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

{{Adams
| number = ML040560544
| issue date = 02/19/2004
| title = Filing of Owner'S Inservice Inspection Summary Report for Refueling Outage U2R26 and 33rd Year Tendon Surveillance and Concrete Examination
| author name = Vanmiddlesworth G
| author affiliation = Nuclear Management Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000266, 05000301
| license number = DPR-024, DPR-027
| contact person = 
| case reference number = NRC 2004-0020
| document type = Inservice/Preservice Inspection and Test Report, Letter type:NRC
| page count = 136
}}

=Text=
{{#Wiki_filter: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 &sect;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          &deg;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:           /&deg; .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           &deg;^'. 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-&deg; 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}}