E.G E8.10 VT-I 2003-0036 WO 9926779 2C-2-DIV E-G E8.10 VT-I 2003-0037 WO 9926780 2C-2-D2V E.G E8.10 VT-I 2003-0038 WO 9926780 2C-3 E.G E8.20 Torque RP-IB 2CH-01 E-C E4.11 VT-I 03U2-760E002 03U2-E002 1E-C E4.12 UT 03U2- 11413001 03U2-E002 E-D E5.30 VT-3 03U2-760E074 2CH-02 E-C E14.11 VT-I 03U2-760E004 03U2-1:002 E-C E4.12 UT 03U2-114E002 03U2-E1002 E-D E5.30 VT-3 03U2-760E074 2CH-03 E-C E4.11 VT-I 03U2-760E006 03U2-E002 E-C E4.12 UT 03U2-11413003 03U2-E002 E-D E5.30 VT-3 03U2-760E1074 2CH-04 E-C E4.11 VT-I 03U2-760E008 03U2-E002 E-C E4.12 UT 03U2-114E004 03U2-E002 E-D E5.30 VT-3 03U2-760C3074 Page 7 of 14

Nuclear Management Company Commercial Service Date: 10/01/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2CH-05 E-C E4.11 VT-I 03U2-760E009 03U2-E01I E-C E4.12 UT 03U2-114E005 03U2-E01 I E-D E5.30 VT-3 03U2-760E010 2CH-06 E-C E4.11 VT-I 03U2-760E01 I 03U2-E011 E-C E4.12 UT 03U2-114E006 03U2-EOI I E-D E5.30 Vr-3 03U2-760E012 2CH-07 E-C E4.11 vr-l 03U2-760E013 03U2-E011 E-C E4.12 UT 03U2-114E007 03U2-E01 I E-D E5.30 VT-3 03U2-760E014 2CP-025 E-A 21.12 VT-3 03U2-760E015 2CP-026 E-A E1.12 VT-3 03U2-760E016 2CP-027 E-A 21.12 VT-3 03U2-760E017 2CP-028 E-A 21.12 VT-3 03U2-760E018 2CP-029 E-A 21.12 VT-3 03U2-760E019 2CP-030 E-A E1l.12 VT-3 03U2-760E020 2CP-031 E-A 21.12 VT-3 03U2-760E021 2CP-032 E-A 21l.12 VT-3 03U2-760E022 Page 8 of 14

Nuclear Managemeent Company Commercial Service Date: 10/1/n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRMI# IDR Notes 2CP-033 E-A 21.12 Vr-3 03U2-760E023 2CP-034 ur 03U2-114E028 03U2-E003 VTr-3 03U2-760E079 E-A 21.12 VTr-3 03U2-760E024 03U2-E003 2CP-035 E-A 21.12 VT-3 03U2-760E025 2CP-036 E-A 21.12 VT-3 03U2-760E026 2CP-037 E-A 21.12 VT-3 03U2-760E027 2CP-038 E-A 21.12 VT-3 03U2-760E028 2CP-039 E-A E1.12 VT-3 03U2-760E029 2CP-040 E-A 21.12 VT-3 03U2-760E030 2CP-041 E-A 21.12 Vr-3 03U2-760C031 2CP-042 E-A 21.12 VT-3 03U2-760E032 2CP-043 E-A 21.12 VT-3 03U2-760E033 2CP-044 E-A 21.12 VT-3 03U2-760E034 2CP-045 E-A 21.12 VT-3 03U2-760E035 2CP-046 E-A E1.12 VT-3 03U2-760E036 Page 9 of 14

Nuclear Management Company Commercial Service Date: 101/o7n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2CP-047 E-A 21.12 Vr-3 03U2-760E037 2CP-048 E-A E1.12 VT-3 03U2-760E038 2CP-049 E-A 21.12 Vr-3 03U2-760E039 Small paint scrapes 2CP-050 E-A 21.12 03U2-760E040 Limited to exposed areas 2CP-051 E-A 21.12 VT-3 03U2-760E041 Limited to exposed areas 2CP-052 E-A 21.12 VT-3 03U2-760E042 Small paint scrapes 2CP-053 E-A E1.12 VT-3 03U2-760E043 03U2-EOOI Small paint scrapes 2CP-054 E-A 21.12 VT-3 03U2-760E044 Small paint scrapes 2CP-055 E-A 21.12 Vr-3 03U2-760El45 Small paint scrapes 2CP-056 E-A E1.12 VT-3 03U2-760E046 Small paint scrapes 2CP-057 E-A 21.12 Vr-3 03U2-760E047 Small paint scrapes 2CP-058 E-A E1.12 VT-3 03U2-760E048 Small paint scrapes. Limited to exposed areas 2CP-059 E-A E1.12 VT-3 03U2-760E049 Small paint scrapes 2CP-060 E-A E1.12 VT-3 03U2-760EO50 Small paint scrapes 2CP-1 16 VT-3 03U2-760EO51 PBNP re-exam Page 10 of 14

Nuclear Management Company Commercial Service Date: i0 olfn2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2CP-127 VT-3 03U2-760E052 03U2-E009 PBNP re-exam 2CP-128 VT-3 03U2-760E053 PBNP re-exam 2CP-129 E-C E.12 UT 03U2-114E008 03U2-EO08 E-C E4.11 VT-I 03U2-760E054 03U2-EO08 2CP-133 E-C F4.11 VT-I 03U2-760E055 03U2-EOI I E-C E4.12 UT 03U2 t14E009 03U2-EOI I 2CP-134 E-C E4.11 VT-1 03U2-760E056 03U2-EOI I E-C E4.12 UT 03U2-114E010 03U2-EO1 I 2CP-135 UT 03U2-114EOI I 03U2-EOI I PBNP (grid)

E-C E4.11 VT-I 03U2-760E057 03U2-EOl I E-C E4.12 UT 03U2-114E01 I 2CP-137 E-C E4.11 VT-I 03U2-760E058 03U2-EOI I E-C E4.12 UT 03U2-114E013 03U2-EOI I 2CP-138 E-C E4.11 VT-1 03U2-760E059 03U2-EOI I E-C E4.12 UT 03U2-114E014 03U2-EOI I Page 11 of 14

Nuclear Management Company Commercial Service Date: 10/o11n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Boand Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2CP-1 39 UT 03U2-114E016 03U2-EO I PBNP (grid)

E-C E4.11 VT-I 03U2-760E060 03U2-E01 I E-C E4.12 UT 03U2-114E016 03U2-EOII 2CP-140 E-C E4.11 VT-I 03U2-760E061 03U2-E01 1 E-C E4.12 UT 03U2-114F017 03U2-EOI I 2CPP-35 E-C E4.11 VT-I 03U2-760E062 E-C E4.12 UT 03U2-114E018 2CPP-36 E-C E4.11 VT-I 03U2-760E063 03U2-E004 E-C E4.12 UT 03U2-114E019 03U2-E004 2CPP-39 E-C A4.11 VT-I 03U2-760E064 E-C E4.12 UT 03U2-114E020 2CPP-40 E-C E4.11 VT-I 03U2-760E065 E-C E4.12 UT 03U2-114E021 2CPP43 E-C E4.11 VT-I 03U2-760E066 E-C E4.12 UT 03U2-114E022 2CPP-44 E-C E4.11 VT-I 03U2-760E067 03U2-E010 E-C E4.12 UT 03U2-114E023 03U2-E010 2CPP47 E-C E4.11 VT-I 03U2-760E068 E-C E4.12 UT 03U2-114E024 Page 12 of 14

Nuclear Management Company Commercial Service Date: 101Oil/2 700 First Street Docket 50-301

[Judson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2CPP-48 E-C E4.11 VT-I 03U2-760E069 03U2-E005 E-C E4.12 UT 03U2-114E025 03U2-E005 2CPP-50 E-C E4.11 VT-I 03U2-760E070 03U2-E006 E-C E4.12 UT 03U2-1142026 03U2-E006 2CPP-51 E-C E4.11 VT-I 03U2-760E071 03U2-E007 E-C E4.12 UT 03U2-114E027 03U2-E007 2CPP-56 E4- E8.10 VT-I 03U2-760E072 2003-0079 (outer flange bolting)

E4- E8.20 Torque 2003-0079 (inner and outer flange bolting) 2CPP-57 E-A 21.12 VT-3 03U2-760E077 2CPP-58 E-A 21.12 VT-3 03U2-760E078 2CPP-V- 1 E-A 21.12 VT-3 03U2-760E080 2003-0083 E-A 21.12 VT-3 03U2-760E075 E-G E8.10 VT-I 03U2-760E081 2003-0083 2CPP-V-2 E-A 21l.12 VT-3 03U2-760E082 2003-0083 E-A 21l.12 VT-3 03U2-760E076 E4- E8.10 VT-I 03U2-760E083 2003-0083 2RB-01 augmented 03U2-762E003 reference bar measurement Page 13 of 14

