NRC 2002-0069, Filing of Owner'S Inservice Inspection Summary Report
ML022490279 | |
Person / Time | |
---|---|
Site: | Point Beach |
Issue date: | 08/15/2002 |
From: | Webb T Nuclear Management Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
NRC 2002-0069 | |
Download: ML022490279 (116) | |
Text
Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, Wl 54216-9511 Two Rivers, Wl 54241 920 388.2560 920 755 2321 NMC Committed to Nuclear Excellence. Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC 2002-0069 August 15, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Ladies/Gentlemen:
Docket 50-301 Point Beach Nuclear Plant, Unit 2 Filing of Owner's Inservice Inspection Summary Report Enclosed is the Owner's Inservice Inspection Summary Report. This report is submitted in accordance with ASME Section XI, Subsection IWA-6230. This submittal includes the NIS-I Inservice Inspection Summary Report, the NIS-I Owner's Report for Inservice Inspections, and the Repair/Replacement Summary Report for Form NIS-2 as required by IWA-6000 of the 1986 Edition of ASME Section XI.
The information contained in the enclosed reports reflect inservice inspection activities conducted since the previous submittal and includes the second outage of the third period of the third ten-year interval at Point Beach Nuclear Plant Unit 2. This is the final submittal for the third inservice inspection interval for Point Beach Nuclear Plant Unit 2.
Sincerely, Licensing Director LAS/kmd Enclosures cc: NRC Resident Inspector NRC Regional Administrator NRC NRR Project Manager PSCW Mike Verhagen, State of Wisconsin AbqY7
1 NIS-1 INSERVICE INSPECTION
SUMMARY
REPORT 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: August 12, 2002 Date: 1 V'2 Written by: a Reviewed by: Date: a 0 Approved by: 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 Installer No. No. No.
Appurtenance Containment Bechtel N/A U009972 N/A Bechtel Group, Inc.
2280 Bates Avenue Concord, CA 94520
- 8. Examination Dates: September 9, 2001 to May 14, 2002
- 9. Inspection Period Identification: Second Period (Implementation 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 status
- 13. Abstract of Examinations. Include a list of examinations and a statement concerning of work required for current Interval.
Energies An Inservice Examination of containment metallic liner Class MC components of We of September 9, Point Beach Nuclear Plant (PBNP) Unit 2 was performed during the time period 2001 to May 14, 2002. This was the second period of the first ten-year interval.
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.
No Code Cases were used in the performance of examinations, tests, and repairs and replacements.
Page 2 of 6
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 was one replacement performed on Class MC components during this IWE exam report.
RRM 2002-0040 replaced the C-3 fuel transfer tube flange bolting. The original bolting was misplaced following completion of the refueling outage.
This exam meets the requirements of Inspection Program B of ASME Section XI with approximately 40 % examination completed for the interval.
- 14. Abstract of Conditions Noted:
Containment Liner Plates One liner plate contained surface corrosion where paint had been removed but no loss of base metal was noted.
Moisture Barrier Two areas of poor adhesion were noted.
- 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.
Moisture Barrier Moisture barrier will be repaired next outage. The poor adhesion is not an immediate concern for degradation to the liner plate.
Page 3 of 6
tests We certify that a) the statements made in this report are correct, b) the examinations and measures meet the Inspection Plan as required by the ASME Code,Section XI and c) corrective taken conform to the rules of the ASME Code,Section XI.
Date: N/A Certificate of Authorization No. (if applicable): NRC Docket 50-301 Expiration Date: -//Iq V 7 -0o0 Signed: Nuclear Management Co., LLC by ,
Owner CERTIFICATE OF INSERVICE INSPECTION of Boiler I, the undersigned, holding a valid commission issued by the National Board employed by and Pressure Vessel Inspectors and the State or Province of Wisconsin and described in this Hartford Steam Boiler of Hartford Connecticut, have inspected the components that to the best Owner's Report during the period September 9, 2001 to May 14, 2002, and state and taken of my knowledge and belief, the Owner has performed examinations and tests the Inspection Plan and corrective measures described in this Owner's Report in accordance with as required by the ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, described in expressed or implied, concerning the examinations, tests, and corrective measures shall be liable in any this Owner's Report. Furthermore, neither the Inspector nor his employer from or manner for any personal injury or property damage or a loss of any kind arising connected with this inspection.
- _ 2.
,-.- Commissions WI-100128 N.x A.
Inspector's Signature National Board, State, Province, and Endorsements Date Page 4 of 6
I Commercial Service Date 10/01172 Nuclear Management Company Docket 50-301 700 First Street Pt Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit N/A Attachment 1 Unit 2 Refueling Outage 25 IWE Containment Inspection Program Examination Summary Page 5 of 6
Commercial Service Date: 10101/72 Nuclear Management Company Docket 50-301 700 First Street Pt Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit: N/A U2R25 IWE Exam Summa Exam Notes Component Category Item Type NDE Data Date RRM # IDR 2C-3 E-G E8.10 VT-I 02U2-760E032 5/2/2002 2002-0040 2CP-061 E-A 21.12 VT-3 02U2-760E001 5/2/2002 2CP-062 E-A E1.12 VT-3 02U2-760E002 5/2/2002 2CP-063 E-A E1.12 VT-3 02U2-760E003 5/2/2002 2CP-064 E-A E1.12 VT-3 02U2-760E004 4/27/2002 2CP-065 E-A El.12 VT-3 02U2-760E005 4/27/2002 2CP-066 E-A E1.12 VT-3 02U2-760E006 4/27/2002 2CP-067 E-A E1.12 VT-3 02U2-760E007 4/27/2002 2CP-068 E-A El.12 VT-3 02U2-760E008 5/2/2002 2CP-069 E-A E1.12 VT-3 02U2-760E009 5/2/2002 2CP-070 E-A El.12 VT-3 02U2-760E010 5/2/2002 2CP-071 E-A E1.12 VT-3 02U2-760E011 5/2/2002 2CP-072 E-A 21.12 VT-3 02U2-760E012 5/2/2002 2CP-073 E-A 21.12 VT-3 02U2-760E013 5/2/2002 2CP-074 E-A E1.12 VT-3 02U2-760E014 5/2/2002 2CP-075 E-A El 12 VT-3 02U2-760E015 4/27/2002 2CP-076 E-A 21.12 VT-3 02U2-760E016 5/3/2002 02U2-E001 2CP-077 E-A El 12 VT-3 02U2-760E017 4/27/2002 2CP-078 E-A E1.12 VT-3 02U2-760E018 4/27/2002 2CP-079 E-A 21.12 VT-3 02U2-760E019 4/27/2002 2CP-080 E-A 21.12 VT-3 02U2-760E020 4/27/2002 2CP-081 E-A E1.12 VT-3 02U2-760E021 4/27/2002 2CP-082 E-A E1.12 VT-3 02U2-760E022 4/27/2002 2CP-083 E-A 21.12 VT-3 02U2-760E023 4/27/2002 2CP-084 E-A 21.12 VT-3 02U2-760E024 4/27/2002 VT-3 02U2-760E025 5/2/2002 00U2-E020 re-exam 2CP- 116 VT-3 02U2-760E026 5/2/2002 00U2-E020 re-exam 2CP-127 VT -3 02U2-760E027 5/2/2002 00U2-E020 re-exam 2CP-128 E-A 121.12 VT-3 02U2-760E029 5/8/2002 In conjunction with WO 0202771 2CPP-56 EIn conjunction with WO 0202771 6E-G 28.10 VT-I 02U2-760030 5/15/2002 CAP003302, Wrong NDE datasheet E-D E5.30 VT-3 02U2-760E031 5/3/2002 02U2-E-002 I 2Z-529 Page 6 of 6
NIS-1 Inservice Inspection Summary Report For U2R25 Outage Nuclear Management Company 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: August 8, 2002 Written by: Date: f6P*!*oo Reviewed by: Date: zlylo 2 Approved by: Date:
Page 1 of 12
Commercial Service Date: 10/1/72 Nuclear Management Company LC Docket 50-301 700 First Street Point Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit NIA FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS
- 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 No. No. No.
Reactor Pressure Combustion 69101 U009973 NB-21009 Vessel Engineering Pressurizer Westinghouse T-1 U009979 68-5 NB-036 1 NB-0362 Regenerative Heat Sentry 3996A3-7 N/ANB06 Exchanger NB-0363 Steam Generator A Westinghouse SG2L-12172 U009974 NB-0059 Residual Heat Joseph Oats Removal Heat 1520-5 U009981 NB-0281 Exchanger A Residual Heat Joseph Oats Removal Heat 1520-6 U009982 NB-0280 Exchanger B Coman Class 1Piping Bechtel N/A N/A N/A Class 2 Piping Bechtel N/A N/A N/A Westinghouse Electric Company Bechtel Group, Inc.
4350 Northern Pike 2280 Bates Avenue Monroeville, PA 15146-2886 Concord, CA 94520 Combustion Engineering Sentry ABB Group 856 Armor Road Zurich, Switzerland Oconomowoc, Wi 53066 Duane Oakley and William Mueller Authorized Nuclear Inservice Inspectors One State Street Hartford Steam Boiler of Connecticut Hartford, Connecticut 06102 Page 2 of 12
Nuclear Management Company LLC Commercial Service Date 10/1/72 Docket 50-301 700 First Street Point Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit: N/A
- 8. Examination Dates: December 28, 2000 to June 30, 2002
- 9. Inspection Interval from December 1, 1992 to June 30, 2002
- 10. Applicable Editions of Section XI: 1986 Edition, no Addenda
- 11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current Interval.
An inservice examination of selected Class 1 and 2 components of We Energies Point Beach Nuclear Plant (PBNP) Unit 2. This plant is operated by the Nuclear Management Company (NMC), LLC. These examinations were performed during the period of December 28, 2000 to June 30, 2002, which includes the Unit 2 Refueling 25 outage (U2R25). This was the second outage of the third period of the third ten-year interval. Additionally, all examinations performed before the end of the third interval, which occurs June 30, 2002, are included.
The components examined were selected in accordance with the Third Ten-Year Inservice Inspection Program. This Program was prepared in accordance with the requirements of the American Society of Mechanical Engineers (ASME)Section XI, 1986 Edition, approved ASME Code Cases, and applicable relief requests.
The following Code Cases were used in the performance of examinations, tests, and repairs and replacements:
Code Case Title N-416-1 Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding,Section XI, Division 1 N-448 Qualification of VT-2 and VT-3 Visual Examination Personnel,Section XI, Division 1 N-460 Alternate Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1 N-481 Alternative Examination Requirements for Cast Austenitic Pump Casings,Section XI, Division 1 N-491-1 Alternative Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants,Section XI, Division 1 N-498-1 Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 1
& 2 Systems,Section XI, Division 1 N-522 Pressure Testing of Containment Penetration Piping,Section XI, Division 1 N-524 Alternative Rules for Examination of Longitudinal Welds Snubber functional testing and visual examinations were conducted in accordance with ASME Section XI and the Snubber Program. We Energies, NMC, and LMT personnel performed the tests. See Attachment 1 for test results.
Page 3 of 12
Nuclear Management Company LLC Commercial Service Date 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit N/A System Pressure testing was conducted by the plant to ASME Section XI and applicable plant procedures. We Energies, NMC, and LMT personnel performed the examinations.
Minor leakage was noted at mechanical connections, which were corrected using maintenance procedures. No through-wall leakage was found.
Manual ultrasonic, visual, magnetic particle, and liquid penetrant non-destructive techniques were used to examine components. NMC personnel, supported by examiners supplied by LMT, and We Energies performed the examinations. PWA personnel performed radiographic examinations. See Attachment 2 for examination results.
Repairs and replacements have been performed on Class 1 and 2 Section XI components since the previous outage. The Class 1 and 2 NIS-2 reports are included with this report.
NIS-2 reports and supporting documentation for all Section XI repairs and replacements are filed at the plant in the permanent record system and are available for review.
All of the required examinations for the third period and third interval are complete. This meets the requirements of Program B of ASME Section XI and applicable relief requests.
- 12. Abstract of Conditions Noted:
Class 2 Systems Reactor Pressure Vessel A visual examination of the accessible interior surfaces of the Reactor Pressure Vessel (RPV) was performed. No recordable indications were noted.
A visual examination of the exterior surface of the RPV head partial penetration welds on the CRD's was performed for Bulletin 2001-01. No evidence of leakage was noted.
Two CRD welds were examined using liquid penetrant techniques. No recordable indications were noted.
RPV closure head nuts, studs, and washers, and threads in flange were examined using ultrasonic and visual examination techniques. No recordable indications were noted.
One snubber was visually examined. No recordable indications were noted.
Pressurizer Liquid penetrant, ultrasonic, and radiographic examination techniques were used to examine the pressurizer nozzles and vessel welds. No indications were noted.
Regenerative Heat Exchanger Ultrasonic examination techniques were used to examine the nozzles and vessel welds.
No indications were noted.
Steam Generator A visual examination was performed on the steam generator supports. This examination revealed an undocumented change to the support location. This was accepted as-is by engineering evaluation.
Page 4 of 12
Nuclear Management Company LLC Commercial Service Date 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit: N/A Reactor Coolant System Liquid penetrant, ultrasonic, and visual examination techniques were used to examine reactor coolant piping welds, supports, and snubbers. No recordable indications were noted.
Visual examinations were performed on bolting. No recordable indications were noted.
On the supports, loose bolting and out of specification spring cans and support gaps were reported. In each case, an evaluation was performed to determine if the support was performing its intended function. All were accepted as-is, but maintenance was performed to tighten hardware, or Drawing Change Notices were initiated to correct the drawings.
Residual Heat Removal System Valve body welds were examined ultrasonically. No indications were noted.
Snubbers were visually examined. Several discrepancies were noted. These were accepted by engineering evaluation. Drawings will be revised to match field conditions.
Safety Injection System Valve bolting was visually examined. No indications were noted.
Piping welds were examined using penetrant techniques. Linear indications were noted near one weld. Additional surface preparation showed these to be shallow, surface conditions that were easily removed. They were acceptable by evaluation.
Supports were visually examined. A gap was noted between the base plate and wall on one support. The gaps were found to be construction related and were evaluated as acceptable as-is.
Baseline examinations were performed on three supports. No recordable indications were noted.
Chemical Volume Control System Liquid penetrant and visual examination techniques were used to examine piping welds, supports, and flange bolting. No recordable indications were noted.
Baseline examinations were performed on four supports. Missing bolts and nuts, a skewed lateral support, misalignment, and lack of thread engagement were noted. These were all acceptable by evaluation. Missing parts were re-installed, and the remainder were left as-is.
Pressure Tests Pressure tests were conducted on Class 1 systems. These tests met the requirements for periodic System Functional and Inservice Testing. ASME Code Case N-498-1 was invoked as an alternative to the System Hydrostatic Testing, which is, performed once each inspection interval. Several areas of leakage were noted at mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.