Nuclear Management Company Commercial Service Date: i0w/ln2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Boand Number for Unit: N/A Component Category Item Exam Type NDE Data Sheet RRM # IDR Notes 2RB-02 augmented 03U2-762E003 reference bar measurement 2RB-03 augmented 03U2-762E003 reference bar measurement 2RB-04 augmented 03U2-762E003 reference bar measurement 2RB-05 augmented 03U2-762E003 reference bar measurement 2RB-06 augmented 03U2-762E003 reference bar measurement 2Z-529 E-D E5.30 VT-3 03U2-760E074 U2-Containmnent E-A EI.l I GV 03U2-762E001 exterior E-A E1.1 I GV 03U2-762E1002 interior Page 14 of 14

NIS-1 Inservice Inspection Summary Report for Unit 1 IWL Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 1 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Operating Date: December 21, 1970 Report Date: February 11, 2004 Written by: At-. Date: t- J '-P Reviewed by: ,

, IDate:

Approved by: I/zDate:

FORMI NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company, 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 1 4. Owner Certificate of Authorization: Docket 50-266

5. Commercial Service Date: December 21, 1970 6. National Board Number for Unit: N/A

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

Containment Bechtel N/A U009971 N/A

4. 4-

4. 4-4- 4 1 4 4 4 4 4 4 4 4

+ + 4 4 Bechtel Group, Inc.

2280 Bates Avenue Concord, CA 94520

8. Examination Dates: September 10, 2001 to February 11, 2004

9. Inspection Period Identification: N/A

10. Inspection Interval Identification: N/A

11. Applicable Edition of Section XI: 1992 Addenda 1992

12. Date / Revision of Inspection Plan: October 25, 2002 / rev. 1

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

An Inservice Examination of containment concrete Class CC components of Nuclear Management Company (NMC) Point Beach Nuclear Plant (PBNP) Unit 1 was performed during the time period of September 10, 2001 to February 11, 2004.

Page 2 of 19

The concrete was examined in accordance with the IWL Containment Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1992 Edition, 1992 Addenda and 10 CFR 50.55a.

No Code Cases were used in the performance of examinations, tests, and repairs and replacements.

The visual tendon surveillance was completed during the implementation period in accordance with Technical Specifications. Precision Surveillance Corporation and WE Energies personnel performed this surveillance. See Attachment I for examinations.

Visual examinations were conducted in accordance with ASME Section XI to meet examination Category L-A, Item L1.1 1 for VT-3C and Item L1.12 for VT-lC. WE Energies, Nuclear Management Company, and Lambert MacGill Thomas, Inc. personnel performed the examinations.

Visual examinations were conducted at the same time as the tendon surveillance. See Attachment 2 for examinations.

No repairs and replacements have been performed on Class CC components during this IWL implementation period.

All examinations required for 33 year tendon surveillance have been completed . This meets the requirements of ASME Section XI and applicable relief requests.

14. Abstract of Conditions Noted:

• Grease Leakage Areas of grease leakage at the tendon grease cans and through concrete leakage were recorded. No appreciable change was noted from conditions recorded during the 2001 concrete examination.

• Exposed Reinforcing Steel Areas of exposed reinforcing steel were recorded. There was no measurable difference since the 2001 examinations

• Concrete Cracking The concrete cracking recorded showed no change with previously recorded indications.

One area of concrete damage was noted that was not previously recorded.

Page 3 of 19

15. Abstract of Corrective Measures Recommended and Taken.

• Grease Leakage Additional corrective maintenance will be pursued to correct grease leakage points.

• Exposed Reinforcing Steel No corrective measures are recommended for these construction defects.

• Concrete Cracking Trending of existing cracks will continue to verify stability of concrete.

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 Authorization No. (if applicable): NRC Docket 50-266 Expiration Date: N/A Date: 2-1-fO'1f Signed: Nuclear Management Co., LLC by Z d/8 Owner 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 or Province of Wisconsin and employed by Hartford Steam Boiler of Hartford Connecticut, have inspected the components described in this Owner's Report during the period September 10, 2001 to February 11, 2004, 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 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 Owner'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.

Y Commissions WI 247972 r's ~ature National Board, State, Province, and Endorsements Date t a-x/

Page 4 of 19

Nuclear Management Power Company Commercial Service Date: 12/2 117O 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A Attachment 1 Unit I Thirty-three Year Tendon Surveillance Summary Page 5 of 19

YEAR UNIT I PHYSICAL AND 3 3 rd UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT NMVC Committed to Nuclear Excellence BEACH NUCLEAR PLANT TABLE I: LABORATORY ANALYSIS OF SHEATHING FILLER UNIT I TENDON END ION CONCENTRATION (PPM) %VNWATER NEUTRAL No.

__________CHLORIDE JSULFIDE NITRATE CONTENT mg KOH/g AC-19 SHOPIBUTT.A. <0.50 I <0.50 <0.50 <0.10 10.5 BF-25 SHOP/BUTT.B <0.59 <0.50 <0.50 <0.10 <0.50 CE-7 SHOP/BUlTr. C <0.50 <0.50 <0.50 <0.10 <0.50

. _j A-----

DF-46 SHOP/BUTTh F <0.50 <0.50 -1 <0.50 <0.10 <0.50 F 050< .0 05001 -0.50--

DF-55_____________

EA455 SHOP/BUTT.AF <0.50 <0.50 <0.50 <0.14 <0.50 EA-5 SHOP/BTOP <.0 0.50 <0.50 0.32 <0.50 V-32 SHOP/TOP . 0.50. <0.50 I <0.50 0.32 <0.50

.t - I ..- ...-

V-88 SHOP/TOP <0.50 <0.50 <0.0O.32O <0.50 V-4HO/O <- <0.50 <0.50 .1 <0.10 <0.50 DV-15 SHOPINEOP A<0.50 <05-05 01 05 DV-36 SHOPMEOP A<0.50 <0.50 <0.50 <0.10 <0.50 Dl3 HPNA 0.50 <0.50 <500.0<0.50 D2-25 SHOP/NEAR A 0.50 -~<0.50 <0.50 <0.10 <0.50 D3-98 SHOP/NEAR A <.050 <0.50 <0.50 <0.10 <0.50 D3-10 SHOP/NEAR B <0.50 I <0.50 <0.50 <0.10 50.50 D391 SHOP/NEAR F 1.00 <0.50 <0.50 <0.20 <0.50 Acceptance Limits Test Limits Water Soluble Chloride Less than 10.0 ppmn Water Soluble Nitrates Less than 10.0 ppmn Water Soluble Sulfides Less than 10.0 ppm, Water Content Less than 10% Dry Weight Neutralization No. Greater than 0 mg KOH/g

33 rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT NIiiI9 Committed to Nuclear Excellnce BEACH NUCLEAR PLANT ears TABLE XI:

SUMMARY

OF DATA SHEETS SQ 12.1 GREASE LOSS Vs GREASE REPLACEMENT UNIT 1 TENDON GREASE REMOVED GREASE REPLACED DIFF. NET  %

SHOP FIELD TOTAL SHOP FIELD TOTAL (GAL.) VOLUME (GAL.) (GAL.)

AC-19 2.25 2.25 4.50 2.25 2.50 4.75 +0.25 56.83 +0.43 BF-25 2.25 2.25 4.50 2.50 2.25 4.75 +0.25 56.78 +0.44 CE-7 2.25 2.25 4.50 2.50 2.50 5.00 +0.50 56.55 +0.88 DF-46 1.75 2.25 4.00 2.50 2.50 5.00 +1.00 56.86 +1.70 DF-55 3.25 2.50 5.75 3.50 2.50 6.00 +0.25 56.71 * +0.44**

EA-45 1.75 2.25 4.00 1.75 2.50 4.25 +0.25 56.55 +0.44 V-5 2.25 37.25 39.50 0.00 39.75 39.75 +0.25 66.83 +0.37 V-32 2.25 40.25 42.50 0.00 43.25 43.25 +0.75 66.81 +1.12 V-88 2.25 40.25 42.50 0.00 44.00 44.00 +1.50 67.23 +2.23 V-144 3.25 37.25 40.50 0.00 42.25 42.25 +1.75 66.87 +2.61 DI-15 3.75 4.00 7.75 4.00 5.25 9.25 +1.50 51.04* +2.93 **

DI-36 2.25 2.75 5.00 2.50 2.50 5.00 0.00 51.04* 0.00 DI-38 2.25 2.75 5.00 2.50 2.50 5.00 0.00 51.05 0.00 D2-25 3.25 3.25 6.50 3.50 3.50 7.00 +0.50 54.04 +0.92 D3-9 2.25 2.25 4.50 2.75 2.50 5.25 +0.75 48.21 +1.56 D3-10 2.25 2.25 4.50 2.50 2.50 5.00 +0.50 50.86 +0.98 D3-15 3.25 3.75 7.00 3.50 4.50 8.00 +1.00 51.04* +1.96**

• Group average.

I ** Acceptable base upon group average

I L I - _ I 33rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT BEACH NUCLEAR PLANT c Nucler &een TABLE VWII:

SUMMARY

OF DATA SHEETS SQ 9.0 - TENDON LIFTOFFS UNIT 1 TENDON END EFFECT. JACK PRESS. LIFTOFF AVE. l LOWER 95% l 90% UPPER ACCEPT WIRES I No. I LIFTOFFI LIMIT LOWERJLOWER LIMIT AC-19 SHOP/ BUTT A 90 6002 3460 653.7 648.2 601.2 571.1 541.1 664.2 YES FIELD/BUTr.C 90 6001 3390 642.8 BF-25 SHOP/BU1T. B 90 6001 3220 610.3 618.9 601.2 571.1 541.1 664.2 YES FIELD/BUTT.F 90 6001 3310 6 627.5 1 1 CE-7 SHOP/BUTT. C 90 6001 3460 656.2 658.7 601.2 571.1 541.1 664.2 lYES FIELD/BUTr. E 90 6002 3500 661.3 l I_!___I DF-55 SHOP/BU1T.F 90 6001 3360 637.1 633 601.2 571.1 541.1 664.2 YES FIELD/BUTT D 90 6002 3330 628.9 I EA-45 SHOPIBUTT.A 90 6002 3360 634.6 628.8 601.2 571.1 541.1 664.2 YES FIELD/BUTT.E 90 6002 3300 623.1 V-5 SHOP/rOP 90 6002 3600 680.3 680.3 628.2 596.8 565.4 672.3 YES V-32 SHOPrrOP 90 6001 3530 669.6 669.6 628.2 596.8 565.4 672.3 YES V-88 SHOP/rOP 90 6001 3540 671.5 671.5 628.2 596.8 565.4 672.3 YES V-144 SHOPrrOP 90 6002 3360 634.6 634.6 628.2 596.8 565.4 672.3 l YES

- . L - , - -

33r YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT BEACH NUCLEAR PLANT Cmwwtd to Nuclerxcen>

TABLE VIII:

SUMMARY

OF DATA SHEETS SQ 9.0 - TENDON LIFTOFFS UNIT 1 TENDON END 1 EFFECT. l JACK PRESS. LIFTOFF AVE. LOWER 95% l 90% UPPER ACCEPT WIRES No. LIFTOFF LIMIT LOWER LOWER LIMIT l D1-36 SHOP/ NEAR A 90 6002 3450 651.7 655.5 613.8 583.1 552.4 666 YES FIELD/NEAR D 90 6002 3490 659.4 D2-25 SHOP/NEAR B 90 6001 3360 637.1 632.0 613.8 583.1 552.4 666 YES FIELD/NEAR E 90 6002 3320 627.0 l D3-15 SHOP/NEAR F 90 6001 3480 660 664.4 613.8 583.1 552.4 666 YES FIELDINEAR C 90 6002 l_3540 668.9__1 1 1l

33rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT Nu BEACH NUCLEAR PLANT Comatd to NuclearEce lns TABLE IX:

SUMMARY

OF DATA SHEETS SQ 10.2 & 10.3-VISUAL INSPECTION AND TENSILE TESTING OF WIRES-UNIT I TENDON SAMPLE CORROSION SAMPLE DIAMETER YIELD ULTIMATE ELONGATION ACCEPTABLE No. LEVEL LOCATION (IN) STRENGTH STRENGTH (IN)

(FT) (PSI) (PSI)

DF-55 I A 20'-29' 0.250 217,654 259,656 4.20 YES 2 A 60'-69' 0.250 218,927 260,292 4.05 YES 3 A 100'-109' 0.250 216,382 261,565 4.30 YES V-88 I A 20'-29' 0.249 228,425 264,997 4.10 YES 2 A 70'-79' 0.249 226,500 265,638 4.25 YES 3 A 120'-129' 0.249 225,217 264,355 4.10 YES D3-15 I A 20'-29' 0.251 219,727 266,448 4.85 YES 2 A 50'-59' 0.251 220,358 266,448 4.65 YES 3 A l 80'-89' l 0.251 l 222,253 268,974 5.05 l YES

L _ _ - _ _I 3 3 rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT BEACH NUCLEAR PLANT Conw srtd to Nuclear EvceffenF TABLE X:

SUMMARY

OF DATA SHEETS SQ 11.0 TENDON RETENSIONING UNIT 1 WIRE REMOVAL TENDONS TENDON END ORIGINAL OBSERVED  % ACCEPT AVE. RETENSIONING  % ACCEPT.

ELONGATION ELONGATION VARI. LIFTOFF VARI.

BEFORE EACH TOTAL EACH ITOTAL RETEN. JACK l PRESS. 1 AVE.

I_ I I I L/OFF DF-55 SHOP - 8.3125 4.4 8.3 -0.15 - YES 633 6001 3660 684.9 +8.20* YES FIELD - - 3.90 - - - 6002 3573 - -

V-88 SHOP - 9.375 9.4 9.4 +0.26 YES 671.5 6001 3620 686.8 +2.28 A YES D3-15 SHOP - 7.125 3.55 7.15 +0.35 YES 644.4 6001 3550 682.6 +5.93 YES FIELD - - 3.6 _ - - - 6002 3660 - - _

• Within 6% of Upper Limit Predicted Force per SQ 9.0 Section 9.8.7.4

Nuclear Management Power Company Commercial Service Date: 12/21/7o 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A Attachment 2 Unit 1 IWL Containment Concrete Examination Summary Page 12 of 19

Nuclear Management Power Company Commercial Service Date: 12/21/70 700 First Street Docket 50-266 Hfudson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR Tendon Gallery Ceiling V-055, V-056 UT, supplemental 03UI -L002 03UI-761L001 Tendon Gallery Ceiling Tendon Gallery Ceiling VT-IC, direct 03UI-L003 03UI-761L002 Tendon Gallery Ceiling Tendon Gallery Ceiling VT-IC, direct 03UI -L003 03UI-761L003 Tendon Gallery Ceiling Tendon Gallery VT-3C, direct 03UI -L003 03UI-761L004 Tendon Gallery Inner Wall Tendon Gallery VT-3C, direct 03UI-L002, 03UI-L003 03UI-761L005 Tendon Gallery Outer Wall Tendon Gallery VT-3C, direct 03UI-L002, 03Ul-L003 03UI-761L006 Dome Top of Dome VT-3C, direct 03UI-L001, 03UI-L002 03UI-761L007 Dome LDR-A-I VT-3C, direct 03UI -761 L008 Dome PLTF-A-I VT-3C, direct 03UI-LOOI 03UI-761L009 Dome PLTF-A-I VT-3C, remote 03UI-L0I0 03U1-761L010 Dome LDR-B-4 VT-3C, direct 03UI-761L011 Dome PLTF-B-3 VT-3C, direct 03UI-L0I0 03UI-761L012 Dome PLTF-B-3 VT-3C, remote 03UI-L0I0 03UI-761L013 Dome LDR-C-I VT-3C, direct 03UI-761L014 Dome PLTF-C-I VT-3C, direct 03UI-LOOI 03UI-761L015 Dome PLTF-C-I VT-3C, remote 03UI-L001 03UI-761L016 Dome LDR-D-2 VT-3C, direct 03UI-761L017 Dome PLTF-D-3 VT-3C, direct 03UI-L0I0 03UI-761L018 Dome PLTF-D-3 VT-3C, remote 03UI -L001 03UI-761L019 Dome LDR-E-I VT-3C, direct 03UI-761L020 Dome PLTF-E-I VT-3C, direct 03UI-L00I 03UI-761L021 Dome PLTF-E-I VT-3C, remote 03UI -L001 03UI-761L022 Dome LDR-F-7 VT-3C, direct 03UI-761L023 Dome PLTF-F-3 VT-3C, direct 03UI-L001, 03UI-L003 03UI-761L024 Dome PLTF-F-3 VT-3C, remote 03UI-LOOI 03UI-761L025 Dome Dome VT-IC, direct 03U1I-L003 03UI-761L026 Buttress A Facade 6.5 ft el VT-3C, direct 03UI-LOO1, 03UI-L002 03UI-761L027 Buttress A Facade 6.5 ft el VT-3C, remote 03UI-LOO1,03UI-L002 03UI-761L028 Between A&B Buttress Facade 6.5 ft el VT-3C, direct 03UI-L003 Page 13 of 19