Page 5 of 12 I
Nuclear Management Company LLC Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit N/A A System Leakage test was performed in accordance with applicable Code requirements and procedures during plant startup. Several minor leaks were detected at mechanical connections. These were dispositioned in accordance with plant procedures. No through wall leakage was noted.
Class 2 Regenerative Heat Exchanger Ultrasonic techniques were used to examine one shell weld. No indications were noted.
Residual Heat Removal Heat Exchanger Visual examinations were performed on the supports. Arc strikes were noted.
A liquid penetrant examination was performed on the nozzles of one heat exchanger.
Rounded indications were noted. Additional surface preparation was performed to determine the nature of the indications. These were found to be small welding discontinuities present since construction. The indications were either removed or reduced to an acceptable size.
Liquid penetrant examinations were performed on valve body welds. No indications were noted.
Main Steam System Baseline examinations were performed on one snubber. No indications were noted.
Ultrasonic, radiographic, and magnetic particle examinations were performed on main steam welds. No indications were noted.
Augmented ultrasonic examinations were performed on main steam welds in accordance with MEB-1. No indications were noted.
Feedwater System Ultrasonic and magnetic particle examinations were performed on main steam welds. No indications were noted.
Augmented ultrasonic examinations were performed on feedwater welds in accordance with MEB-1. No indications were noted.
Residual Heat Removal System Supports were visually examined. Weld spatter was noted near a welded attachment.
The weld spatter is considered a housekeeping issue and is acceptable. It will be removed during future maintenance activities.
Safety Injection System Supports were visually examined. One linear indication was noted.
Ultrasonic and liquid penetrant examinations were performed on main steam welds. No indications were noted.
Page 6 of 12
Nuclear Management Company LLC Commercial Service Date: 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit N/A Pressure Tests Pressure tests were conducted on Class 2 systems. These tests met the requirements for periodic System Function and Inservice Testing. In addition, ASME Code Case N-498-1 was invoked as an alternative to the System Hydrostatic Testing that is performed once each inspection interval. Several areas of leakage were noted at mechanical joints. These were addressed through plant procedures. No through wall leakage was noted.
- 13. Abstract of Corrective Measures Recommended and Taken.
Several supports were noted as not in accordance with the design drawings. In each case, an evaluation was performed to determine if the support was performing its intended function. Every support was found to be acceptable. However, either the indications were corrected or the drawings were revised to reflect the as-built condition.
On the RHR Heat Exchanger supports, weld spatter and arc strikes were noted. These were not Code rejectable, but were removed on one heat exchanger. The other heat exchanger was left as-is due to high radiation. The nozzle to shell welds on one heat exchanger showed small round indications on the welds. These welds are reinforcement plates around the entry and discharge, and are not pressure retaining. Additional flapping was performed to determine the nature of the indications. It was determined these were present since the heat exchanger was built. The original Code of construction did not require a final visual or penetrant examination, so the indications were not removed. The indications were shallow and easily removed or reduced to an acceptable size. The welds are acceptable.
One steam generator support was found to be misaligned at the floor connection. A review of the calculations showed this to be an acceptable condition. The support was left in the as-found condition.
On one pressurizer safe-end weld, an RT examination noted tungsten inclusions, elongated, and rounded inclusions in the weld. These indications were all evaluated as acceptable.
On one main steam weld, an RT examination noted tungsten inclusions in the weld. This indication was evaluated as acceptable.
All indications noted were evaluated. In each case, the evaluation showed the indication as being acceptable. Many of the indications were removed in accordance with maintenance or construction procedures. In those cases where the indications were not removed, drawings revisions were initiated or they were left in place after the evaluation showed they were acceptable for continued service.
Page 7 of 12
Nuclear Management Company LLC Commercial Service Date 10/1/72 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit: N/A We certify that the statements made in this report are correct and the examinations and 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 2 ,d:::',--
Date: /F/ oo-2k Signed: Nuclear Management Company by L Owner Nuclear Management Company 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 Hartford Steam Boiler of Hartford Connecticut, have inspected the components described in this Owner's Report during the period December 28, 2000 to June 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 the ASME Code,Section XI.
By Signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in the Owner" 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.
/r. at-. Commissions ___"___ _-__ xi, Inspector's Signature National Board, State, Province, and Endorsements Date d/42, Zev 2..-
Page 8 of 12
Commercial Service Date* 10/I/72 Nuclear Management Company LLC Docket 50-301 700 First Street Point Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit: N/A Attachment 1 Snubber Functional Testing Page 9 of 12
Nuclear Management Company LLC Commercial Service Date. 10/1172 Docket 50-301 700 First Street Point Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit: N/A Equipment System Description Manufacturer Code Results Date Number Class HS-32 MS HX-1A msl Ankor-Holth 2 Pass 4/25/2002 HS-22 RCS PZR Spray Grinnell 1 Pass 4/19/2002 HS-23 RHR RHR to RPV Grinnell 1 Pass 4/25/2002 HS-30 RCS PZR Safety Grinnell 1 Pass 4/22/2002 No reportable indications were noted during functional testing. Visual VT-3 examinations were performed before the snubbers were removed for testing. Indications were noted and evaluated as acceptable. Visual VT-3 examinations were performed on each snubber after they were reinstalled to re-establish the preservice examination.
The VT-3 examination reports can be found in the U2R25 Inservice Inspection Final Report. The functional testing reports are filed with the Work Order.
Page 10 of 12
Commercial Service Date: 10/1m72 Nuclear Management Company LLC Docket 50-301 700 First Street Point Beach Unit 2 Hudson, Wisconsin 54016 National Board Number for Unit- N/A Attachment 2 Class 1 and 2 Examination Results Database guide page 12 and database pages 1 through 48 Page 11 of 12
Nuclear Management Company LLC Commercial Service Date 10/1172 700 First Street Docket 50-301 Hudson, Wisconsin 54016 Point Beach Unit 2 National Board Number for Unit- N/A Examination Results Guide POINT BEACH NUCLEAR PLANT UNIT 2 PAGE: 00 DATE: 06/07/02 (A) INSERVICE INSPECTION RESULTS
SUMMARY
(C)
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CPAB COMPONENTS (B)
REACTOR PRESSURE VESSEL CLOSURE HEAD (D)
N 0 ASME STATUS G T SEC. XI RE H
SUMMARY
EXAMINATION AREA CATGY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO l METHOD PROC/DATA SHEET C M R NOTES R-1 (REF. DWG. NO. ISI-PRI-2105) (E)
(K) B-A C MT 163-9931092-001 X - - - Cal. Block: 39-PTB 000060 RPV-HFLANGE (G)
(F) HEAD TO FLANGE (H) (L) B1.21 (M) UT 60 350-9931092-002 X - -
(I) CSCL (N) (P) (R) Work Order 9931092 CSCL (J) 5.75 DATE AND REMARKS ON EXAM (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 (I) Material upstream and downstream as applicable (J) Thickness of component if available or applicable (K) ASME Code category (L) ASME Code item number (M) Shows status of examination C - Code completed L - Limited code complete P - Partial examination A - Augmented examination B - Baseline (Preservice exam)
R - Removed from service E - Expanded (additional) sample examination (Other codes may be used as necessary)
(N) NDE methods (P) Data sheet number (R) Types of indications found Page 12 of 12
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 1 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS us N 0 0 G T R E H
SUMMARY
NUMBER EXAMINATION AREA IDENTIFICATION Reactor Pressure Vessel / Dwg. No. Various ITEM NO CATEGORY KTA' EXAM METHOD PROC/DATA SHEET E
C 0
M E
R ** NOTES **
003800 RPV Instrument B-E C VT-2 SEM 7.11.6 x - -
Penetrations B4.13 Work Order 9948325 36 Instrument Penetrations SS 5/11/2002 - VT-2 complete. No recordable indications. Examined instrument penetrations 1 through 36.
003900 RPV Interior Surface B-N-1 C VT-3 756-0001 Vessel Interior B13.10 Work Order 9946083 Surfaces CSCL thickness: Varies 4/29/2002 - VT-3 complete on all accessible surfaces. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 2 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
-TATUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAME E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Reactor Pressure Vessel Closure Head Bolting/CRD / Dwg. No. ISI-PRI-2103 004300 CRD Housings B-O C PT 451-0001 X - -
B14.10 PT 451-0002 49 CRD Housings Work Order 9940080 SS to SS 4/23/2002 - PT complete. No recordable indications. Examined Nos. 35 and 36.
004400 CRD Penetrations B-E C VT-2 SEM 7.11.6 X X
49 CRD Penetrations B4.12 VT-2 757-0001 Work Order 9948325 SS 5/11/2002 - VT-2 complete. No recordable indications. Examined a minimum of 25% of the CRD nozzles.
4/23/2002 - A visual examination was performed on the CRD penetrations to look for leakage and head degredation in response to IE Bulletin 2001-01 (WO 9945304).
004500 RPV Closure Head Nuts B-G-1 C VT-I 750-0001 X - -
1 thru 48 B6.10 Work Order 9946079 CS thickness: 7.875 4/22/2002 - VT-I complete. No recordable indications. Examined nuts 17 through 48.
004600 RPV Closure Head Studs B-G-1 C UT 0 169-0001 X - - Cal Block: 23A-REG RPV Closure Head Studs B6.30 Work Order 9945542 1 thru 48 CS thickness: 56.625 4/20/2002 - UT complete. No recordable indications. Examined studs 33 through 48.
004700 RPV Closure Head B-G-1 C VT-I 750-0002 X - -
Washers B6.50 Work Order 9946080 RPV Closure Head Washers I thru 48 CS thickness: 3 4/22/2002 - VT-i complete. No recordable indications. Examined washers 33 through 48.
004800 RPV THREADS IN FLANGE B-G-1 C UT 0 165-0001 Cal Block: 21-PTB Flange Threads 1 B6.40 Work Order 9946082 through 48 CS 4/19/2002 - UT complete. No recordable indications. Examined from stud hole 33 through 48.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 3 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS KTATUS N 0 G C
T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO ME:THOD PROC/DATA SHEET C M R **NOTES**
Reactor Pressure Vessel / Dwg. No. ISI-PRI-2103 004900 RPV-VENT B-E C VT-2 SEM 7.11.6 X - -
Closure Head Vent B4.11 Work Order 9948325 Penetration SS to CS thickness: 0.154 5/11/2002 - VT-2 complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 4 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
--STA TUS N 0 G 0 T
R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES Pressurizer Upper Head / Dwg. No. ISI-PRI-210' 4 005700 PZR-SPRAYNOZ-IRS B-D L UT 58 171-0001 X - - Cal Block: 39-PTB Inside Radius Section B3.120 Work Order 9946084 CSCL thickness: 0.53 4/19/2002 - UT complete. No recordable indications. Limited examination due to insulation support ring.
005800 PZR-SPRAYNOZ-SE B-F C PT 451-0003 - - X Cal Block: 36-PTB B5.40 RT RT-2-WE, REV 2 - X Safe-End to Nozzle Work Order 9946084 SS to CSCL thickness: 0.53 4/19/2002 - PT complete. One acceptable round indication. 5/2/2002 - RT complete. Porosity, tungsten inclusions, and elongated/slag inclusions noted. Accepted as-is. RT performed in lieu of UT to increase weld coverage.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 5 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS Tus N 0 0 G T R E H
SUMMARY
EXAMINATION AREA EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
CATEGORYKTA¶ Pressurizer T-l / Dwg. No. ISI-PRI-2105 005900 PZR Heater PenetrationsB-E C VT-2 SEM 7.11.6 X - -
78 Heater Penetrations B4.20 Work Order 9948325 SS 5/11/2002 - VT-2 complete. No recordable indications..
S-------------------------------------------------------------------------------------------------------------------------------------------------------------------------
006000 PZR Instrument B-E C VT-2 SEM 7.11.6 X -
Penetrations B4.20 Work Order 9948325 Intrument Penetrations SS 5/11/2002 - VT-2 complete. No recordable indications. Examined all nine penetrations.
006100 PZR-Cweld-I B-B C UT 0 163-0001 X - Cal Block: 38-PTB UT 45 163-0001 X Upper Head to Upper B2.11 Work Order 9946081 UT 60 163-0001 X -
Shell CSCL to CSCL thickness: 5 4/20/2002 - UT complete. No recordable indications. Examined entire weld.
S------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
B-B C UT 0 163-0002 X - - Cal Block: 38-PTB 006300 PZR-Cweld-3 X
Lower Shell to Lower B2.11 UT 45 163-0002 _ Work Order 9946081 UT 60 163-0002 Head CSCL to CSCL thickness: 5 4/20/2002 - UT complete. No recordable indications. Examined entire weld.
B-B C UT 0 163-0003 X Cal Block: 38-PTB 006400 PZR-Vweld-I 163-0003 X Vertical Weld at 255 B2.12 UT 45 Work Order 9946081 UT 60 163-0003 X Deg CSCL to CSCL thickness: 5 4/20/2002 - UT complete. No recordable indications.
S--------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
B-B C UT 0 163-0004 X Cal Block: 38-PTB 006500 PZR-Vweld-2 UT 45 163-0004 X Vertical Weld at 285 B2.12 X - Work Order 9946081 UT 60 163-0004 Deg CSCL to CSCL thickness: 5 4/26/2002 - UT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 6 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS K T A
TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer T-l / Dwg. No. ISI-PRI-2105 006600 PZR-SKIRT F-A C VT-3 754-0007 F1.40 IDR 7P-021 Vessel Support Work Order 9946081 4/23/2002 - VT-3 complete. General corrosion noted on skirt. Accepted as-is per Code Case N-491-1, -3400, (b) (5). Examined the entire support skirt. .. . .. . .. .. . .. . .. .. . ...----------
C UT 25 171-0002 X - - Cal Block: 39-PTB 006800 PZR-SURGENOZ-IRS B-D Inside Radius Section B3.120 Work Order 9946085 CSCL thickness: 1.114 4/26/2002 - UT complete. No recordable indications. ..-------------------------
006900 PZR-SURGENOZ-SE B-F L PT 451-0004 X - Cal Block: 35-PTB UT 0L 109-0005 X -
Safe-End to Nozzle B5.40 Work Order 9946085 UT 45 161-0001 X -
SS to CSCL UT 60 161-0001 X-thickness: 1.114 4/29/2002 - PT complete. No recordable indications. 4/26/2002 - UT complete. No recordable indications.
Limited examination due to nozzle configuration.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 7 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
--TA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Regenerative Heat Exchanger HX-2 / Dwg. No. ISI-PRI-2107 009000 RHE-01 B-B L BM SPRD 106-0050 Cal Block: 61-PTB UT 45 166-0002 X Head to Shell B2.51 Work Order 9946086 UT 60 166-0002 X -
SS to SS 4/27/2002 - Beam spread and UT complete. No recordable indications. Limited examination due to support and lugs.