Nuclear Management Power Company Commercial Service Date: 12/21O 700 First Street Docket 50-266 Hludson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03UI-761L029 Between A&B Buttress Facade 6.5 ftc VT-3C, remote 03UI -L002 03UI -761L030 Buttress B Facade 6.5 ftc VT-3C, direct 03UI-L001 03UI-761L031 Buttress B Facade 6.5 ft el VT-3C, remote 03UI-LOOI, 03UI-L002, 03UI-L003 03UI-761L032 Between B&C Buttress Facade 6.5 ftc VT-3C, direct 03UI-LOOI, 03UI-L003 03UI-761L033 Between B&C Buttress Facade 6.5 ftc VT-3C, remote 03UI-LOOI, 03UI-L002 03UI-761L034 Buttress C Facade 6.5 e! VT-3C, direct 03UI-LOOI 03UI-761L035 Buttress C Facade 6.5 ftc VT-3C, remote 03UI-LOOI 03UI-761L036 Between C&D Buttress Facade 6.5 ftc VT-3C, direct 03UI-L003 03UI-761L037 Between C&D Buttress Facade 6.5 ftc VT-3C, remote 03UI -761 L038 Buttress D Facade 6.5 ftc VT-3C, direct 03UI-LOOI 03UI -761 L039 Buttress D Facade 6.5 ft el VT-3C, remote 03UI-LOOI 03UI-761L040 Between D&E Buttress Facade 6.5 ftc VT-3C, direct 03UI-L01O, 03UI-L003 03UI-761L041 Between D&E Buttress Facade 6.5 ft el VT-3C, remote 03UI-761L042 Buttress E Facade 6.5 ftc VT-3C, direct 03UI-L001 03UI-761L043 Buttress E Facade 6.5 ft el VT-3C, remote 03UI -L001 03UI-761L044 Between E&F Buttress Facade 6.5 ftc VT-3C, direct 03UI-L003 03UI-761L045 Between E&F Buttress Facade 6.5 ftc VT-3C, remote 03UI-LOOI 03UI-761L046 Buttress F Facade 6.5 ftc VT-3C, direct 03UI-L003 03UI-761L047 Buttress F Facade 6.5 ftc VT-3C, remote 03UI-LOOI 03UI-761L048 Between F&A Buttress Facade 6.5 ftc VT-3C, direct 03UI-L00I 03UI-761L049 Between F&A Buttress Facade 6.5 ftc VT-3C, remote 03UI-L002, 03UI-L003 03UI-761L050 Buttress A Platform T-21A VT-3C, remote 03UI-L00I 03UI-761L051 Between A&B Buttress Platform T-21A VT-3C, remote 03UI-LOOI 03UI-761L052 Buttress B Platform T-21A VT-3C, remote 03UI-L0OI 03UI-761L053 Between B&C Buttress Platform T-21A VT-3C, remote 03UI-L001 03UI-761L054 Buttress C Platform T-21A VT-3C, remote 03UI-L01I 03UI-761L055 Between C&D Buttress Platform T-21A VT-3C, remote 03UI-761L056 Buttress B LDR-B-I VT-3C, direct 03UI-L00I 03UI-761L057 Buttress B PLTF-B-I VT-3C, direct 03UI-L001 03UI-761L058 Between B&C Buttress PLTF-B-I VT-3C, direct 03UI-761L059 Buttress B LDR-B-2 VT-3C, direct Page 14 of 19

Nuclear Management Power Company Commercial Service Date: 12/2l/7O 700 First Street Docket 50-266 Iludson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03UI-761L060 Buttress B PLTF-B-l VT-3C, remote 03UI-L001 03UI-761L061 Between B&C Buttress PLTF-B-1 VT-3C, remote 03UI-L001 03UI -761 L062 Buttress B LDR-B-3 VT-3C, direct 03UI-761L063 Between A&B Buttress PLTF-B-2 VT-3C, direct 03UI-761L064 Buttress B PLTF-B-2 VT-3C, direct 03UI-LOOI 03UI-761L065 Between A&B Buttress PLTr-B-2 VT-3C, remote 03UI-761L066 Buttress B PLTr-B-2 VT-3C, remote 03UI-LOOI 03UI-761L067 Between B&C Buttress Equipment Hatch Platform VT-3C, direct 03UI-761L068 Between B&C Buttress Equipment Hatch Platform VT-3C, remote 03UI-761L069 Buttress C Equipment Hatch Platform VT-3C, remote 03UI -L001 03UI-761L070 Buttress E Door 149 platform VT-3C, remote 03UI-L0I0 03UI-761L071 Between D&E Buttress Door 149 platform VT-3C, remote 03UI-761L072 Between E&F Buttress LDR-F-I VT-3C, direct 03UI-761L073 Buttress E Transfer Canal Platform VT.3C, remote 03UI -LOO0 03UI-761L074 Between E&F Buttress Transfer Canal Platform VT-3C, remote 03UI -761 L075 Buttress F Transfer Canal Platform VT-3C, remote 03UI-LOI 03UI-761L076 Between E&F Buttress PLTF-F-I VT-3C, direct 03UI -L003 03UI-761L077 Buttress F PLTF-F-I VT-3C, direct 03UI-LOOI 03UI-761L078 Between E&F Buttress PLTF-F-l VT-3C, remote 03UI-L00I,03UI-L003 03UI-761L079 Buttress F PLTF-F-1 VT-3C, remote 03UI -L001 03UI-761L080 Buttress F LDR-F-3 VT-3C, direct 03UI-761L081 Buttress F LDR-F-4 VT-3C, direct 03UI-761L082 Buttress F LDR-F-5 VT-3C, direct 03UI-761L083 Buttress F LDR-F-6 VT-3C, direct 03UI-761L084 Buttress F PLTF-F-2 VT-3C, direct 03UI-LOOI 03UI-761L085 Between F&A Buttress PLTF-F-2 VT-3C, direct 03UI-761L086 Buttress F PLTF-F-2 VT-3C, remote 03UI-LOOI 03UI -761 L087 Between F&A Buttress PLTF-F-2 VT-3C, remote 03UI-LOOI 03UI-761L088 Between E&F Buttress Radwaste Compactor Landing VT-3C, remote 03UI-LOOI 03UI-761L089 Buttress F Radwaste Compactor Landing VT-3C, remote 03UI-LOOI 03UI-761L090 Between F&A Buttress Radwaste Compactor Landing VT-3C, remote 03UI-LOOI Page 15 of 19

Nuclear Management Power Company Commercial Service Date: 12/2l/7O 700 First Street Docket 50-266 Hudson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U1*761L091 Between C&D Buttress WKWY-CD-I VT-3C, direct 03UI-LOO1, 03UI-L002 03UI-761L092 Buttress C WKWY-CD-I VT-3C, remote 03Ul-LOO0 03UI-761L093 Between C&D Buttress WKWY-CD-I VT-3C, remote 03U1-761L094 Buttress D WKWY-CD-I VT-3C, remote 03UI-L001 03UI-761L095 Between C&D Buttress WKWY-CD-2 VT-3C, direct 03UI-L001 03UI-761L096 Buttress C WKWY-CD-2 VT-3C, remote 03UI-L001 03UI-761L097 Between C&D Buttress WKWY-CD-2 VT-3C, remote 03U1 -LOO0 03UI-761L098 Buttress D WKWY-CD-2 VT-3C, remote 03UI -LOO0 03UI-761L099 Between D&E Buttress Pipeway #2 Upper (on top) VT-3C, direct 03UI-761L100 Between D&E Buttress Pipeway #2 Upper (on top) VT-3C, remote 03UI-761L101 Buttress E Pipeway #2 Upper (on top) VT-3C, remote 03UI -LOO0 03UI-761L102 Buttress C WKWY-CD-3 VT-3C, remote 03UI-LOO0 03UI-761L103 Between C&D Buttress WKWY-CD-3 VT-3C, remote 03UI-LOOI 03UI-761L104 Buttress D WKWY-CD-3 VT-3C, remote 03UI-LOOI 03UI-761L105 Between C&D Buttress WKWY-CD-4 VT-3C, direct 03UI-761L106 Buttress C WKWY-CD-4 VT-3C, remote 03UI-L001 03UI-761L107 Between C&D Buttress WKVWYD-4 VT-3C, remote 03UI-LOOI 03UI-761L108 Buttress D WKWY-CD-4 VT-3C, remote 03UI-L001 03UI-761L109 Buttress C Mezzanine 66 ft el. VT-3C, remote 03UI-L001 03UI-761L1 10 Between C&D Buttress Mezzanine 66 ft el. VT-3C, remote 03UI-761LI I I Between C&D Buttress WKWY-CD-5 VT-3C, direct 03UI-LOO1, 03UI-L003 03UI-761L1 12 Buttress D WKWY-CD-5 VT-3C, direct 03UI-L0O1,03UI-L003 03UI-761L1 13 Buttress D WKWY-CD-5 VT IC, direct 03UI-LOO1, 03UI-L003 03U1.761L1 14 Between D&E Buttress WKWY-CD-5 VT-3C, direct 03UI-LOO1, 03UI-L003 03UI-761L1 15 Buttress C WKWY-CD-5 VT-3C, remote 03UI-LOOI 03UI-761L1 16 Between C&D Buttress WKWY-CD-5 VT-3C, remote 03UI-L001 03U1.761L1 17 Buttress D WKWY-CD-5 VT-3C, remote 03UI-L001 03U1 *761L1 18 Between D&E Buttress WKWY-CD-5 VT-3C, remote 03UI-LOOI 03UI-761L1 19 Buttress E WKWY-CD-5 VT-3C, remote 03UI-LOOI 03UI-761L120 Between C&D Buttress WKWY-CD-6 VT-3C, direct 03UI-L003 03UI-761L121 Buttress D WKWY-CD-6 VT-3C, direct 03UI-L001, 03UI-L003 Page 16 of 19

Nuclear Management Power Company Commercial Service Date: 12/21/70 700 First Street Docket 50-266 Iludson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03UI-761L122 Buttress C WKWY-CD-6 VT-3C, remote 03UI-L00I 03UI-761L123 Between C&D Buttress WKWY-CD-6 VT-3C, remote 03UI-L0I0 03UI-761L124 Buttress D WKWY-CD-6 VT-3C, remote 03UI-LO01 03UI-76IL125 Between C&D Buttress PLTF-D-2 VT-3C, direct 03UI-761L126 Buttress D PLTF-D-2 VT-3C, direct 03UI-LOI 03UI-761L127 Between C&D Buttress PLTF-D-2 VT-3C, remote 03UI-761L128 Buttress D PLTF-D-2 VT-3C, remote 03UI-LOOI 03UI-76IL129 Buttress D PLTF-D-I VT-3C, direct 03UI-L0I0 03UI-76IL130 Between D&E Buttress PLTF-D-I VT-3C, direct 03UI-761L131 Buttress D PLTF-D-I VT-3C, remote 03UI-LOOI 03UI-761L132 Between D&E Buttress PLTF-D-I VT-3C, remote 03UI-761L133 Between D&E Buttress PLTF-DE-I VT-3C, remote 03UI-LOOI 03UI-761L134 Buttress E PLTF-DE-I VT-3C, remote 03UI-LOOI 03UI-761L135 Between C&D Buttress Pipeway #1 VT-3C, direct 03UI-761L136 Between D&E Buttress Pipeway #2 Lower VT-3C. direct 03UI -LOOI 03UI-76IL137 Between D&E Buttress Pipeway #2 Upper VT-3C, direct 03UI-L00I, 03UI-L002 03UI-761L138 End Anchorage V-5 (Dome) VT-IC, direct 03UI-761L139 End Anchorage V-5 (Tendon Gallery) VT-IC, direct 03UI-L002 03UI-761L140 End Anchorage V-32 (Dome) VT-IC, direct 03UI-761L141 End Anchorage V-32 (Tendon Gallery) VT-IC, direct 03UI-761L142 End Anchorage V-88 (Dome) VT-IC, direct 03UI-761L143 End Anchorage V-88 (Tendon Gallery) VT-IC, direct 03UI-76IL144 End Anchorage V-144 (Dome) VT-IC, direct 03UI-761L145 End Anchorage V-144 (Tendon Gallery) VT-IC, direct 03UI-761L146 End Anchorage AC-I9 (Buttress A) VT-IC, direct 03UI-761L147 End Anchorage AC-19 (Buttress C) VT-IC, direct 03UI-761L148 End Anchorage BF-25 (Buttress B) VT-IC, direct 03UI-761L149 End Anchorage BF-25 (Buttress F) VT-IC, direct 03UI-761L150 End Anchorage CE-7 (Buttress C) VT-IC, direct 03UI-761L151 End Anchorage CE-7 (Buttress E) VT-IC, direct 03UI-761L152 End Anchorage DF-46 (Buttress D) VT-IC, direct Page 17 of 19

Nuclear Management Power Company Commercial Service Date: 12/21/70 700 First Street Docket 50-266 Iludson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03UI-761L153 End Anchorage DF-46 (Buttress F) VT-IC, direct 03UI-761L154 End Anchorage EA-45 (Buttress A) VT-IC, direct 03UI-761L155 End Anchorage EA-45 (Buttress E) VT-IC, direct 03UI-761L156 End Anchorage DI-38 (Field end) VT-IC, direct 03UI-761L157 End Anchorage DI-38 (Shop end) VT-IC, direct 03UI-761L158 End Anchorage D2-25 (Field end) VT-IC, direct 03UI-761L159 End Anchorage D2-25 (Shop end) VT-IC, direct 03UI-761L160 End Anchorage D3-9 (Field end) VT-IC, direct 03UI-761L161 End Anchorage D3-9 (Shop end) VT-IC, direct 03UI-761L162 End Anchorage DF-55 (Buttress D) VT-IC, direct 03UI-761L163 End Anchorage DF-55 (Buttress F) VT-IC, direct 03UI-761L164 End Anchorage D3-15 (Field end) VT-IC, direct 03UI-761L165 End Anchorage D3-15 (Shop end) VT-I C, direct 03UI-761L166 End Anchorage DI-36 (Field end) VT-IC, direct 03UI-761L167 End Anchorage Dl-36 (Shop end) VT-IC, direct 03UI-761L168 End Anchorage V-S (Dome) VT-I, direct 03UI.761L169 End Anchorage V-5 (Tendon Gallery) VT-I, direct 03UI-761L170 End Anchorage V-32 (Dome) VT-I, direct 03UI-761L171 End Anchorage V-32 (Tendon Gallery) VT-I, direct 03UI-761L172 End Anchorage V-88 (Dome) VT-I, direct 03UI-76IL173 End Anchorage V-88 (Tendon Gallery) VT-I, direct 03UI-761L174 End Anchorage V-144 (Dome) VT-I, direct 03UI-761L175 End Anchorage V-144 (Tendon Gallery) VT-I, direct 03UI-761L176 End Anchorage AC-I9 (Buttress A) VT-I, direct 03UI-761L177 End Anchorage AC-19 (Buttress C) VT-I, direct 03UI-761L178 End Anchorage BF-25 (Buttress B) VT-I, direct 03UI-761L179 End Anchorage BF-25 (Buttress F) VT-I, direct 03U1-761L180 End Anchorage CE-7 (Buttress C) VT-I, direct 03UI-761 Li 81 End Anchorage CE-7 (Buttress E) VT-I, direct 03UI-761L182 End Anchorage DF-46 (Buttress D) VT-I, direct 03UI-761L183 End Anchorage DF-46 (Buttress F) VT-I,direct 03UI-L004 Page 18 of 19

Nuclear Management Power Company Commercial Service Date: 12/21/7o 700 First Street Docket 50-266 Hludson, Wisconsin 54016 Pt. Beach Unit I National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03UI-761L184 End Anchorage EA-45 (Buttress E) VT-I, direct 03UI-761L185 End Anchorage EA-45 (Buttress A) VT-I, direct 03UI-761L186 End Anchorage DI-38 (Field end) VT-I, direct 03UI-761L187 End Anchorage DI-38 (Shop end) VT-I, direct 03UI-761L188 End Anchorage D2-25 (Field end) VT-I, direct 03UI-761L189 End Anchorage D2-25 (Shop end) VT-I, direct 03UI-761L190 End Anchorage D3-9 (Field end) VT-I, direct 03UI-761L191 End Anchorage D3-9 (Shop end) VT-I, direct 03UI-761L192 End Anchorage DF-55 (Buttress D) VT-I, direct 03UI-761L193 End Anchorage DF-55 (Buttress F) VT-I, direct 03UI-761L194 End Anchorage D3-15 (Field End) VT-I, direct 03UI-761L195 End Anchorage D3-15 (Shop End) VT-I, direct 03U1.761L196 End Anchorage DI-36 (Field End) VT-I, direct 03UI-761L197 End Anchorage Dl-36 (Shop End) VT-I, direct Page 19 of 19

NIS-1 Inservice Inspection Summary Report for Unit 2 IWL Nuclear Management Company, LLC 700 First Street Hudson, Wisconsin 54016 Point Beach Nuclear Plant Unit 2 6610 Nuclear Road Two Rivers, Wisconsin 54241 Commercial Operating Date: October 1, 1972 Report Date: February 11, 2004 Written by: C c- Date: : .- /D Y Reviewed by: .E Date: By Approved by: o k* /' Date:

FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS

1. Owner: Nuclear Management Company, 700 First Street Hudson, Wisconsin 54016

2. Plant: Point Beach Nuclear Plant, 6610 Nuclear Road, Two Rivers, Wisconsin 54241

3. Plant Unit: 2 4. Owner Certificate of Authorization: Docket 50-301

5. Commercial Service Date: October 1, 1972 6. National Board Number for Unit: N/A

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

Containment Bechtel N/A U009972 N/A t t 1- 1-t 4- 4-4- I-t .t 1 1-4 4 4-4 4 4-Bechtel Group, Inc.