009700 RHE-Nl-IRS B-D L UT30/70/70 176-0001 X - - Cal Block: 61-PTB RHE Nozzle Inside B3.160 Work Order 9946086 Radius Section SS 4/27/2002 - UT complete. No recordable indications. Limited examination due to nozzle configuration.
S------------------------------.. ... .. ... .. ..------------
009900 RHE-N4-IRS B-D L UT30/70/70 176-0002 X - - Cal Block: 61-PTB RHE Nozzle Inside B3.160 Work Order 9946086 Radius Section SS 4/27/2002 - UT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 8 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N
0 G 0 STA T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO L METHOD PROC/DATA SHEET C M R ** NOTES **
Reactor Coolant Pumps / Dwg. No. ISI-PRI-2109 B-P C VT-2 SEM 7.11.6 X -
014300 RCP-A-CASE-EXT Pump Casing Exterior B15.60 Work Order 9948325 CSS 5/11/2002 - VT-2 complete. No recordable indications.
015300 RCP-B-CASE-EXT B-P C VT-2 SEM 7.11.6 X - -
Pump Casing Exterior B15.60 Work Order 9948325 CSS 5/11/2002 - VT-2 complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 9 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS T N 0 G 0 T
K A R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
NUMBER Steam Generator / Dwg. No. ISI-PRI-2112 018000 SG-A-Main Support-i F-A C VT-3 754-0004 -
F1.40 IDR 7P-015 thru 4 Work order 9946088 Component Support 4/16/2002 - VT-3 complete. No recordable indications on supports 1, 2 and 4. On support 3, the baseplate anchor bolts are not lined up per the drawing. Accepted as is based on engineering calculations.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 10 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS TUS N 0 G 0T R E H
SUMMARY
EXAMINATION AREA EXAM E 0 E PROC/DATA SHEET C M R NOTES **
TA METHOD NUMBER IDENTIFICATION ITEM NO **
CATEGORY Residual Heat Removal Suction / Dwg. No. ISI-PRI-2123 034900 Valve 2RH-701-WLD B-M-1 L UT THE 109-0041 Cal Block: NDECB-014 UT 45 173-0006 10" Velan Gate Valve B12.40 X Work Order 9946087 UT 60 RL 173-0006 Body Welds CSS 4/16/2002 - UT complete. No recordable indications. Limited examination due to valve configuration.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: ii DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA EXAM E 0 E NUMBER IDENTIFICATION CATEGORYKTA ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Safety Injection Loop B Injection / Dwg. No. ISI-PRI-2124 037800 Valve 2SI-867B Bolting B-G-2 B VT-I 750-0008 X - -
RRM 2002-0022 Valve Bolting B7.70 Work Order 0200912 SS 4/9/2002 - Baseline VT-I complete on 18 studs and 19 nuts. Light rust noted. Acceptable as-is.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 12 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS TUS N 0 O G T R E H
SUMMARY
EXAMINATION AREA EXAM E 0 E NUMBER IDENTIFICATION CATEGORYKTA ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Residual Heat Removal to RPV /Dwg. No. ISI-PRI-2131 052400 HS-23 F-A C VT-3 754-0046 - X F1.10S IDR 7P-020 Snubber Work Order 9944422 VT-3 754-0066 X - -
4/15/2002 - VT-3 complete. Undersize weld, clearences on gaps are not per the drawing, shim welds are not located per the drawing. Accepted as-is. Drawing will be revised to match field condition. --------------------------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 13 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS ifTATUS N 0 G T 0
R E H
SUMMARY
EXAMINATION AREA CATEGORY S XAM E 0 E NUMBER IDENTIFICATION ITEM NO L METrHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer Safety / Dwg. No. ISI-PRI-2133 RC-04-PR-2002-04 B-J C PT 451-0005 X Cal Block: 6-PTB 058700 UT 0L 109-0007 X Pipe to Elbow B9.11 Work Order 9946092 UT 45 173-0009 X SS to SS thickness: 0.438 4/19/2002 - PT and UT complete. No recordable indications.
059300 RC-04-PR-2002-09-FB B-G-2 A VT-l 750-0011 X - -
Flange Bolting B7.50 Work Order 9941565 SS 4/21/2002 - VT-l complete on eight studs. No recordable indications. Examination performed while disassembled. ............------------------------------------------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 14 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS ifTA' us N 0
R G
E 0T H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer Spray / Dwg. No. ISI-PRI-2134 060100 RC-03-PS-2001-14 B-J C PT 451-0006 Pipe to Elbow B9.21 Work Order 9946089 SS to SS thickness: 0.438 4/25/2002 - PT complete. No recordable indications. .. . . .. . . .. ..---------------
060400 RC-03-PS-2001-17 B-J C PT 451-0007 X - -
Elbow to Pipe B9.21 Work Order 9946089 SS to SS thickness: 0.438 4/25/2002 - PT complete. No recordable indications.
S 063000 A-04 F-A C VT-3 754-0009 X - -
Anchor F1.10B Work Order 9946090 4/25/2002 - VT-3 complete. No recordable indications. .. . ...------------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 15 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS KTATtJS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DAI TA SHEET C M R ** NOTES **
Spray Line from Loop A to Pressurizer / Dwg. No. ISI-PRI-2135 067900 HS-22 F-A B VT-3 754-0010 X VT-3 754-0067 X -
Snubber Fl.10S Work Order 9932889 4/14/2002 - VT-3 complete on as-found condition. No recordable indications. 4/26/2002 - VT-3 complete on as-left condition. No recordable indications.
069000 R-75 F-A C VT-3 754-0011 x - -
Rigid Support Fl.10B Work Order 9946091 4/17/2002 - VT-3 complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 16 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS Tus N 0
-TAK 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer Relief to PORV's / Dwg. No. ISI-PRI-2137 075100 RC-03-PSF-2002-02 B-J C PT 451-0008 X - -
Reducer to Tee B9.21 Work Order 9946092 SS to SS thickness: 0.438 4/19/2002 - PT complete. No recordable indications.
076400 RC-03-PSF-2002-09 B-J C PT 451-0009 X - -
Pipe to Conc Swage B9.21 Work Order 9946092 Reducer SS to SS thickness: 0.438 4/25/2002 - PT complete. No recordable indications.
078400 RC-03-PSF-2003-04 B-J C PT 451-0010 X - -
Pipe to Elbow B9.21 Work Order 9946092 SS to SS thickness: 0.438 4/25/2002 - PT complete. No recordable indications.
079600 RC-03-PSF-2003-08A B-J C PT 451-0011 X - -
Conc Swage Reducer to B9.40 Work Order 9946092 Valve RC-430 SS to SS thickness: .344 4/25/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 17 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS I CLPABESR COMPONENTS N 0
-STATUS O G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Loop B RTD Bypass / Dwg. No. ISI-PRI-2139 089500 15-PSSB F-A C VT-3 754-0012 X - -
Rigid Support Fl.10B Work Order 9946093 4/15/2002 - VT-3 complete. No recordable indications.
091200 10-PHD F-A C VT-3 754-0013 -
Spring Hanger FI.10C IDR 7P-013 Work Order 9946093 4/15/2002 - VT-3 complete. Loose bolt connecting the south spring can to the horizontal component of the hanger. Accepted as-is but will be tightened. Spring can setting not as per drawing, but within tolerances. Accepted as-is. .. . .. .. . .. ...----------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 18 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
-STA! us N 0 G 0T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Charging Line to Loop A / Dwg. No. ISI-PRI-21440 092300 CH-03 F-A C VT-3 754-0014 X - -
Spring Hanger Fl.10C Work Order 9946094 4/27/2002 - VT-3 complete. No recordable indications.
092500 CVC-03-CH-2001-03 B-J C PT 451-0012 X - -
Pipe to Elbow B9.21 Work Order 9946094 SS to SS thickness: 0.438 4/27/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 19 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
-- TA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Auxiliary Charging / Dwg. No. ISI-PRI-2141 098100 06-PRB F-A C VT-3 754-0015 X - -
Rigid Support F1.10B Work Order 9946095 4/22/2002 - VT-3 complete. No recordable indications.
098600 10-PHB F-A C VT-3 754-0016 X - -
Rigid Support F1.10B Work Order 9946095 4/22/2002 - VT-3 complete. No recordable indications.
098900 CVC-02-ACH-2001-12 B-J C PT 451-0013 X - -
Elbow to Pipe B9.40 Work Order 9946095 SS to SS thickness: 0.344 4/21/2002 - PT complete. No recordable indications.
099400 CVC-02-ACH-2001-15 B-J C PT 451-0014 X - -
Pipe to Elbow B9.40 Work Order 9946095 SS to SS thickness: 0.344 4/21/2002 - PT complete. No recordable indications.
099700 CVC-02-ACH-2001-17 B-J C PT 451-0015 X - -
Pipe to Valve CV-383 B9.40 Work Order 9946095 SS to CSS thickness: 0.344 4/21/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 20 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0 0 G T
-STATUS R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer Spray / Dwg. No. ISI-PRI-2142 102500 CVC-02-AS-2001-29 B-J C PT 451-0031 x - -
Pipe to Reducer B9.40 Work Order 9946108 SS to SS thickness: 0.344 4/25/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 21 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
-STA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Reactor Coolant Pump A Seal Injection / Dwg. No. ISI-PRI-2146 B-J C PT 451-0016 X - -
116900 CVC-02-PSI-2001-20 Coupling to Pipe B9.40 Work Order 9946096 SS to SS thickness: 0.344 4/15/2002 - PT complete. No recordable indications. . .. .. . .. . .. .. . ...-----------
117900 24-PRB F-A C VT-3 754-0017 X - -
Rigid Support F1.10B Work order 9946096 4/15/2002 - VT-3 complete. No recordable indications. ... ... ... ..------------------------
B-J C PT 451-0017 X - -
118200 CVC-02-PSI-2001-25 Pipe to Flange B9.40 Work Order 9946096 SS to SS thickness: 0.344 4/15/2002 - PT complete. No recordable indications.
118300 CVC-02-PSI-2001-25-FB B-G-2 C VT-i 750-0005 X - -
Flange Bolting B7.50 Work Order 9946096 SS 4/15/2002 - VT-i complete. No recordable indications. . . .. . .. . . .. . . .. ..------------
118700 CVC-02-PSI-2001-28 B-J C PT 451-0018 X - -
Valve CV-304A to Pipe B9.40 Work Order 9946096 CSS to SS thickness: 0.344 4/17/2002 - PT complete. No recordable indications. . .. . . .. . . .. ..------------
B-J C PT 451-0019 X - -
119500 CVC-02-PSI-2001-34 Pipe to Flange B9.40 Work Order 9946096 SS to SS thickness: 0.281 4/15/2002 - PT complete. No recordable indications. .. . .. .. . .. . .. .. . ...------------
119600 CVC-02-PSI-2001-34-FB B-G-2 C VT-i 750-0006 X - -
Flange Bolting B7.50 Work Order 9946096 SS 4/15/2002 - VT-i complete. No recordable indications. . .. .. . .. . .. .. . ...----------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 22 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0
--STATUS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Reactor Coolant Pump B Seal In: jection / Dwg. No. ISI-PRI-2147 121400 CVC-02-PSI-2002-08B B-J C PT 451-0020 X - -
Coupling to Pipe E9.40 Work Order 9946100 SS to SS thickness: 0.344 4/22/2002 - PT complete. No recordable indications.
121700 CVC-02-PSI-2002-12 B-J C PT 451-0021 X - -
Elbow to Pipe B9.40 Work Order 9946100 SS to SS thickness: 0.344 4/22/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 23 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0 O G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATTA SHEET C M R **NOTES**
Reactor Coolant Pump B Seal Injection / Dwg. No. ISI-PRI-2148 Reactor 123700 CVC-02-PSI-2002-27B B-J C PT 451-0022 X - -
Tee to Pipe B9.40 Work Order 9946102 SS to SS thickness: 0.344 4/16/2002 - PT complete. No recordable indications.
S.......................................................................................................................................................................................
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 24 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS TUS N 0 G 0 T
R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Cold Leg Injection Loop A / Dwg. No. ISI-PRI- 2149 125800 SIS-02-SI-2004-ll B-J C PT 754-0023 Pipe to Elbow B9.40 Work Order 9946103 SS to SS thickness: 0.344 4/20/2002 - PT complete. No recordable indications.
126800 20-PHC F-A C VT-3 754-0018 S- X FI.1OB IDR 7P-017 Rigid Support Work Order 9946103 4/19/2002 - VT-3 complete. 1/4" gap noted between base plate and wall. Accepted as-is by engineering evlaution. .. .
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 25 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
-TA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY T EXAM E 0 E IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
NUMBER Letdown from Loop B Cold Leg / Dwg. No. ISI-P RI-2152 B VT-3 754-0069 - - X 134650 RC-2501R-10-21PS F-A Component Support F1.10A Work Order 0206367 5/9/2002 - Baseline VT-3 complete. Lack of thread engagement on two nuts and one nut not installed.
Accepted as-is by engineering evaluation. . . .. . . .. . .. . . .. . . .. . . .. . . .. ..--------------
F-A B VT-3 754-0068 -- X 134700 29-PRE Spring Hanger F1.10C Work Order 0206367 5/9/2002 - VT-3 complete. Missing bolt, spring can out of alignment, and lateral support skewed.
Acceptable by engineering evaluation. .. . . .. . . .. . . .. . . .. . . .. . . .. . ..-------------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 26 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0
--STATUS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R **NOTES**
Excess Letdown to Chemical and Volume Control / Dwg. No. ISI-PRI-2153 136900 RC-2501R-13-55 F-A B VT-3 754-0019 X -
Rigid Support F1.10B Work Order 9947297 4/24/2002 - Baseline VT-3 complete. No recordable indications.
137200 RC-2501R-13-S6 F-A B VT-3 754-0020 Fl. 10B MR 01-126 Rigid Support Work Order 9947297 4/24/2002 - Baseline VT-3 complete. No recordable indications.
137900 RC-2501R-13-S9 F-A B VT-3 754-0021 - - X Rigid Support FI.10B IDR 7P-019 VT-3 754-0061 - - X Work Order 9947297 IDR 7P-025 MR 01-126 4/22/2002 - VT-3 complete. C-clamp damaged on the end beyond the lock nut. Does not affect the function of the support. Accepted as-is. 4/27/2002 - Baseline VT-3 complete after modification. Clearance problem noted. Accepted as-is by ECR 2002-0060. . .. . . . . . .. . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . .. S..