2280 Bates Avenue Concord, CA 94520

8. Examination Dates: September 10, 2001 to February 11, 2004.

9. Inspection Period Identification: N/A

10. Inspection Interval Identification: N/A

11. Applicable Editions of Section XI: 1992 Edition Addenda 1992

12. Date / Revision of Inspection Plan: October 25, 2002 / rev. 1

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

An Inservice Examination of containment concrete Class CC components of Nuclear Management Company (NMC) Point Beach Nuclear Plant (PBNP) Unit 2 was performed during the time period of September 10, 2001 to February 11, 2004.

Page 2 of 15

The concrete was examined in accordance with the IWL Containment Inspection Program, which was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1992 Edition, 1992 Addenda and 10 CFR 50.55a.

No Code Cases were used in the performance of examinations, tests, and repairs and replacements.

The visual tendon surveillance was completed during the implementation period in accordance with Technical Specifications. Precision Surveillance Corporation and WE Energies personnel performed this surveillance. See Attachment 1 for test results.

Visual examinations were conducted in accordance with ASME Section XI to meet examination Category L-A, Item L1.1 1 for VT-3C and Item L1.12 for VT-IC. WE Energies, Nuclear Management Company, and Lambert MacGill Thomas, Inc. personnel performed the examinations.

Visual examinations were not conducted at the same time as the tendon surveillance due to incorporation of relief requests in the ASME Section XI visual examination program. See for test results.

No repairs and replacements have been performed on Class CC components during this IWL implementation period.

All examinations required for the 33rd year tendon surveillance been completed. This meets the requirements of ASME Section XI and applicable relief requests.

14. Abstract of Conditions Noted:

• Grease Leakage Areas of grease leakage at the tendon grease cans and through concrete leakage were recorded. No appreciable change was noted from conditions recorded during the 2001 concrete examination.

• Grease Voids Grease voids greater than 5% duct volume were noted in five Unit 2 tendons with three of these exceeding 10% duct volume.

• Exposed Reinforcing Steel Areas of exposed reinforcing steel were recorded. There was no measurable difference since the 2001 examinations

• Concrete Cracking The concrete cracking recorded showed no change with previously recorded indications.

One area of concrete damage was noted that was not previously recorded.

Page 3 of 15

15. Abstract of Corrective Measures Recommended and Taken.

• Grease Leakage Additional corrective maintenance will be pursued to correct grease leakage points.

• Grease Voids Tendons with the grease voids were refilled after completion of the visual examinations.

• Exposed Reinforcing Steel No corrective measures are recommended for these construction defects.

• Concrete Cracking Trending of existing cracks will continue to verify stability of concrete.

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 Authorization No. (if applicable): NRC Docket 50-301 Expiration Date: N/A Date: z- t-° OV Signed: Nuclear Management Co., LLC by Owner 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 or Province of Wisconsin and employed by Hartford Steam Boiler of Hartford Connecticut, have inspected the components described in this Owner's Report during the period September 10, 2001 to February 11, 2004, 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 Owner'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 insp n.

Commissions WI 247972 tor's Signature National Board, State, Province, and Endorsements Date x-lv_ A/

Page 4 of 15

Nuclear Management Company Commercial Service Date: 10/1n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A Attachment 1 Unit 2 Thirty-three Year Tendon Surveillance Summary Page 5 of 15

33 rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT BEACH NUCLEAR PLANT Committed to Nuclear Excellence TABLE I: LABORATORY ANALYSIS OF SHEATHING FILLER UNIT 2 TENDON END ION CONCENTRATION (PPM)  % WATER NEUTRAL No.

CHLORIDE SULFIDE NITRATE CONTENT mg KOH/g HK-10 SHOPIBUTT.H. <0.50 <0.50 <0.50 0.19 <0.50 KM-60 SHOP/BUTT.K <0.50 <0.50 <0.50 <0.10 0.510 MH-56 SHOP/BUTT. H <0.50 <0.50 <0.50 <0.10 8.24 JL-30 SHOP/BUTT.J <0.50 <0.50 <0.50 0.18 3.08 GL-7 SHOP/BU1T.G <0.50 0.50 < 0 0

<0.59'-'

<0.10 -

-i-11.4 V-217 SHOP/TOP <0.50 <0.50 <0.50 0.30 <0.50 V-243 SHOP/TOP <0.50 <0.50 <0.50 0.20 1 2.58 V-273 SHOP/TOP <0.50 <0.50 <0.50 0.30 <0.50 V-328 SHOP/TOP <0.50 <0.50 <0.50 0.28 . <0.50 V-337 SHOP/TOP <0.50 <0.50 <0.50 <0.10 <0.50 D1-216 SHOP/NEAR H <0.50 <0.50 <0.50 0.20 <0.50 D2-230 SHOP/NEAR G 0.50 <0.50 <0.50 0.29 <0.50 D3-221 SHOP/NEARJ 0.50 <0.50 <0.50 <0.10 <0.50 D3-226 SHOP/NEAR J <0.50 <0.50 <0.50 0.20 5.69 Acceptance Limits Test Limits Water Soluble Chloride Less than 10.0 ppm Water Soluble Nitrates Less than 10.0 ppm Water Soluble Sulfides Less than 10.0 ppm Water Content Less than 10% Dry Weight Neutralization No. Greater than 0 mg KOH/g

33 rd YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT NMC )

Committed to Nuclear Excellence BEACH NUCLEAR PLANT

'ISISA TABLE XI:

SUMMARY

OF DATA SHEETS SQ 12.1 GREASE LOSS Vs GREASE REPLACEMENT UNIT 2 TENDON GREASE REMOVED GREASE REPLACED DIFF. NET  %

SHOP FIELD TOTAL SHOP FIELD TOTAL (GAL.) VOLUME (GAL.) (GAL.)

HK-10 1.75 1.75 3.50 2.0 2.0 4.0 +0.50 56.27 +0.88 KM-60 2.25 1.75 4.00 2.50 1.75 4.25 +0.25 56.65 +0.44 MH-56 2.25 2.50 4.75 2.50 2.50 5.00 +0.25 56.31 +0.44 JL-30 1.75 1.75 3.50 2.00 2.00 4.00 +0.50 56.73 +0.88 GL-7 1.75 1.75 3.50 2.00 2.00 4.00 +0.50 56.53 +0.88 V-217 1.25 17.25 18.50 0.25 24.75 25.00 6.50 67.02 +9.69+

V-243 2.75 32.25 35.00 0.25 39.00 39.25 4.25 67.10* +6.30^

V-273 2.25 20.25 22.50 0.25- 35.50 35.75 13.25 67.45 +19.60-V-328 1.25 31.25 32.50 0.25 42.50 42.75 10.25 67.14 +15.26+

V-337 3.25 27.25 30.50 0.25 31.75 32.00 1.50 66.79 +2.60 D1-216 5.75 4.00 9.75 6.00 4.25 10.25 0.50 53.18 +0.94 D2-230 18.00 6.75 24.75 0.25 25.75 26.00 1.25 55.03 +2.27 D3-221 6.75 4.25 11.00 7.25 4.75 12.00 1.00 54.77* +1.80 D3-226 17.25 N/A 17.25 25.50 0.00 25.50 8.25 56.10 +14.70+

- Ref. NCR# FN885-001

+ Ref. NCR# FN885-002

• Ref. NCR# FN885-003

- L - I 33r YEAR UNIT 1 PHYSICAL AND UNIT 2 VISUAL TENDON SURVEILLANCE AT THE POINT NMIC Cemwed to Ntchear &edlhncf BEACH NUCLEAR PLANT TABLE VIII:

SUMMARY

OF DATA SHEETS SQ 9.0 - TENDON LIFTOFFS UNIT 2 TENDON I

END EFFECT. JACK PRESS. LIFTOFFf WIRES No. I_ I_

AVE.

l_LIFTOFF LOWER LIMIT 95% 90% JUPPER LOWER LOWERI LIMIT I IACCEPT MH-56 SHOP/ BUTT.H 89 6001 3360 637.1 638.7 594.5 564.8 535.1 656.8 YES FIELD/BUTT.M 89 6002 3390 640.3 V-337 SHOP/TOP 90 6002 3420 646 646 628.2 596.8 565.4 672.3 YES D2-230 SHOP/NEAR G 90 6002 3350 632.7 633.6 613.8 583.1 552.4 666.0 YES FIELD/NEAR K 90 6002 3360 634.6 l 1 1 1 I

Nuclear Management Company Commercial Service Date: 10/1n2 700 First Street Docket 50-301 Hudson, Wisconsin 54016 PL Beach Unit 2 National Board Number for Unit: N/A Attachment 2 Unit 2 IWL Containment Concrete Examination Summary Page 9 of 15

Nuclear Management Company Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U2-76IL001 Tendon Gallery Ceiling Tendon Gallery VT-IC, direct 03U2-L003 03U2-761LD02 Tendon Gallery Ceiling Tendon Gallery VT-IC, direct 03U2-.L003 03U2-76H.L03 Tendon Gallery Ceiling Tendon Gallery VT-IC, direct 03U2-1-003 03U2-761L004 Tendon Gallery Ceiling Tendon Gallery VT-IC, direct 03U2-L003 03U2-761LO05 Tendon Gallery Ceiling Tendon Gallery VT-3C, direct 03U2-1.001, 03U2-1-003 03U2-761 LO06 Tendon Gallery Inner Wall Tendon Gallery VT-3C, direct 03U2-1-002 03U2-76IL007 Tendon Gallery Outer Wall Tendon Gallery VT-3C, direct 03U2-1-002 03U2-7611,008 Dome Dome VT-3C, direct 03U2-LOOI, 03U2-L002 03U2-761 [009 Dome LDR-G-I VT-3C, direct 03U2-761L010 Dome PLTF-G-I VT-3C, direct 03U2.LOOI 03U2-761L011I Dome PLTF-G-I VT-3C, remote 03U2-tL.00 03U2.761L012 Dome LDR-H-S VT-3C, direct 03U2-761 [013 Dome PLTF-H1-3 VT-3C, direct 03U2-L.001 03U2-761L014 Dome PLTF-H-3 VT-3C, remote 03U2-LOOI 03U2.761L01 5 Dome LDR-J-I VT-3C, direct 03 J2-761 L01 6 Dome PLTFJl-l VT-3C, direct 03U2-LOOI, 03U1-L002 03U2-761L017 Dome PLTF-J-I VT-3C, remote 03U2-761L018 Dome LDR.K-4 VT-3C, direct 03U2.761L019 Dome PLTF-K-3 VT-3C, direct 03U2-LOOI 03U2-761L020 Dome PLTF-K-3 VT-3C, remote 03U2-LOOI 03U2.761L021 Dome LDR-L-I VT-3C, direct 03U2-761 [022 Dome PLTF-L-I VT-3C, direct 03U2-761L023 Dome PLTF-L-I VT-3C, remote 03U2-761 [024 Dome LDR-M-2 VT-3C, direct 03U2-761L025 Dome PLTF-M-3 VT-3C, direct 03U2-LD02 03U2-761 [026 Domne PLTF-M-3 VT-3C, remote 03U2-761L027 Buttress G Facade 6.5 ft el VT-3C, direct 03U2-L.001 03U2-761L028 Between G&H Buttress Facade 6.5 f el VT-3C, direct 03U2-1.003 03U2-761L029 Buttress 11 Facade 6.5 ft el VT-3C, direct 03U2-1-001 Page 10 of 15

Nuclear Management Company Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U2-761L030 Between ll&J Buttress Facade 6.5 ft el VT-3C, direct 03U2-761 [031 Buttress J Facade 6.5 ft el VT.3C, direct 03U2-LOOI 03U2-761L032 Between J&K Buttress Facade 6.5 ft el VT-3C, direct 03U2-L0OI 03U2.761 [033 Buttress K Facade 6.5 ft el VT-3C, direct 03U2-761L034 Between K&L Buttress Facade 6.5 ft el VT-3C, direct 03U2-761 [035 Buttress L Facade 6.5 fn el VT-3C, direct 03U2-LOOI 03U2-761 [036 Between L&M Buttress Facade 6.5 f el VT-3C, direct 03U2-1,OOI. 03U2-L002,03U2-L003 03U2-761 [037 Buttress M Facade 6.5 ft el VT-3C, remote 03U2.L0OI 03U2-761L038 Between M&G Buttress Facade 6.5 ft el VT-3C, direct 03U2-L00OI, 03U2-1,003 03UJ2-761L039 Buttress G Facade 6.5 ft el VT-3C, remote 03U2-LO0l, 03U2-L[002 03U2-761L040 Between G&Il Buttress Facade 6.5 n el VT-3C, remote 03U2-761L041 Buttress If Facade 6.5 ft el VT-3C, remote 03U2-LOOI 03U2-761L042 Between H&J Buttress Facade 6.5 ftc VT-3C, remote 03U.2-761 [043 Buttress J Facade 6.5 ft el VT-3C, remote 03U2.LOOI 03U2-761L044 Between J&K Buttress Facade 6.5 ft el VT-3C, remote 03U2-761L045 Buttress K Facade 6.5 ftn VT-3C, remote 03U2-LOOI 03U2-761 [046 Between K&L Buttress Facade 6.5 ft el VT-3C, remote 03U2-761[047 Buttress L Facade 6.5 ft el VT-3C, remote 03U2-761[048 Between L&M Buttress Facade 6.5 f el VT-3C, remote 03U2-761[049 Buttress M Facade 6.5 ft el VT-3C, direct 03U2.LOO01, 03U2-L002 03U2-761[050 Between M&G Buttress Facade 6.5 ftn VT-3C, remote 03U2-LOOI 03U2-761[051 Between G&H Buttress PLTF-II-I VT-3C, direct 03U2-761L052 Between G&H Buttress PLTF-II.1 VT-3C, remote 03U2-761L053 Buttress H LDR-II-. VT-3C, direct 03U2-761L054 Buttress H PLTF-1I.I VT-3C, direct 03U21.001I 03U2.761 [055 Buttress H PLTF-II-1 VT-3C, remote 03U2.LOOI 03U2-761L056 Buttress H LDR-H-2 VT-3C, direct 03U2.761L058 Buttress H LDR-H-3 VT-3C, direct 03U2-761L059 Buttress 11 LDR-H14 VT-3C, direct 03U2-761L060 Buttress H PLTT-11-2 VT-3C, direct 03U2.1-001 03U2-761L061 Buttress H PLTF-11-2 VT-3C, remote 03U2.LOOI, 03U2-L002 Page 11 of 15

Nuclear Management Company Commercial Service Date: 10/1/72 700 First Street Docket 50-301 IHudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet# Concrete Area Examination Location Exam Type IDR 03U2-761 L062 Between H&J Buttress PLTF-11-2 VT-3C, direct 03U2.761L063 Between H&J Buttress PLTF-IJ-2 VT-3C, remote 03U2-L002 03U2-761L064 Buttress J evap bldg ladder VT-3C, direct 03U2-761L065 Buttress I evap bldg landing VT-3C, direct 03U2-761L066 Between J&K Buttress evap bldg landing VT-3C, direct 03U2-761 L067 Between IJ&J Buttress evap bldg landing VT-3C, remote 03U2-761 L068 Buttress J evap bldg landing VT-3C, remote 03U2-LOOI 03U2-761 L069 Between J&K Buttress evap bldg landing VT-3C, remote 03U2-761L070 Between J&K Buttress PLTF-K-2 VT-3C, direct 03U2-761 L071 Between J&K Buttress PLTF-K-2 VT-3C, remote 03U2-761 L072 Buttress K LDR-K-I VT-3C, direct 03U2-761L073 Buttress K LDR-K-2 VT-3C, direct 03U2.761L074 Buttress K PLTF-K-1 VT-3C, direct 03U2-LOOI 03U2.761L075 Between K&L Buttress PLTF-K-I VT-3C, direct 03U2-L003 03U2-761 L076 Between K&L Buttress PLTF-K-I VT-3C, remote 03U2-761 L077 Buttress K PLTF-K-1 VT-3C, remote 03U2-LOOI 03U2-761L078 Buttress K LDR-K-3 VT-3C, direct 03U2.761L079 Buttress K PLTF-K-2 VT-3C, direct 03U2-LOOI 03U2-761L080 Buttress K PLTr-K-2 VT-3C, remote 03U2-LOOI 03U2-761L08 1 Between L&M Buttress WKWY-LM-I VT-3C, direct 03U2-LOOI, 03U2-L003 03U2-761L082 Buttress L WK WY-LM-1 VT-3C, remote 03U2-LOOI 03U2-761 L083 Between L&M Buttress WKWY-LM-1 VT-3C, remote 03U2-761 L084 Buttress M WKWY-LM- VT-3C, remote 03U2-LOOI 03U2-761L085 Between L&M Buttress WKWY-LM-2 VT-3C, remote 03U2-LOO1, 03U2-L002 03U2-761L086 Between K&L Buttress Pipeway #3 Upper (on top) VT-3C, direct 03U2-L002 03U2-761 L087 Between K&L Buttress Pipeway #3 Upper (on top) VT-3C, remote 03U2-LOOI, 03U2-L002 03U2-761L088 Between L&M Buttress WKWY-LM-3 VT-3C, direct 03U2-LOOI 03U2-761L089 Buttress L WKEWY-LM-3 VT-3C, remote 03U2-LOOI 03U2-761 L090 Between L&M Buttress WKWY-LM-3 VT-3C, remote 03U2-LOOI 03U2-761 L091 Buttress M WKWY-LM-3 VT-3C, remote 03U2-761 L092 Between L&M Buttress WKWY-LM-4 VT-3C, direct Page 12 of 15