138300 RC-2501R-13-Sl0 F-A B VT-3 754-0022 X -
FI.10B VT-3 754-0062 Rigid Support IDR 7P-023 Work Order 9947297 MR 01-126 4/22/2002 - Baseline VT-3 complete. No recordable indications. 4/27/2002 - Baseline VT-3 complete after modification. Clearance problems noted. Acceptable as-is per ECR 2002-0059.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 27 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS I CLPABESR COMPONENTS TA'. N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
NUMBER Core Deluge Injection Line / Dwg. No. ISI-PRI-2154 B-J C PT 451-0025 X - -
139700 SIS-02-SI-2001-13 Pipe to Elbow B9.40 Work Order 9946105 SS to SS thickness: 0.344 4/19/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 28 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS t-STA*TUS 0N N O T
R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Cold Leg Injection Loop B / Dwg. No. ISI-PRI- 2155 142200 SIS-02-SI-2002-18 B-J C PT 451-0026 X - -
Elbow to Pipe B9.40 Work Order 9946106 SS to SS thickness: 0.344 4/20/2002 - PT complete. No recordable indications.
DATE: 08/08/02 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 29 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
--STA rus N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Core Deluge Header / Dwg. No. ISI-PRI-2156 144300 SIS-02-SI-2003-l0 B-J C PT 451-0027 - - X Elbow to Pipe B9.40 PT 451-0043 X IDR 7P-016 Work Order 9946107 SS to SS thickness: 0.344 4/17/2002 - PT complete. Linear indications noted on inside of elbow. 4/20/2002 - PT complete. No recordable indications. Re-examination after additional weld preparation.
S......................................................................................................................................................................................
144500 10-PKH F-A C VT-3 754-0023 X - -
Rigid Support F1.10B Work Order 9946107 4/16/2002 - VT-3 complete. No recordable indications.
S...................................................................................................................................................................................................
144700 SIS-02-SI-2003-14 B-J C PT 451-0028 X - -
Elbow to Pipe B9.40 Work Order 9946107 SS to SS thickness: 0.344 4/17/2002 - PT complete. No recordable indications.
S...................................................................................................................................................................................................
144900 SIS-02-SI-2003-16 B-J C PT 451-0029 X - -
Elbow to Pipe B9.40 Work Order 9946107 SS to SS thickness: 0.344 4/19/2002 - PT complete. No recordable indications.
S...................................................................................................................................................................................................
145000 2SI-878C-6 F-A B VT-3 754-0024 X - -
Pipe Support Fl.10B Work Order 9946107 4/16/2002 - VT-3 complete. No recordable indications.
145100 2SI-878C-7 F-A B VT-3 754-0025 X - -
Pipe Support F1.10B Work Order 9946107 4/16/2002 - Baseline VT-3 complete. No recordable indications.
S...................................................................................................................................................................................................
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 30 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0 TATUS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO1 ME THOD PROC/DATA SHEET C M R ** NOTES **
Core Deluge Header / Dwg. No. ISI-PRI-2156 145400 2SI-878C-8 F-A B VT-3 754-0026 X - -
Pipe Support F1.10B Work Order 9946107 4/16/2002 - VT-3 complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 31 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0
--TA!TS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Pressurizer Spray / Dwg. No. ISI-PRI-2157 147000 RC-04-PS-2001-01 B-J L PT 451-0046 X Cal Block: 6-PTB UT OL 109-0046 X Reducer to Tee B9.11 Work Order 9946108 UT 45 173-0010 X SS to SS UT 70 173-0010 X -
thickness: 0.531 4/20/2002 - PT and UT complete. No recordable indications. Limited examination upstream due to reducer to tee configuration.
S------------------------------------------------------------------------------------------------------------------------------------------------------------------------------
B-J PT 451-0030 - - X Cal Block: 6-PTB 147600 RC-04-PS-2001-06 C PT 451-0047 X Elbow to Pipe B9.11 Work Order 9946108 UT 0L 109-0009 X SS to SS UT 45 173-0003 X -
thickness: 0.531 4/19/2002 - PT complete. One linear indication on the elbow. 4/20/2002 - PT re-examination complete after additional surface preparation. No recordable indications. 4/26/2002 - UT complete. No recordable indications. . .. .. . .. . .. .. . ...----------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 32 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS N 0 FS T A TUS 0 a T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C H R ** NOTES **
Letdown from Loop B Cold Leg / Dwg. No. ISI-PRI-2158 152000 RC-08-DR-2001-01 B-J L PT 451-0032 X Cal Block: 17-PTB UT OL 109-0045 X Branch Connection to B9.11 Work Order 9946109 UT 45 173-0011 X Pipe X UT 60 173-0011 SS to SS thickness: 0.812 4/21/2002 - PT complete. No recordable indications. 4/24/2002 - UT complete. No recordable indications.
Limited examination due to branch connection configuration.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 33 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 1 CLPABESR COMPONENTS
--STA TUS N 0 0 0 T
R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Cold Leg Injection Loop B / Dwg. No. ISI-PRI- 2159 155100 21-PR F-A C VT-3 754-0027 x -
Rigid Support F1.10B Work Order 9946110 4/15/2002 - VT-3 complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 34 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS N 0
--STATUS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY M E 0 E NUMBER IDENTIFICATION ITEM NO L METHO D PROC/DATA SHEET C M R ** NOTES **
Regenerative Heat Exchanger / Dwg. No. ISI-PRI-2203 204000 RHE-03 C-A L BM SPRD 106-0050 Cal Block: 61-PTB UT 45 166-0001 X Shell to Tubesheet C1.30 Work Order 9946086 UT 60 166-0001 X -
SS to SS thickness: .812 4/27/2002 - UT complete. No recordable indications. Limited examination due to nozzles.
S...................................................................................................................................................................................................
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 35 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS
-- TATUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Residual Heat Removal Heat Exchangers / Dwg. No. ISI-PRI-2204 205600 RHR-A-LEG-I thru 4 F-A A VT-3 754-0003 - - X F1.40 IDR 7P-006 Component Support Work Order 9946111 3/18/2002 - VT-3 complete. Arc Strike on vessel base material adjacent to weld toe. Accepted as-is by evaluation. . .. . .. .. . ...------------
206200 RHR-B-NI C-B C VT-2 2-PT-RH-1 Nozzle to Shell C2.33 Work Order 9948323 SS to SS thickness: 0.75 4/14/2002 - VT-2 complete. No recordable indications.
206300 RHR-B-N2 C-B C VT-2 2-PT-RH-1 X - -
Shell to Nozzle C2.33 Work Order 9948323 SS to SS thickness: 0.75 4/14/2002 - VT-2 complete. No recordable indications.
206400 RHR-B-N3 C-B C PT 451-0039 - - X C2.31 PT 451-0044 X - -
Inlet Nozzle Work Order 0200424 IDR 7P-011 Reinforcing Plate Welds 3/27/2002 - PT complete. Two round indications noted. 4/1/2002 - PT re-examination complete on area with indications after additional surface preparation. No recordable indications.
206500 RHR-B-N4 C-B C PT 451-0040 S- X C2.31 PT 451-0041 -- X Outlet Nozzle Work Order 0200424 IDR 7P-010 Reinforcing Plate Welds 3/27/2002 - PT complete. Three indications noted. 4/8/2002 - PT complete after additional surface preparation. Largest indication was reduced to an acceptable size. . ..
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 36 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS N 0 TATUS 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO L METHOD PROC/DATA SHEET C M R ** NOTES **
Residual Heat Removal Heat Exchangers / Dwg. No. ISI-PRI-2204 206600 RHR-B-LEG-l thru 4 F-A A VT-3 754-0002 - X F1.40 VT-3 754-0045 - X Component Support Work Order 9946113 IDR 7P-005 3/18/2002 - VT-3 complete. Arc strikes were noted on the vessel and leg base material. Accepted as-is by evaluation. 4/8/2002 - VT-3 re-examination complete after flapping of indications. All arc strikes and weld spatter were removed except for one on leg 4. Accepted as-is.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 37 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS N 0T ifTA rUS 0 R
G E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
RER Heat Exchanger HX-IIB Inlet / Dwg. No. IS I-PRI-2229 242800 2H-25 F-A C VT-3 754-0020 - - X FI.20C IDR 7P-001 Spring Support Work Order 9946114 AR CAP002741 3/20/2002 - VT-3 complete. Weld spatter noted on pipe next to welded attachment. Accepted as-is. This is a house-keeping issue. Work order written to remove. .. . ..
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 38 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS TA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Safety Injection Pump A inlet and Outlet / Dwg. No. ISI-PRI-2238 272700 1-2H2 F-A C VT-3 754-0001 - X F1.20C IDR 7P-002 Spring Hanger Work Order 9946116 AR CAP002655 3/18/2002 - VT-3 complete. Linear indication in crater of weld on welded attachment, spring can is not correct for this support and load is higher than allowed by drawing. Accepted as-is by engineering evaluation. Action Request written to document condition. . .. . .. .. . ...----------
DATE: 08/08/02 POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 39 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Loop A Main Steam Inside Containment / Dwg. No. ISI-PRI-2243 285500 HS-32 F-A B VT-3 754-0063 X Snubber Fl.20S VT-3 754-0063 X -
Work Order 9914721 4/14/2002 - VT-3 complete on as-found condition. No recordable indications. 4/26/2002 - VT-3 complete on as left condition. No recordable indications.
S............................................................................................................................................................................................
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 40 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS N 0
-STATUS OC T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DA* TA SHEET C M R ** NOTES **
Loop B Main Steam Outside Containment / Dwg. No. ISI-PRI-2248 308600 MS-30-MSR-2002-05-BC C-F-2 C MT 350-0001 80 Branch Connection C5.81 Work Order 9946118 A155 Gr KC70 to CS thickness: 1.5 4/24/2002 - MT complete. No recordable indications.
308990 MS-30-MSR-2002-07LU C-F-2 C MT 350-0002 X - Cal Block: 46-PTB C5.52 UT OL 109-0032 X -
Upstream Long Weld Work Order 9946118 UT 45 172-0023 X - -
A155 Gr KC70 thickness: 1.5 4/24/2002 - MT complete. No recordable indications. 4/25/2002 - UT complete. No recordable indications.
309000 MS-30-MSR-2002-07 C-F-2 C MT 350-0003 X Cal Block: 46-PTB UT OL 109-0033 X Pipe to Cap C5.51 Work Order 9946118 UT 45 172-0023 X A155 Gr KC70 to CS UT 60 172-0023 X thickness: 1.5 4/24/2002 - MT complete. No recordable indications. 4/25/2002 - UT complete. No recordable indications.
313000 MS-08-MSR-2008-01 C-F-2 C MT 350-0004 X RT RT-2-WE R2 - x Branch Connection to C5.51 Work Order 9946118 Flange CS to A106 Gr B thickness: TBD 4/24/2002 - MT complete. No recordable indications. 5/3/2002 - RT complete. Tungsten inclusion.
Accepted as-is.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 41 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS TATUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E O E NUMBER IDENTIFICATION ITEM NO MEr THOD PROC/DATA SHEET C M R ** NOTES **
Feedwater Loop A / Dwg. No. ISI-PRI-2250 319100 FW-2H4 F-A C VT-3 754-0032 - - X Rigid Support F1.20B IDR 7P-014 Work Order 9946120 4/16/2002 - VT-3 complete. Clearances are not as specified on drawing. Accepted as-is.
320800 FW-16-FW-2001-26 C-F-2 C MT 350-0005 X - Cal Block: 34-PTB UT OL 109-0036 X -
Elbow to Valve C5.51 Work Order 9946120 UT 45 172-0026 X -
CS-466BB x UT 60 172-0026 CS to CS thickness: 0.843 4/23/2002 - MT complete. No recordable indications. 4/24/2002 - UT complete. No recordable indications.
No examination on the valve side due to its configuration.
321500 FW-16-FW-2001-28G C-F-2 C MT 350-0006 X - Cal Block: 34-PTB C5.51 UT THK 109-0037 Pipe to Nozzle UT 45 172-0027 X - Work Order 9946120 CS to CS UT 60 172-0027 - X -
thickness: 0.843 4/23/2002 - MT complete. No recordable indications. 4/24/2002 - UT complete. Root geometry indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 42 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS N 0
SUMMARY
NUMBER EXAMINATION AREA IDENTIFICATION CATEGORY ITEM NO E-STA* TUS EXAM METHOD PROC/DATA SHEET 0
R E
C a
E T
H 0 E M R ** NOTES **
SA-Feedwater Loop B / Dwg. No. ISI-PRI-2251 325900 FW-16-FW-2002-18G C-F-2 C MT 350-0007 X Cal Block: 34-PTB UT OL 109-0039 X Pipe to Nozzle C5.51 Work Order 9946121 UT 45 172-0029 X CS to CS UT 60 172-0029 X thickness: 0.843 4/23/2002 - MT complete. No recordable indications. 4/24/2002 - UT complete. No recordable indications.
Root geometry noted at less than 50% DAC.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 43 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS TATUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
RHR Pump A Suction from Cont Sump & Loop A Hot Leg / Dwg. No. ISI-PRI-2252 327100 Valve 2SI-850A C-G C PT 451-0048 X - -
10" Valve C6.20 Work Order 9946123 SS thickness: 0.365 6/24/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 44 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS
-TATUS N 0 0 0 T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAME 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Containment Spray Pumps P-14A and P-15A Test Line / Dwg. No. ISI-PRI-2257 348100 SIS-02-SI-2009-01 C-F-I C PT 451-0001 X - -
Valve SI-859B to Pipe C5.30 Work Order 9946125 CSS to SS thickness: 0.344 3/25/2002 - PT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 45 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS TA TUS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E ITEM NO METHOD PROC/DATA S] HEET C M R ** NOTES **
NUMBER IDENTIFICATION Core Deluge and Cold Leg Injection Header / Dwg. No. ISI-PRI-2260 365300 SIS-04-SI-2002-21 C-F-I C PT 451-0037 X Cal Block: 27-PTB UT OL 109-0040 X Elbow to Pipe C5.21 Work Order 9946126 UT 45 173-0004 X SS to SS UT 60 173-0004 X thickness: 0.337 3/28/2002 - PT complete. No recordable indications. 4/1/2002 - UT complete. No recordable indications.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 46 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS 2 CLPABESR COMPONENTS
-STATUS N T 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY EXAM E 0 E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R ** NOTES **
Containment Spray Pumps P-14A and P-14B Suction / Dwg. No. ISI-PRI-2270 400500 3H-01A F-A C VT-3 754-0033 - x FI.20C IDR 7P-009 Spring Support 3/21/2002 - VT-3 complete. Spring can is tack welded to the support stanchion, load indicators are painted, pipe stanchion load flange is warped 3/32N at the center of the plate, rust on the internal surface of the spring support screw. Accepted as-is by evaluation.
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 47 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS P CLPABESR COMPONENTS S N 0 0 G T R E H
SUMMARY
EXAMINATION AREA EXAM E 0 E NUMBER IDENTIFICATION ITEM NO CATEGORYKTA* METHOD PROC/DATA SHEET C M R ** NOTES **
Pressure Test / Dwg. No.
P C VT-2 2-PT-AF-2 - - X 700200 2-PT-AP-2 Auxiliary Feedwater Work Order 9948188 2/13/2002 - VT-2 complete. Leakage noted at valve 2AF-98A of 3 drops per minute. Leakage has corrosive affect on any components and is acceptable. Work Order written to correct. . .. ...---------
P C VT-2 2-PT-CC-I - - X 700400 2-PT-CC-I VT-2 2-PT-CC-I X - -
Component Cooling Work Order 9948318 5/2/2002 - VT-2 complete. Packing leaks noted. 5/9/2002 - VT-2 complete on section between pump 2P-IIA and valve 2CC-724A. . . .. . .. . .. . . .. . .. . .. ..-------------
P C VT-2 2-PT-MS-I - - X 701000 2-PT-MS-i Main Steam Outside Work Order 9934624 Containment 3/15/2001 - VT-2 complete. .. . .. .. . .. .. . .. .. . .. .. . .. .. . .. .. . .. ...---------
P C VT-2 2-PT-RH-I - - X 701500 2-PT-RH-i Residual Heat Removal Work Order 9948323 Inside/Outside Con 4/14/2002 - VT-2 complete. Leakage noted at several mechanical connections.... ... .. ... ... -----------------
P C VT-2 2-PT-SI-4 - - X 702000 2-PT-SI-4 Safety Injection A Work Order 9948320 Train Outside Contain 4/23/2002 - VT-2 complete. 13 areas of dry white bofic acid. These were all cleaned. No through wall leakage. . .. . .. . .. . .. . .. . .. . .. . .. . .. . ...---------
P C VT-2 2-PT-SI-5 - - X 702100 2-PT-SI-5 Safety Injection B Work Order 9948321 Train Outside Contain 4/27/2002 - Two active leaks and several areas where evidence of leakage was noted. No through wall leaks. Active leaks were stopped using maintenance procedures. The areas where evidence of leakage was noted were cleaned. . .. . .. . .. .. . .. . .. . .. . .. . ...--------
POINT BEACH NUCLEAR PLANT - UNIT 2 PAGE: 48 DATE: 08/08/02 INSERVICE INSPECTION RESULTS
SUMMARY
INTERVAL 3, PERIOD 3, OUTAGE 2 (U2R25)
CLASS P CLPABESR COMPONENTS N 0 0 G T R E H
SUMMARY
EXAMINATION AREA CATEGORY TATUSEXAM E O E NUMBER IDENTIFICATION ITEM NO METHOD PROC/DATA SHEET C M R **NOTES**
Pressure Test / Dwg. No.
702200 2-PT-SI-6 P C VT-2 2-PT-SI-6 -- X Safety Injection A/B Work Order 9948322 Inside/Outside Cont 5/11/2002 - VT-2 complete. Two active leaks and several areas where evidence of leakage was noted. No through wall leaks. Active leaks were stopped using maintenance procedures. The areas where evidence of leakage was noted were cleaned or left as-is.
S...................................................................................................................................................................................................
702300 2-PT-SI-7 P C VT-2 2-PT-SI-7 X - -
Safety Injection Spray Work Order 9928582 Additive Tank 1/22/2001 - VT-2 complete. No recordable indications.
S....................................................................................................................................................................................................
702400 2-PT-SI-8 B-P C VT-2 2-PT-SI-8 - - X Safety Injection Event Work Order 9948324 V RCS Check Valve 5/11/2002 - VT-2 complete. Two active leaks and two areas where evidence of leakage was noted. No through wall leaks. Active leaks were stopped using maintenance procedures. The areas where evidence of leakage was noted were cleaned.
703000 2-PT-SW-I P C VT-2 2-PT-SW-I - - X Service Water Inside Work Order 9948319 Containment 5/1/2002 - VT-2 complete. Evidence of leakage noted.
705200 SEM 7.11.6 B-P C VT-2 SEM 7.11.6 - - X RCS System Leakage RMKS Work Order 9948325 Test 5/11/2002 - VT-2 complete. Leakage noted at valve packings. These were corrected with maintenance procedures. This pressure test satisfies the system leakage test at the end of the outage and the 10-year hydrostatic test as modified by Code Case N-498-1 as required by the applicable item numbers.
UNIT 2 REFUELING 25 REPAIR/REPLACEMENT
SUMMARY
REPORT' FOR FORM NIS-2 Written by: OJLKP 71, ** Date: 4g*
Reviewed by: 22-Z41,-', Date: //*2./ cb:2 Approved by:
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd, Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit: N/A Acronyms AR Action Request ASME American Society of Mechanical Engineers CAP Corrective Action Program CR Condition Report MR Modification Request MT Magnetic Particle Examination NDE Nondestructive Examination NRC Nuclear Regulatory Commission PBNP Point Beach Nuclear Plant PT Liquid Penetrant Examination RRM Repair/Replacement/Modification UT Ultrasonic Examination VT Visual Examination WO Maintenance Work Order Page i
Wisconsin Electric Power Company, 231 WVest Michigan, Milwaukee, Wisconsin 53201 Pt Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd , Two Rivers, Wisconsin 54241 Docket 50-266 Commercial Service Date. December 12, 1970 National Board Number for Unit: N/A Table of Contents
1.0 INTRODUCTION
2.0 CODE CASES AND INTERPRETATIONS 3.0 ABSTRACT OF REPAIR/REPLACEMENT Page ii
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd, Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit: N/A UNIT 2 REFUELING 25 REPAIR/REPLACEMENT
SUMMARY
1.0 INTRODUCTION
From December 28, 2000, to June 30, 2002, repairs and replacements were performed on items at PBNP Unit 2. These repairs/replacements were largely completed in the second outage of the third period, of the third 10-year interval at PBNP Unit 2. The time interval for this examination period included the Unit 2 Refueling 25 outage (U2R25) that began on April 13, 2002, and ended May 14, 2002.
2.0 CODE CASES AND INTERPRETATIONS This report and examinations were completed by applying the following:
2.1 ASME Code Interpretation, Section VJII-1-83-17, that allows for computer generated data report forms to be used as long as size, arrangement and content are identical.
2.2 Code Case N-448 (VT-2 and VT-3 personnel qualifications).
3.0 ABSTRACT OF REPAIR(REPLACEMENT 3.1 Repairs/replacements performed on Class 1, 2, MC and CC items are documented on the attached NIS-2 forms. Repairs/replacements on ASME Class 3 items are documented on NIS-2 forms and maintained on file at PBNP.
They are not included in this report in accordance with ASME Section XI, IWA-6210(c).
3.2 There were 52 repairs/replacements performed on Class 3 items. A detailed listing of these can be found in Point Beach memo NPM 2002-0416.
Page 1 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd., Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit- N/A RRM: 1996-0003 WO: 9512275 Component: AC-152N-9-2SBH-8, AC-152N-14-2SBH-2 Class: 2
Description:
Modified supports in accordance with MR 94-09 I*B.
RRM: 2000-0015 WO: 9924572 Component: CV-01298 Class: 1
Description:
Replaced valve due to increase in RCS pressure.
RRM: 2000-0020 WO: 9924867 Component: 2T-103 Class: 2
Description:
Added new anchors and reinforce existing anchor bolt stiffeners.
RRM: 2000-0032 WO: 9920011 Component: MS-05959 Class: 2
Description:
Replacement of valve plug.
RRM: 2001-0034 WO: 9932821 Component: CV-266 Class: 2
Description:
Replacement of bolting.
RRM: 2001-0070 WO: 9944064 Component: P-002A Class: 2
Description:
Replaced seat in discharge check valve due to cracking.
RRM: 2001-0073 WO: 9937081 Component: AC-152N-1-H33 Class: 2
Description:
Replaced adjustment assembly on piping support.
Page 2 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd, Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit N/A RRM: 2001-0075 WO: 9940403 Component: Pipe AC 0152N-04 Class: 2
Description:
Replacement of piping for realignment.
RRM: 2001-0076 WO: 9947297 Component: Pipe RC 2501R-13 Class: 1
Description:
Piping supports were installed or modified in order to bring all piping and other in-line components within their applicable design stress code requirements.
RRM: 2001-0090 WO: 9948927 Component: C-1-D-2 Class: MC
Description:
Replaced, cleaned, inspected, and relubed o'rings and sealing surfaces.
RRM: 2001-0091 WO: 9945302 Component: CV-00296 Class: 1
Description:
Installed smaller diameter stem, replaced the plug, trim assembly, gland follower and bonnet.
RRM: 2002-0001 WO: 9936175, 9948259 Component: RC-00570A/B, 2RC-00575A/B, 2RC-00580A./B Class: 1
Description:
Replacement of vent valves, piping, and pipe support.
RRM: 2002-0002 WO: 9936175, 9948259 Component: RC-00570A/B, 2RC-00575A/B, 2RC-00580A./B Class: 1
Description:
Replacement of vent valves, piping, and pipe support.
Page 3 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd , Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit- N/A RRM: 2002-0004 WO: 9941565 Component: RC-00435 Class: 1
Description:
Like-for-like replacement of safety valve.
RRM: 2002-0005 WO: 9932576 Component: IA-03047 Class: 2
Description:
Replacement of valve plug and seat.
RRM: 2002-0006 WO: 9937576 Component: AF-00100 Class: 2
Description:
Like-for-like replacement of check valve.
RRM: 2002-0011 WO: 9938729 Component: HX-225A Class: 2
Description:
Like-for-like replacement of 2P-lA RCP motor upper oil cooler.
RRM: 2002-0014 WO: 0202642 Component: 2P-015B Class: 2
Description:
Replacement of casing studs.
RRM: 2002-0021 WO: 0203103 Component: S-00845E Class: 1
Description:
Replacement of check valve.
RRM: 2002-0022 WO: 0200912 Component: SI-00867B Class: 1
Description:
Replacement of bonnet studs and nuts.
Page 4 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd., Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit. N/A RRM: 2002-0023 WO: 0205497 Component: SI-00839B Class: 1
Description:
Replaced valve trim.
RRM: 2002-0025 WO: 0205496 Component: SI-00845A Class: 1
Description:
Like-for-like replacement of check valve.
RRM: 2002-0026 WO: 0205821 Component: CV-01299 Class: 1
Description:
Repaired body-to-bonnet leak.
RRM: 2002-0027 WO: 0205820 Component: CV-00295 Class: 1
Description:
Repaired body-to-bonnet leak and replacement of studs and nuts.
RRM: 2002-0028 WO: 0205878 Component: CC-00763B Class: 2
Description:
Like-for-like replacement of relief valve.
RRM: 2002-0029 WO: 0200909 Component: MS-02016 Class: 2
Description:
Replacement of valve trim.
RRM: 2002-0030 WO: 0205986 Component: CC-00763A Class: 2
Description:
Like-for-like replacement of relief valve.
Page 5 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd, Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit: N/A RRM: 2002-0033 WO: 0205820 Component: CV-00295 Class: 1
Description:
Repaired body-to-bonnet leak and replacement of studs and nuts.
RRM: 2002-0034 WO: 9936175, 9948259 Component: RC-00570A/B, 2RC-00575A/B, 2RC-00580A./B Class: 1
Description:
Replacement of vent valves, piping, and Pipe support.
RRM: 2002-0035 WO: 9944663 Component: RC-00434 Class: 1
Description:
Like-for-like replacement of valve.
RRM: 2002-0036 WO: 9914721 Component: HS-32 Class: 2
Description:
Replacement of snubber to facilitate installation of bypass line.
RRM: 2002-0038 WO: 0202446 Component: HS-22 Class: 1
Description:
Replacement of shock suppressor.
RRM: 2002-0039 WO: 9938170 Component: R-1 Class: 1
Description:
Replacement of the male flange.
RRM: 2002-0040 WO: 9939921 Component: C-3 Class: MC
Description:
Replacement of fuel transfer tube flange bolting.
Page 6 of 7
Wisconsin Electric Power Company, 231 West Michigan, Milwaukee, Wisconsin 53201 Pt. Beach Nuclear Power Plant Unit 2, 6610 Nuclear Rd, Two Rivers, Wisconsin 54241 Docket 50-301 Commercial Service Date: October 1, 1972 National Board Number for Unit N/A RRM: 2002-0043 WO: 0206367 Component: RC-00427, RC-00427 piping, RC-2501R-10-21PS Class: 1
Description:
Replacement of valve, small sections of pipe, U-bolt and adjacent support.
RRM: 2002-0044 WO: 0206367 Component: RC-00427, RC-00427 piping, RC-2501R-10-21PS Class: 1
Description:
Replacement of valve, small sections of pipe, U-bolt and adjacent support.
Page 7 of 7
FORMVNIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI -
- 1. Owner Wrisconsin Electric Power Company Date Augiust 1, 2001 Sheet: 1 of 1 231 West Michigan, Milwaukee, WI 53201 Unit 2
- 2. Plant Point Beach Nuclear Plant WO 9932821 6610 Nuclear Road; Two Rivers, WI 54241 Repair Organization P.O. No., Job No. Etc.
- 3. Work Performed By: Wisconsin Electric Power Co. Type Code Symbol Stamp N/A Authorization No. N/A 6610 Nuclear Road, Expiration Date N/A Two Rivers, WI 54241
- 4. Identification of System: Chemical and Volume Control West. Spec G-676241
- 5. (a) Applicable Construction Code N/A 19 N/A Edition, No Addenda, N/ACode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda 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)
CV'-00266 Aloyco, Inc. 376-SP N/A CV-266 Unknown Replacement No
- .. .. i "_ _ I - _ "_ _ -, _ _ 7 1
- 7. Description of Work: Replacement of two 1/2 ich cover bolts witn 9io mcn Doits.
- 8. Tests Conducted: Hydrostatic- L] Pneumatic H Nominal Operating Pressure []
Other E] Pressure _ psi Test Temp. OF t None
- 9. Remarks RRM 2001-0034, CR 00-3595 Applicable Manufacturer's Data Reports to be attached.
CERTlICATE OF COM[PLIACE We 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 replacement
-Type Code Symbol Stamp: -N/A -----
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed - - I Coordinator Date
,ISI
- 1 2001. ___ __m
__ ___ - Owner or Owner's Designee,-Tit!e ..... ii -
__-__CERTIFICATE-OF-INSERVICE-INSPECT[ON
- -- I, the-inder-si de-, hlding-a vo- f-is-u-d b-th-Naii B do- f B-iler-and Pr-t-idVel ---
______2- -mInspectors and the State of Province of-Wisconsin-and employed-by-HSBII, Co.-of-Hartford, CT--have inspected the components described in this Owner's-Report during the-period-March 26, 2001 to -August 1, 2001, 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 ex-afiinatio6n-sad c-6rrecfive measures described n t OWn-esRort- Furthermore,neitherh-e ispector-toriais employer shh I_;bleny merj'orany- ersonalminjury-y2damageyr a loss of*any _
kind arising from or connected with this inspection.
Commissions WI-100128 4, .-
Inspector's Signature National Board, State, Province, and Endorsements Date: "-Z '- 0N1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date May.29, 2002 Sheet: 1 of 1 700 First Street, Hudson, WI 54016 Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 0200909 6610 Nuclear Road, Two Rivers, WI 54241 Repair Organization P.O No, Job No. Etc.