Nuclear Management Company Commercial Service Date: 10o/l72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U2-761 L093 Buttress L WKWY-LM-4 VT-3C, remote 03U2-LOOI 03U2-761 L094 Between L&M Buttress WKWY-LM-4 VT-3C, remote 03U2-LOOI 03U2-761 L095 Buttress M WKWY-LM-4 VT-3C, remote 03U2-LOOI 03U2-761 L096 Between K&L Buttress WKWY-LM-5 VT-3C, direct 03U2.LOOI. 03U2-L003 03U2-761L097 Buttress L WKWY-LM-5 VT-3C, direct 03U2-LOOI 03U2-761L098 Between L&M Buttress WKWY-LM-5 VT-3C, direct 03U2.L002, 03U2.L003 03U2-761L099 Buttress K WKWY-LM-5 VT-3C, remote 03U2.LOOI 03U2-761L100 Between K&L Buttress WKWY-LM-5 VT-3C, remote 03U2.LOOI. 03U2-L0D02.03U2-L003 03U2-761L101 Buttress L WKWY-LM-5 VT-3C, remote 03U2.LOOI 03U2-761L102 Between L&M Buttress WKWY-LM-5 VT-3C, remote 03U2-761L103 Buttress M WKWY-LM-5 VT-3C, remote 03U2.LOOI 03U2-761L104 Between L&M Buttress WKWY-LM-6 VT-3C, direct 03U2-L002, 03U2-L003 03U2-761L105 Buttress L WKWY-LM-6 VT-3C, remote 03U2-LOOI 03U2-761L106 Between L&M Buttress WKWY-LM-6 VT-3C, remote 03U2-761L107 Buttress M WKWY-LM-6 VT-3C, remote 03U2-761 L108 Between L&M Buttress PLTF-M-2 VT-3C, direct 03U2-761 L109 Buttress M PLTF-M-2 VT-3C, direct 03U2.LOOI 03U2-761L1 10 Between L&M Buttress PLTF-M-2 VT-3C, remote 03U2-761LI I I Buttress M PLTF-M-2 VT-3C, remote 03U2.LOOI 03U2-761L112 Buttress M LDR-M-I VT-3C, direct 03U2-76 Ll 13 Buttress M PLTF-M-I VT-3C, direct 03U2.LOOI 03U2-76 Ll 14 Between M&O Buttress PLTF-M-I VT-3C, direct 03U2-761L1 15 Buttress M PLTF-M-I VT-3C, remote 03U2.LOOI 03U2-761L1 16 Between M&G Buttress PLTF-M-I VT-3C, remote 03U2-761L1 17 Between M&G Buttress Equipment hatch walkway VT-3C, direct 03U2.761L1 18 Between M&G Buttress Equipment hatch walkway VT-3C, remote 03U2-761Ll 19 Buttress M Equipment hatch walkway VT-3C, remote 03U2.LOOI 03U2-761L120 Buttress M gas stripper bldg. Platform VT-3C, remote 03U2-L00OI 03U2-761L121 Between M&G Buttress gas stripper bldg. Platform VT-3C, remote 03U2.LOOI 03U2-761L122 Between K&L Buttress Pipeway #3 Lower VT-3C, direct 03U2-LOOI 03U2-761L123 Between L&M Buttress Pipeway #4 VT-3C, direct 03U2.LOOI Page 13 of 15

Nuclear Management Company Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U2-761L124 Between K&L Buttress Pipeway #3 Upper VT-3C, direct 03U2-L)DOI 03U2-761L125 End Anchorage V-217 (Dome) VT-IC, direct 03U2-761L126 End Anchorage V-217 (Tendon Gallery) VT-IC, direct 03U2-761 L127 End Anchorage V-273 (Dome) VT-IC, direct 03U2-76I L128 End Anchorage V-273 (Tendon Gallery) VT-IC, direct 03U2-761L129 End Anchorage V-328 (Dome) VT-IC, direct 03U2-LOOI 03U2-76IL130 End Anchorage V-328 (Tendon Gallery) VT-IC, direct 03U2-76IL131 End Anchorage V-337 (Dome) VT-IC, direct 03U2-LDD2 03U2-761L132 End Anchorage V-337 (Tendon Gallery) VT-IC, direct 03U2-761L133 End Anchorage GL-7 (Buttress L) VT-IC, direct 03U2-76IL134 End Anchorage GL-7 (Buttress G) VT-IC, direct 03U2-761L135 End Anchorage HK-I0 (Buttress H) VT-IC, direct 03U2-LOO1 03U2-761L136 End Anchorage HK-10 (Buttress K) VT-IC, direct 03U2-761 L137 End Anchorage JL-30 (Buttress J) VT-IC, direct 03U2-76IL138 End Anchorage JL-30 (Buttress L) VT-IC, direct 03U2-L002 03U2-76IL139 End Anchorage KM-60 (Buttress M) VT-IC, direct 03U2-76IL140 End Anchorage KM-60 (Buttress K) VT-IC, direct 03U2-761L141 End Anchorage MH-56 (Buttress M) VT-IC, direct 03U2-76IL142 End Anchorage MH-56 (Buttress H) VT-IC, direct 03U2-76IL143 End Anchorage DI-216 (Field end) VT-IC, direct 03U2-76IL144 End Anchorage DI-216 (Shop end) VT-IC, direct 03U2-76IL145 End Anchorage D2-230 (Field end) VT-IC, direct 03U2-76I L146 End Anchorage D2-230 (Shop end) VT-IC, direct 03U2-761 L147 End Anchorage D3-226 (Field end) VT-IC, direct 03U2-761L148 End Anchorage D3-226 (Shop end) VT-IC, direct 03U2-761L149 End Anchorage V-217 (Dome) VT-I, direct 03U2-761L150 End Anchorage V-217 (Tendon Gallery) VT-I, direct 03U2-761 L151 End Anchorage V-273 (Dome) VT-I, direct 03U2-LO04 03U2-76IL152 End Anchorage V-273 (Tendon Gallery) VT-I, direct 03U2-761L153 End Anchorage V-328 (Dome) VT-I, direct 03U2-761L154 End Anchorage V-328 (Tendon Gallery) VT-I, direct Page 14 of 15

Nuclear Management Company Commercial Service Date: 10/1/72 700 First Street Docket 50-301 IHudson, Wisconsin 54016 Pt. Beach Unit 2 National Board Number for Unit: N/A NDE Data Sheet # Concrete Area Examination Location Exam Type IDR 03U2-761 L155 End Anchorage V-337 (Dome) VT-I, direct 03U2-761L156 End Anchorage V-337 (Tendon Gallery) VT-I, direct 03U2-761 L157 End Anchorage GL-7 (Buttress L) VT-I, direct 03U2-761L158 End Anchorage GL-7 (Buttress G) VT-I, direct 03U2-761LI59 End Anchorage IIK-IO (Buttress 11) VT-I, direct 03U2-76IL160 End Anchorage IIK IO (Buttress K) VT-I, direct 03U2-761L161 End Anchorage JL-30 (Buttress J) VT-I, direct 03U2-76IL162 End Anchorage JL-30 (Buttress L) VT-I, direct 03U2-761L163 End Anchorage KM-60 (Buttress M) VT-I, direct 03U2-761L164 End Anchorage KM-60 (Buttress K) VT-I, direct 03U2-761L165 End Anchorage M11-56 (Buttress M) VT-I, direct 03U2-L004 03U2-761 L166 End Anchorage MH-56 (Buttress H) VT-I, direct 03U2-L004 03U2-76I L167 End Anchorage DI-216 (Field end) VT-I, direct 03U2-76IL168 End Anchorage DI-216 (Shop end) VT-I, direct 03U2-761L169 End Anchorage D2-230 (Field end) VT-I, direct 03U2-761L170 End Anchorage D2-230 (Shop end) VT-I, direct 03U2-761L171 End Anchorage D3-226 (Field end) VT-I, direct 03U2-761L172 End Anchorage D3-226 (Shop end) VT-I, direct Page 15 of 15