We Energies Type Code Symbol Stainp N/A
- 3. Work Performed By:
name 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Rivers, WI 54241 c
- 4. Identification of System: Main Steam 4ddre WE Spec PB-584, Copes Vulcan Dwg D-350250 Rev. 1
- 5. (a) Applicable Construction Code No 19 No 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)
M8-02016 Copes Vulcan 9420-97357-1-A N/A MS-2016 Unknown Replacement No
- 7. Description of Work. .Replacement of valve trim.
- 8. Tests Conducted: Hydrostatic E] Pneum atic El Nominal Operating Pressure E]
Other Z Pressure psi Test Temp. F F__
"Z None Required -I
- 9. Remarks RRM 2002-0029 Applicable Manufacturer's Data Reports to be attachea.
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 ISLCoordinator Date ---
Owner or owner's Designee,-Title CERTIFICATE OF INSERVICEJNSPECTION .
Iv-th6-i-d eio-n diný-a 9*lid c6 iisfiigi-ii*-d by--th-e-ff-ti6l B6-a-d-rf Boiler-and-Pf&re-Vesýel
_Inspectors-and the-State of Province of -Wisconsin' and employed byHSBRCT-have-inspected the-components
-described-in this-Owner's Report during the period April 23, 2002 toMay 29, 2002,and-state-hat-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 signipg 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 tis employer shall be liable in any manner for anypersonal injury-orpropertyxdamagceora loss Df.any kind arising from or connected with this inspection.
. . Commissions WI-100128 - -- . .
zAJ1.
Inspector's Sijrature -National Board, StateProvince, and Endorsements Date: - '9-* - ' -- __,_.....
PBF-7050 SEM 7.11.1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date Junte 13, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9945302 Repair Organization P 0 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 ialdreVo
- 4. Identification of System: Chemical and Volume Control Westinghouse Spec 676270 Rev. 1
- 5. (a) Applicable Construction Code B31.1/ASA B1 6.5 19 67/67 Edition, No/No Addenda, No/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)
CV-00296 Copes Vulcan N/A NIA CV-296 Unknown Replacement No
- 7. Description of Work: Install smaller diameter stem, replace the plug, trim assembly, gland follower and bonnet.
- 8. Tests Conducted: Hydrostatic U Pneumatic El Nominal Operating Pressure [
SOther. - El 'Pressure NOP psi Test Temp. NOT 'F
- ----- -_ System Leakage Test
- 9. Remarks RRM 2001-0091 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. --.-. repar or replacement-Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A
-Signed ..... . ... "----I Coordinator-Date-----7 -/- .
O~wner or Owner'a Designee, Title_ - -_ _ f/
CERTIFICATE OFINSERVICE-INSPECTION 1
-- I, the-undersigned,-holding a valid commission issued by-the NationaLBoard-of-Boiler-and-Pressure-Vessel-Inspectors and-the-State-of Province of Wisconsin and employed-byfHSB CTlhave-inspectedthe-components_ "
described in this Owner's Report during the period November 9. 2001 to June 13, 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.
ysigning-thiscertificate, neither the Inspector nor his-employer makes-any~warrantyexpressed or-implied; .
oncerningihe examinations and corrective measures described inthis Owner's Report. .Furthermore, mieither-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. _ ""
- _ 0Commissions WI-100128--
Inspector's Signatiqe -National Board, State, Province, and Endorsements Date: (, ,2~
PBF-7050 Revision 1 05/17/02 SEM 7.11.1
FORM NIS..2 OWNTR'S RET~ORT' FOR flElA MRS OR REPLAACEMENTS A4 Recquired by the Provisiomi of the ASMIE Code Section XI
- 1. Owner~ Wisconsin Electric Powecr Cornpiny Date - 4/12/2002 231 West Michigan, MilwatkLe, WI 53201 Sheet. I of 3
- 2. P'lant Point Beach Nuclear P1~nt Unit: 2 6610 Nucicor Road, Two Rivcrs, WI 54241 P045004323&9, Job No. N391 ¶A/5 Q,*Aw5?j51 Rttpair Ozi'anii~iiion F.0 No . Job NanHei C.cD-Io~
3 Work- Performed Dy: S~nior O~perationq, Inc._____ Typ~e Code Sy~mbol Starrp N/A 2400 Lozielron Indusitial Dr. Authorization No N'/A __ _ _ _ _
New tBraunfcls, TX 78130 Expiration Date N/A _____
- 4. Idclicification of~ System: Service Water 5.(it) Applicablo Commtrction Code FM31_119 95 Edition, No Addenda, No Code Case (b) Applicible Edition of Section XI Utilized for Repairs or Rcplactements 1986
- 6. Identification of Comnponents Repaired or Replarcd and Replacemri-rt Components Replaird, ASMF, Nitioazl Rcplaced, Code Nailic 0! Na~me of Minufacturer Bloard Other \'car or s ta"Tiped (Annparien NManuat-IU~rr Serial No No. Identificotion B~uilt Rcplaccrnent (Yc-s or No)
_4 -. I-- i - I 2-t[12" Flex fHo'c+/- Stntior Flexonicz 1 11771S09.1 1 NIA I_ N/A 1 200, 1 Iitplace~rmt-t No 2-1/2" 1 idluxo.c' Scmior Flcxomcs i HS7LSo-9-2 -L N/A N/A 20017 Replacnimerit No
'7. Desciiipion of Work- Fabticate flx hoscs for contaianment fan coolierýs'epTjlacenet.
8 Tests Con~due~t'J TIlVdIoItati ED Pneumatic El N14ominal Operating PreSsure E Other 1:1 Pressure 225 ps I [ est TLrnP. N/A ol' 10 rniiiwte hold timle 9). Rerniarkq Supply and RMUMn lines for 211X-15C and 21[X-15D 1-,gr)- ~.J c(-YI YD) -7.5~
C*FUTTFICATr ore ('ompi.rAwCP Wec ceitify that the statemcnts mande in the report are r orrect and this -flcplernntconfonns to the rules of thz ASMP, Cock,, Scetion XI ~ru.
Ty1,c Cod.- Symbol Stamp' N/A Ceilificaite of Authlorirtiot No. N/A Expiration Date N/A Signed ,/ ______ ISI Coordinator Date 1
Wne or O0weer "ii. ThIc CF.RTtTICATE OF INSEAVICE INSPE~CTI ON 1, ihe xi rders i.pned, holding a valid commnission issued by the Nzitionil roiord of Boiler -and Piressure Vessel Inc~lcctors aind thec State of'Province of Wicni n mlydb STCo of Connecticut have inspected thlt components described in thi3 Owner's Report during the period _1/23/200ý to 4/12/2002, and staic thlat to the bebt of'my knowledge anti belief', thet Owner has performed exan-dnatioras and Tkt~n corrective mcasuies described in this 0%ncrla Re'.port in zccordance with the requiremients of ASME Code,Section XI.
gni~nun this ceitirimte, neither the Inspector nor his emnployer mAkes any warranty, expressed or implied, coincernuig die examinations and coriectivi. measuires described in this Ownier's Report Furthermore, neiherth Inspector nor his einploytr shall be liable in any manrfor any pcirsonal injury or property damage or a loss of any kind at isine fioin or connected wvith this inspcction.
- -z'I Cot wziisý,ions Wisconsin 100128 Insupectitis sipatur(' Ht'ionanl Gcard. Staic, Provincc, an-d F.iuo~rcmeruit Date: t.- A&- 2
-. . - -. -----------. r . - :'=-.-.- - ,#t==- - --
Prif.-70SO rf~visioni 012/20/01 SENI M 1.1
FORM NIS-2 CONTINUATION OWiNER;S REPORT FOR REPAIRS OR RtEPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Wisconsin Electric Power Company Date 4/11/2002 231 West Michigan, Milwaukee, WI 53201 Sheet: 2 of 3
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 PO 4500432389, Job No. N39 1/ WLO)5 qq9q5'?5 Repair Organization P.O. No., Job No. Etc.qgq Sg65?9
- 3. Work Performed By: Senior Operations, Inc Type Code Symbol Stamp N/A name 2400 Longhorn Industrial Dr. Authorization No. N/A New Braunfels, Tx 78130 Expiration Date N/A address
- 4. Identification of System: SW
- 5. (a) Applicable Construction Code B31.1 19 95 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986
- 6. Identification of Components Repaired or Re ilaced and Replacement Components Repaired, ASME 4 National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No. Identification Built Replacement (Yes or No) 2-1/2" Flex Hose Senior Flexonics H87180-9-3 ..N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-9-4 N/A N/A 2001 Replacement No 2-1/2" Flex Uose Senior Flexonics H87180-10-1 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-10-2 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-10-3 N/A NIA 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-10-4 N/A N/A 2001 -' Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-11-1 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics. H87180-11-2 N/A NIA 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-11-3 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-1 1-4 N/A N/A 2001 Replacement No 2-1/2" Flex Hose - Senior Flexonics H87180-12-1-- -N/A-- -- N/A-- - -2001 -- Replacement - No -.
2-1/2" Flex Hose Senior Flexonics H87180-12-2 -NIA N/A 2001 Replacement - No.
21/2"-Flex-Hose- -Senior-Flexonics H87180;12-3 -NIA-- NIA -2001t- -Replacement- No 2-1/2_'FlexHdsE-Z _-Senior--Tlexonics _H87180-12-4 --- N/A -__----NA ...- -... 200IZ _-Replacement- ------No ---
"2-1/2"Fle-x--ofsEn--- -STior-FIeC-o-ics -H87180-13-l -1 NIA- NIA 2001- - Repla*cement- - No 2-1/2" Flex Hose- _Senior-Flexonics H87180-13-2 N/A -_.... N/A 2001 -Replacement --- No 2-1/2" Flex Hose Senior Flexonics H87180-13-3 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexbnics H87180-13-4 N/A N/A 2001 Replacement No 2-1/2" Flex Hose- --Senior.Flexonics - -H87180-14-1 N/A--- --- N/IA -2001- Replacement ---- No 2-112" Flex;Hose -oSenior:Flexonics H87180-14-2 N/A NIA -001 aReplacement No 2-1/2" Flex Hose Senior Flexonics H87180-14-3 N/A N/A 2001 Replacement No 2-1/2" Flex Hose-s Senior-Flexonics H87180-14-4 N/A N/A 2001 Replacement No-2-1/2" Flex Hose Senior Flexonics H87180-15-1 NIA N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-15-2 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-15-3 N/A N/A 2001 Replacement No PBF-7050a Revision 0 12/20/01 SEM 7.11.1
FORM NIS-2 CONTINUATION .
OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Wisconsin Electric Power Company Date 4/11/2002 231 West Michigan, Milwaukee, WI 53201 Sheet: 3 of 3
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 PO 4500432389, Job No. N391 INN.c 9qN-65*,2 Repair Organization P.O. No., Job No. Etc. Oq*/.f2,*5" 2
- 3. Work Performed By: Senior Operations, Inc Type Code Symbol Stamp N/A name 2400 Longhorn Industrial Dr. Authorization No. N/A New Braunfels, Tx 78130 Expiration Date N/A address
- 4. Identification of System: SW
- 5. (a) Applicable Construction Code B31.1 19 95 Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements `1986
- 6. Identification of Components Repaired or Replaced and Replacement Components Repaired, ASME
-4 National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped Coniponent Manufacturer Serial No. No. Identification Built Replacement (Yes or No) 2-1/2" Flex Hose Senior Flexonics H87180-15-4 NIA N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-16-1 N/A N/A 2001 Replacement No 2-1/2" Flex 13ose Senior Flexonics H87180-16-2 N/A N/A 2001 Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-16-3 N/A N/A 2001" Replacement No 2-1/2" Flex Hose Senior Flexonics H87180-16-4 N/A N/A 2001 Replacement No
'I . . . . . . .. .. . . .. . . . . . . ._ ___ ___ _ __ __
PBF-7050a Revision 0 12/20/01 SEM 7.11.1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. "Owner Nuclear Management Corporation Date Ma, y29, 2002 700 First Street, Hudioin, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0205821 Repair 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 addrV m n
- 4. Identification of System: Chemical and Volume Control Westinghouse Spec 676258
- 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 Nameof Nameof Manufacturer Board Other Year or Stamped Component Manufacturer Serial No. No. Identification ___Built Replacement (Yes or No)
CV-0 1299 Darling Valve S350-W-DD N/A CV-1299 Unknown Repaired No
______________________________ .1. _____________ 1 ________ .1. ____________ .1. .1. ___________ .1
- 7. Description of Work: Repaired body-to-bonnet leak.
- 8. Tests Conducted: Hydrostatic El Pneumatiic El Nominal Operating Pressure nl Other Z Pressure psi Test Temp. OF None Required
- 9. Remarks RRM 2002-0026 Awitcahie ManuThct,,re,' Data Renarts to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this reoair 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- !'t ,ISI Coordinator--Date--c./t-O ;:2.
Owne~r o O ner's Designee, Title . .. .
ii
"_-_.. __ .. _ CERTIFICATE OF INSERVICE INSPECTION-___ . .
I the undersig nd,-h-l1mi--a-id_ m6riiso i u he- o-fl B--id f Biler- nd Ps eVs
,a 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 April 18, 2002 toMa 29, 2002,and-state-thattolhe-best ofimy 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 rmeasures described in this Owner's-Report.-Furthermore,-neither the-nhis*ectorpir his x-plyershallte liable in any manner forakny personalinj rrpropydamage43rzlossqofany kind arising from or connected with this inspection.
//, --.......... Commissions WI-I00128 ........- -
National Board, State, Provimcee-andErndorsements Date:te Si-g.a-ture Date: i~vfd2-.
PBF-7050 Revision 1 05/17/02 SEM 7.11.1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of theASME Code Section XI
- 1. Owner Nuclear Management Corporation Date June 13, 2002, 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0202446 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: Reactor Coolant "addre-t Bechtel Spec M-78, MSS SP-58 1967 Edition
- 5. (a) Applicable Construction Code B31.1 19 55 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)
HS-22 Grinnel Co. N/A N/A None Unknown Replacement No
- 7. Description of Work: Replacement of shock suppressor.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure E]
Other [ Pressure psi Test Temp. OF None Required.
- 9. Remarks RRM 2002-0038 A.,,,i,'.,hi, l,,, flat, ,,n,+/- in he attached CERTIFICATE OF COMPLIANCE We 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 eplacement Type Code Symbol Stamp:-N/A .....
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed "" ISI -Coordinator-Date- -
Owner-orOwiier's-Designee, Title -
.1
-CERTIFICATE OF.INSERVICE INSPECTION -__
-Ith-dii- n--dh61ding-a-vilid c -nssiofi-iss-iie býy-the-Nf l B6*da-rdfBiliid Pressur lV ...
Inspectors and the State ofProvince of Wisconsin and employed byHSB CT-haveinspected-the-components---
described in this Owner's Report during the period May 1. 2002 to June 13, 2002,and~statethatto the bestof 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 signipg 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-ReP o---Fe*oer re-neither the Inspector or his employer shall be liable in any manner forany personal injuryzor -operty~arrage-orim loss of;any kind arising from or connected with this inspection.
Commissions WI-100128-- -
Inspector's Signature National Board,-StateProvince-and Endorsements Date- ,ryý ,r* Z'0-0"I PBF-7050 SEM 7.11.1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
, As Required by the-Provisions-of the ASME Code Section XI "1. Owner Nuclear Management Corporation Date July 3, 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 9937576 Repair Organization P.O. No, Job No Etc.
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A nilme 6610 Nuclear Road -- Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A "rndrd
- 4. Identification of System: Auxiliary Feedwater 5 (a) Applicable Construction Code B31 1/ASA 16.5 19 67/61 Edition, No/No Addenda, No/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)
Aft-00 100 Enertech 10740 N/A AF- 100 Unknown Replacement No
- 7. Description of Work: Like for like replacement of checkvalve.
- 8. Tests Conducted: Hydrostatic E3 Pneumatic [] Nominal Operating Pressure [
Other [ Pressure NOP psi Test Temp. NOT °F System Leakage Test
- 9. Remarks 1RRM 2002-0006 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLLINCE We 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 replacement Type Code Symbol Stamp:-N/A - -2 Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed .ISI Coordinator-Date "O_
-ner-or w Owneris Designee, Title
-.-..... _CERTIFICATE OF INSERVICE INSPECTION
,-th-eýndersig e - lai-dghalinvlid-cmniiiriin issu-d bediyhe -Nit-i6n1o--arl adn-fBoiler-nd PressuresVel.- -
--- Inspectors and the -Stateof-Province of -Wisconsin and employed by-HSB-CT-have-insected-the-components described in this-Owner's Report during the period" January 10, 2002 to-July 32002,d_state_that~tothehest-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 signiug this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the-examinations-and corrective measures described in this'Own-er's-KReportT7Fmrthermore,-neither the Inspectornor his mployer5hall e-.iable in anymanner for anypersonal ,damage loss ofmny___
kind arising from or connected with this inspection.
./ - 2--
- e"'- - Commissions WI-100128 -
Inspector's Signature National Board, State, Provin&6,-ind Endorsements Date: * - - -
PBF-7050 Revision 1 05/17/02 SEM 7.11.1
7 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provision-s of the ASME Code Section XI
- 1. 'Owner Nuclear Management Corporation Date July 5,200" Sheet: I of I 700 First Street, Hudson, WI 54016
- 2. Plant Point Beach Nuclear Plant Unit: 2 Road, Two Rivers, WI 54241 WO 9941565 6610 Nuclear Repair Organization P.O. No, Job No Etc. -
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A naNme 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Riyers, WI 54241
"*ddre*m
- 4. Identification of System: Reactor Coolant
- 5. (a) Applicable Construction Code ASME Section 1119 65 Edition, Winter 66 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)
R't-00435 Crosby XX05950174 N/A RC-435 Unknown Replacement Yes
- 7. Description of Work: Like for like replacement of safety valve.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure [
Other El " Pressure NOP psi Test Temp. NOT 'F "SystemLeakage Test
- 9. Remarks RRM 2002-0004; valve was tested and repaired by Crane Movats Inc._under-POA500376203...
Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLiNC2E We 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 replacement Type Code Symbol Stamp:-N/A -..
Certificate of Authorization No. Docket 50-301 Expiration Date NIA Signed 4,7 *g -I" SICoordinator--Date--- , -.
Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION . . . .
- I, the undersigned,_holding a yalidcommission issued by the-National Board of Boiler and Pressure Vessel q
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 January 8, 2002 to Julv-5,-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, cdncer6n iigtheei* fif d corr ctiv rmeasures de scrbed in-this Ow-e-r'gR*-6-rt.pF&-irth-ii-he,i6ther e th--
Inspector nor hisemployervshal-be -liable in any manner for-any personal injuryroper tya qage ur m-oss of-a-y kind arising from or connected with this inspection.
1.1.- -- -..... Commissions WI-100128 Inspector's Signature . National Board, State, Province, and Endorsements Date: . , 2002.--
2 PBF-7050 SEM 7.11.1 Revision 1 05/17/02
<KFORM NVR-1 REPORT OF REPAIRK.MODIP1CAT1ONEOR REM] .ACEMENTE 4--
rane Moyat3 Inc.- ~~ -45003 203---
1: Wor p fqrnie by. - __
2S25 Cobb 1iter_- tionzl Blvd., Kerinessw, GA 30152-4352 ____________
Work performed for Wiscotsin Electric Power CO. Point Beaih diie~rstatio'n 661 *eear RDf Two Rivt_-,WI
- 3. Owner Wisconsin Electritc Power Co.____________
6610 Nuclei~r Road Two RiversWI 54241 ____________
4, Niame,'address and identification of nuclear power plant Point ibeach~nuclear station _____________
-6610 NodTucea-r Road Two Rivern,WI 542411
- 5. A-- Repair pre=sue relief device- Shop # 51209SPARE PRESSIJREZER.XXID5950174 b: Name of manufacturer: Cr osby Valve and Gage Co.
51249 B8BP 4 X.2 6 N/A c: Identifying nos. wt~ aaMLIno,4 Ly4.&rbIuilI d: ConstnucTion Code' U =W6~
6 ASME Code Secttion Ml applicable for in-service inspection. 1986
- 7. ASME Code Section )a used for repairs, modifications, or replacement s: 1986 (Cod. CA..ý-A3L
- 8. Corfstruction Code used for repairs, modifications, Or repl.Cements: 1986
- 9. Des~gn Reaponsibili ty Crosby Valve and Guge Gie Co. Co.
Crosby Valve and
- 10. Opening pressure: 248S5 Blow-down (if applicable) N/A %.Set pre sure and blow-down adjustment made at-, Wyle Labs Huntville.AI US~lg_ Stearn 4-
- 11. Description of work: (include name and identif'ing number of replacement parts) Cleaned a, .dinspected parts. machined
- .Nozzle, Vedfid critical dinnensona & sprng~ oRag, reconditioned seats by lapping & poishnmg. reassembled & testev..
1-I2-.*RenmArks-Replaced Crosby parrS: Dif Insert PIN~ N96532 3-0004,-c&conerpiP.O.21 1920 4N-903Th116(1IXDISC ?iP.Q0m-
=PI#0-MAeS ?Aa9778nY-()B~AKPl-,1-11D ý ____AUý17MM3W 9 1- 13 Z.
-I - --- CERTIFI1CATE OF COMPLIANCE -
1, _-- DOUG MILTER .certify that to the best of my knowledge anc belief the statements made in this rep~rt are correct and the repair, modification or replacement of -the-pressure relief devices lescribed above conforns~to .1: ----- -
a6~MlQ~eA aeoa or npe C V ~ ~~iP Natl6nal Board Ckrficate ofAuthdriai~onJJo. 47Z:3..to Use stamp..expires- .J!:,4..--
-h.Y v22 ;20 -O2' y 22 -r20 02 Nationa-BoardLCartnficate-of AuthaFlat 6lN. 32 tustij tapepi- 2~2 - 2. -.
Date 3/~122O-Qz ___
___ ý-Crane
___ ___ ___ ______mcyats-in?
___ _ __ ___ ___ ___ ___ __ ___ ___~ o-IQns _________ ector _
(i,frtiflrta V 2....-o holdar holder) Z&s..tah (authorized-redtesentaUve)-ttfl9e CERTIFICATE OF INSPECTION M. ;j7-.J4J~ holding avalid commissior issued by Th Nlational Board
- . .- - - *. .~-. - *of Boiler and Pressure Vessel Inspectors and cer~tiiate of competency-issued by the jurisdiction of4 end employeqd
-by-L- f- _=6X,r7 & J-cgrT-- have 4nspec dMe~rpalr..Jodi=UcaUotriEplreflfltde-5cibadflinsmeport~l S iý-2Dr betOf-My knowledge and_1ll&fth- ýifo or replacemn hsbEn rmplated in accoianczvith-SeclcrwXI oAIAE~de e an theNqaUril Bardý!nIpectfio Code"VR' 6nd 'NR^ rules.
k signLng thls certiicate, n~ither the-undersigned nor my employer makes any warranty, expres the repair, mod ification or replacement described in'thl-r-ep-o-rt F-ur-thermobre. neither the under, 'gned nor my employershalV orcnnected with this.
be-liable n-any-manner-for anpersnaliiJoury pr~p rty - damnage or loss of anyklir~d arising frm Inped"_ -. -- __- -ý -1 Oat"~-/Z*-'-0eZ Signed 'I-~~JCommissions i/ *7e
-sduAd .
- - - - - - - - - - - - - - - - - - - - - -. 4 S -. A-- I '- -
- F_ r T.. 7CO 1- It.,,-
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Managenient Corporation Date May 29, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0205820 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: Chemical and Volume Control Westinghouse Spec 676241
- 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)
C*V-00295 Velan N/A N/A CV-295 Unknown Repaired No
- 7. Description of Work: Repaired body-to-bonnet leak and replacement of studs and nuts.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other [ Pressure __ psi Test Temp. OF None Required
- 9. Remarks RRM 2002-0027, RRM 2002-0033 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this reeee conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp: --NIA ...
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed-- 1T ,T' . ISI Coordinator-Date--
esignee, Title Owne.ror Owner'-O ' .
______CERTIFICATE OF INSERVICE INSPECTION I, Ihe undersigned__olding avlidommissio-n issueedb*-th- National-Board of B-oiler 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 April 18. 2002 to May 29. 2002,_and state-that-to-the-best-ofmy 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 xaiiin tion--and -corrective measures described in this-Owner's-Re-p-tT--FiF--rthermoreiethser the Inspector norhis cmployer'shall be 'Iiable ina;ny manner-forany persalILj *_yrppery dmge~or a oss *mny_ -
kind arising from or connected with this inspection.
Commissions WI-100128 lnspector('Signature National Board, State, Province, and Endorsements Date:
- 6 -. .
PBF-7050
. .... . . . SEM 7.11.1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management C6rporation Date July 5,2002 WI 54016 Sheet: 1 of 1 700 First Street, Hudson, Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 9944663 6610 Nuclear Road, Two Rivers, WI 54241 Repairorganization 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 Expiration Date N/A Two Riyers, WI 54241
- 4. Identification of System: Reactor Coolant West Spect 676279
- 5. (a) Applicable Construction Code ASME Section III 19 68 Edition, No Addenda, Noo 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)
Rb-00434 Crosby R 1].2A-b -Cto) N/A RC-434 1994 Replacement Yes
- 7. Description of Work: Like for like replacement of valve.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure [
Other [ Pressure NOP psi Test Temp. NOT *F System Leakage Test
- 9. Remarks RRM2002-0035. Valve was refurbished under PO 4500376203_byCrane-Nuclear atiWiley Laboratories.
CERTIFICATE OF COMPLIANCE We 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 rephacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed --- ISI Coordinator-Date
_______Ow=-rw-Owneres resneritdc - t7EZ
-. CERTIFICATE OF INSERVICE INSPECTION T. -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-omponents---
described in this Owner's Report during the period April 30. 2002 to July 5. 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. "
B y-signi-g-thisctificte, neithethe Inispector nor his employer mxaký anUy-E tyxp-ressed -implied,
- -onerning the-exantions-and corrective-measures described inihis Owner's R'epot. -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.
- g. 4"Commissions WI-100128 Inspector's Signature - -National Board, State, Province, and Endorsements Date: r , Mn -
PBF-7050 SEM 7.11.1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS "AsRequired by the Provisions of the-ASMECode Section XI b
- 1. Owner Nuclear Management .orporation Date May 29, 200 2 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0200912 Repair Organization P 0. No Job No Etc.
Work Performed By: We Energies Type Code Symbol Stamp' N/A 3.
name 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
%didre;
- 4. Identification of System: Safety Injection
- 5. (a) Applicable Construction Code USAS 16 5 19 66 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)
SIt00867B Darling Valve N/A N/A SI-867B Unknown Replacement No
- 7. Description of Work: Replacement of bonnet studs and nuts.
- 8. Tests Conducted: Hydrostatic El Pneumatic E] Nominal Operating Pressure E]
Other [ Pressure psi Test Temp. OF Seat Leakage Test
- 9. Remarks RRM 2002-0022 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We 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 replacement Type Code Symbol Stamp: -N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed .ISI CoordinatorJDate___ .--- _
-- OwirorOtneiaes-ignee,-Title ..
-fl i'1 -
______CERTIFICATE OF INSERVICE INSPECTION . ... .
I, theu in -dhldin-g a val-i-d commissi6n is ued by the Niti6fl BZ-a-d 6f B6il*eariid Pre-&e-Ve1 -_-l 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 April 8. 2002 to May 29, 2002,andcstate~that-to-the-hest~ofmy knowledg&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 signipg 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.-Furthermoreneit#erthe.---_-
Inspector nor his employer shall*e Aiable ininy manner for any personal injuryor property amage irz 1osssoffany __,
kind arising from or connected with this inspection.
S , .. . Commissions WI-100128. -
Inspector's Sig'nature - National Board, State, Province, and Endorsements Date: "t -*a2,* -
PBF-7050 SEM7.11.1 Revision 1 05117/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the-ASME Code Section XI
- 1. Owner Nuclear Management Coi'poration "Date Ma, r24,2002 700 First Street, Hudson, WI 54016 Sheet: 1 of I
- 2. Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 WO 9938729 Repair Organization P.O. No, ,Job No Etc
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A na*m*e 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A sddireqq
- 4. Identification of System: Component Cooling Water West. E-Spec 676433, Rev 1 Dated 10/09/67; West G-Spec 676262
- 5. (a) Applicable Construction Code B31 1 19 67 Edition, No Addenda, NoCode 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)
HX-225A Westinghouse N/A N/A None Unknown Replacement No
- 8. Tests Conducted: Hydrostatic El Pneumatic [] Nominal Operating Pressure El
. Other ED Pressure NOP psi Test Temp. NOT *F System Leakage Test
- 9. Remarks RRM 2002-0011,CAP028413 Apphcable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We 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 replacement Type Code Symbol Stamp:-N/A - --- -
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed - / -ISI Coordinator-Date-- //D" 02 Owner or Owei&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 Province of-Wisconsin and employed by HSB CT-have inspected-the-components described in this Owner's Report during the period January 5, 2002 to May 24-2002.-and state-that-to-the-best-of----
my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owper'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, concuming-th76amifhtions and corre tive measures- described in-this Ownr's-Rp-rt th--rCor-e-n-iifh'er--e inspector nor his employer sha14oe liable'*imany mana er -for any-personal injury orprgprtydamIage'or-a4oss of'any kind arising from or connected with this inspection. ---.
-* ;y/,. -Commissions WI-100128 Inspector's Signfture National Board, State, Province, and Endorsements Date: ,_ - Z-PBF-7050 Revision 1 05/17/02 _- SEM7.11.1 .- --
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Cnde Section XI
- 1. Owiner Nuclear Management Corporation Date Ma] '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 9932576 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: Instrument Air Bechtel Spec M-78
- 5. (a) Applicable Construction Code No 19 No 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 Senal No. No. Identification - Built -Replacement (Yes or No)
I1403047 Fisher Governor 4593772 N/A IA-3047 Unknown Replacement No
- 7. Description of Work: Replacement of valve plug and seat.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other Z Pressure psi Test Temp. OF Appendix J Test performed under WO 9939951
- 9. Remarks RRM 2002-0005
. ,D-. An,,1,,,hh Mn,,f flata Renorta In be atlached CERTIFICATE OF COMPLIANCE "
We gertify that the statements made in the report are correct and this replacement 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 S--ISI Coordinator-Date---A/,A_,0 -- -
Signed -Owner o Il -
r Owner or Owriei's Desice -FltTc
____ _CERTIFICATE OF INSERVICE INSPECTION
-I,th-e-unde-rsi n--d_ hIdng a-ali-d co ils-iioissued by-dtie-in~1 Bo-adofBoil dPr-E--ie-Vesa e -- - _l 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 January 9. 2002 to May 31, 2002, and-statetihatlo-the-bestof_
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 Report7-Furthermoreneither-the-----_
4nspectornor his employer shalIbe liablej'iRanymanner for any-personaljuryorprP 'f y damage ,oraoss any_
kind arising from or connected with this inspection.
,/, sr .Inspector's Signature
...... Commissions W I-100128 --
National Board, State, Provinceand Endorsmenff s -..
D ate:
- C, 7_ - .... ..
PBF-7050 o Revision 1 05/17/02 - -_ __ SEM7.11.1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date Jun 42002 Sheet: 1 of I 700 First Street, Hudson, WI 54016 Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 9914721 6610 Nuclear Road, Two Rivers, WI 54241 Repair Organizaton P.o NoSJobNo Etc.
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A n6lar 66 10 Nuclear Road Authorization No. N/A Expiration Date N/A Two Riyels, WI 54241
- 4. Identification of System: Main Steam Anker-Holth Spec 6118-C-27
- 5. (a) Applicable Construction Code None 19 No 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 1 Manufacturer Serial No. No. Identification Built - Replacement- (Yes or No)
Component N/A N/A Unknown Replacement No I11ý-32 Anker-Holth 37149A
- 7. Description of Work: Replacement of snubber to facilitate installation of bypass line.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other Z Pressure - psi Test Temp. OF None
- 9. Remarks RRM 2002-0036 -
CERTIFICATE OF COMPLIAXICE .
to the rules of the We certify that the statements made in the report are correct and this replacement conforms 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-.-,---1 _ ISI Coordinator-Date-- 7 j- 9i/-/)_&- ...-
Owner or Owner's Designee, Title . . . . .. -
CERTIFICATE OF INSERVICE INSPECTION ....
-_I,the undersigned, -holdingayalid-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 April 30, 2002 to June 4,2002. and state-that-to the-best-of my-I described in this knowledge and belief, the Owner has performed examinations and taken corrective measures 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, he-rrffolre,ýleithler the concerixng the examinations and orrectivemieasures described in this-Ovn-ee'sRE-po-rt.-F nor Inspector -yhis pl oy Th Leiable"in_-anymaerfo_"anypersonal___jury___-propertydamagor-a lossfny kind arising from or connected with this inspection.
- Commirissions WI-100128 -
National Board, State, Province, and Endorsements .
- Inspector's Signature Date: ,f*.,t *.j -zt*.*
PBF-7050 -SEM7.11.I Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the-ASME Code Section XI
- 1. Owner Nuclear Management Corporation "Date Feb:ruary 26, 2002 Sheet: 1_ of 1 700 First Street, Hudson, WI 54016 2.- Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0202642 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 Expiration Date N/A Two Rivers, WI 54241
- 4. Identification of System: Safety Injection Westinghouse Spec 676370 Rev. 0
- 5. (a) Applicable Construction Code N/A 19 N/A Edition, No Addenda, NoCode 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) 219-015B Byron Jackson 671N0449 None P-15B Unknown Replacement No
- 7. Description of Work: Replacement of casing studs.
- 8. Tests Conducted: Hydrostatic El Pneuma'tic El Nominal Operating Pressure 0 Other El Pressure NOP psi Test Temp. NOT *F System Leakage Test
- 9. Remarks RRM2002-0014 U A Applicable Manur~cvI'T s Data lxxIk.epo -n. a c eg CERTIFICATE OF COMPIUNCE ..
We 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 replacement Type Code Symbol Stamp: -N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed _----/__ ,,- - ISI Coordinator-Date __ -/2_-7jo -.
[ w &r
?sel's Dg Owner's Designee, d"]Owneror Title -ide __
_-- CERTIFICATE OF INSERVICE INSPECTION-----
__ I, the undersigned, holding a valid c _ommission issued by the National Board-of Boiler and Pressure Vessel
¶
-Inspectors afid the State of Province of-Wisconsin-and employed by HSB CT have inspected the components described in this Owner's Report during the period --February 21, 2002 to February 26.-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-theexai ntfis and--6rr-cti*ie- iures descib-ed in-this-Ow -*-'e eprt,-uttrthermoreiieithert- ----- _--
_nspector'nor his-employer.skalbe 4e~tia-ble_'-wmanyanner for-any-personalnuly-rppbrtylet*' _ a _ossfany kind arising from or connected with this inspection.
&.4 :-
............... Coimmissions WI-100128 Inspector's Signature National Board, State, Province, and Endorsements Date: - ,
PBF-7050 - ----. SEM7lI1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions-of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date May 20, 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 9938170 Repair Organization P.O. No, Job No. Etc.
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A nime 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A addreq,
- 4. Identification of System: Reactor Coolant Westinghouse Spec 676243
- 5. (a) Applicable Construction Code ASME III 19 65 Edition, No Addenda, No Code Casi (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)
R-A CE N/A N/A N/A Unknown Replacement No
- 7. Description of Work: Replacement of the male flange.
- 8. Tests Conducted: Hydrostatic E] Pneumatic El Nominal Operating Pressure '
Other El Pressure 2302 psi . Test Temp. 535 OF System Leakage Test
. Remarks RRM2002-0039, CAP_028538_____
Apphcable Manufacttrcrs Data RMpor s to be attached.
CERTIFICATE OF COMPLIANCE . . . .. .. . .
We 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 replacement Type Code Symbol Stamp:-N/A ....
Certificate of Authorization No. Docket 50-301 Expiration Date N/A
-Signed---- -IS1 Coordinator-Date AI ._- _
r orOwner's De, nOw Title .
- CERTIFICATE OF INSERVICE INSPECTION -
I the undersigned, holding a valid commission issued by the National Board of Boi-e-r -and P-ress-ure V--essl-------
-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 20, 2002, andstate that to the-best-ofmy 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, concerii ii9i e xain--ati-ns -nd corrective me asure9d&cfribed in this Ovner's Repo-rt.-Fur'ha-rtf,6e-teitherthe-__
a nSlpector.nor his vmployer-hall bheji bleinany-manner for-any personal injury or-roperty ge ossfy .......
_ kinaý arising from or connected with this inspection.
.,-- -- Commissions WI-100128 Inspector's 'ignature National Board, State, Province, and Endorsemnents Date: 7- 2'-OL PBF-7050
.-- SEM-7.111l ---
Revision 1 05/17/02 .
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Piovisions of the ASME Code SectionXI
- 1. Owner Nuclear Management Corporation Date Noi rember 14, 2001 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 9948927 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 addreq
- 4. Identification of System: Containment PDMS Dwg D-17
- 5. (a) Applicable Construction Code N/A 19 N/A Edition, No Addenda, No Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Edition, 1992 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)
C--D2 Westinghouse N/A N/A None Unknown Replacement No
. 7. Description of Work: Replaced, cleaned, inspected, anti relubed oirings and sealing surfaces.
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other [ Pressure psi Test Temp. OF Appendix J Local Leak Rate Test
- 9. Remarks RRM 2001-0090 Apphcable Manufacturer's Data Reports to be attached.
-* - CERTIFICATE OF COMPLIANCE "-
We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. tepair or replacenet ..
Type Code Symbol Stamp: -NIA Certificate of Authoriza No. Doke 50-301 Expiration Date N/A Signed--/- .ISI -.-- Coordinator-Date-- _c-- t 2/,, , ---
,Jwnor ..uvIWUm LX;3ZgflVCI RUc
__CERTIFICATE OF INSERVICE INSPECTION ....................
_I,_the undersigned, holding a valid commission issued byth-e 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-theperiod -November 10, 2001 to November -14. 2001, andstate-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 n6r his employer makes any warranty, expressed or implied, -__._-.
concering-the examiniationisýund-e-m-rri eaý--ns*.ires described in this Owner's-Rep6 u-t-Ffhermore,-a,-ithe-?the__ .
-_nspector iior-his-employer-shall be-liablei n anner for-any -personal injuryperty-dam ,geor'a4oss-fp _Ml kind arising from or connected with this inspection.
/.-- "- -- Commissions WI-100128 - ..
Inspector's Signature National Board, State, Province, and Endorsements Date: & 2. .2 ..... ..... _..
PBF-7050 Revision 1 05/17/02 --SEM 7.11.1 - ---.
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date Octcober 24, 2001 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9944064 Repair 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
- 4. Identification of System: Chemical and Volume Control Westinghouse Spec 676370
- 5. (a) Applicable Construction Code None 19 N/A 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 Senal No. No. Identification Built --- -Replacement- -(Yes or No)
P-M02A Westinghouse 6456 N/A P-2A Unknown Replacement No
- 7. Description of Work: Replace seat in discharge check valve due to cracking.
- 8. Tests Conducted: Hydrostatic E] Pneumatic El Nominal Operating Pressure Dl Other 0 Pressure NOP psi Test TIemp. NOT 'F "SystemLeakage Test
- 9. -Remarks RRM 2001-0070 ............
A licable Manufactarer's Data R-rts to be attached.
CERTIFICATE OF COMPLIANCE . .. ..
We 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 replacement
-Type Code Symbol Stamp: N/A Certificate of Auorization No. Doc et 66 Expiration Date N/A Signed---i/T--* 4 *.-- - -ISI Coordinator-Date---
O~cnr o Owefs-Desipie,-Title
-______ - CERTIFICATE-OF INSERVICE INSPECTION -.......
_- Ite 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 -August 13, 2001 to October 24.-2001 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 ithe Inspector nor his employer makes any warranty, expressed or implied, conceming-the exaaminat'-0-----a..dE-ff-rcive measures descrbed in this Owner's Repo*rt.-F-uthermore, neitherthe_-_--
_ -Inspector'nor his employershallbeiable i"-nymmiierfor"any personal injury orproperty __amageoraoss-of~any 7 kind arising from or connected with this inspection.
- / y,.
- ," Lf) , Commissions WI-100128 Inspector's Signatu-e National Board, State, Province, and Endorsements
-Date:_ ,-_-___ _.. . ...
PBF-7050
- ..... Revision 1 05/17/02 - - SEM7.1.1 . .
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
.As Required by the Provisions of the ASME Code Section XG
- 1. Owner Nuclear Management Corporation Date N'o*ember 2, 2001 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 9937081 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 Riyers, WI 54241 Expiration Date N/A siddre.d
- 4. Identification of System: Component Cooling Water Bechtel Spec 6118-M-78 Rev. 6
- 5. (a) Applicable Construction Code B3.1 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)
Aa-152N-1-H33 Unknown N/A N/A N/A Unknown Replacement No
- 7. Description of Work: Replaced adjustment assembly on piping support.
- 8. Tests Conducted: Hydrostatic El Pneumatic El No minal Operating Pressure El Other El Pressure - psi '1Fest Temp. OF None
-9.--Remarks -RRM 2001-0073 D...~f~,..tr.
!,ý C C C a = I- 4tuched CER-TIfCATE OF COMPLIXME We 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 repbcentnt
-Type Code Symbol Stamp: -N/A - - -----
Certificate of Authorization No. Docket 50-266 Expiration Date N/A Signe -J 4 5o' - -- --- ISI Coordinator-Date - /7-/ .
'Owner
-or Own.es Designee, Tie-.
_ ----_-- --- S......... CERTIFICATE--OF INSERVICE INSPECTION 1, the undersigned, holding a valid commi'ssion 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-August 28, 2001 to November 2, 2001,-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 XIU... ...
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerningtihe ex-amiia-tionsandcorrective measures de-E-iibe-d in this Ow--'s Rei-t-Fithermore, neither-he_- .... .
3nspector-finof-s mployer shallUbe--iable--m-anyimannner-for-anypersoml injuryr-roperty_,arge-oria 'lossoftany_
- kind arising from or connected with this inspection.
--__Cd
---.--- , s-siiiibons- WI-100128 Inspector's Signa6re National Board, State, Province, and Endorsements Date: =
- ,A iq, * *4,-
PBF-7050
-Revision 1 05/17/02 - SEM-7.1I1A
FORM NIS-2VOWNER'S EEPORT FOR REPAIRS OR.REPLACEMrENTS As Required by the Provisions of the ASMiE Code Section XI
- 1. Owner Wisconsin Electric Power Company Date April 4, 2000 231 West Michigan, Milwaukee, WI 53201 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9512275, MR 94-091*B Repair Organization P.O. No., Job No. Etc.
- 3. Work Performed By: Wisconsin Electric Power Co. Type Code Symbol Stamp N/A 6610 Nuolear Road, Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
- 4. - Identification of System: Component Cooling 5' (a) Applicable Construction Code B31.1 19 67 Edition, N/A Addenda, N/ACode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition No Addenda
. A*,*ro,, ,,f r,,in,,pne PI i(ri. nr P enhe~imdnnlRenlaeement Comn~onents Repaired, ASME National Replaced, Code Name of Component Name of Manufacturer Board Other Year or Stamped Manufacturer Serial No. No. Identification Built Replacement (Yes or No)
Aý-152N-9-2SBH-8 N/A N/A N/A N/A Unknown Replacement No AC-152N-14-2SBH-2 N/A N/A N/A N/A Unknown Replacement No
- 7. Description of Work: Modity supports m accordance win vR.9+-u0--B.
- . Tests Conducted: Hydrostatic [] Pneumatic El Nomir tal Operating Pressure El Pressure psi Test Temp. OF___
Other E] _
- 9. Remarks RRM 1996-0003, CR 97-0887, CR 99-3222 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We 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 replacement
-Type Code Symbol Stamp: N/A__
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed _ ,ISICoordinatorDate_ *7 ,20
- -- Owner or Owner's DesigneeTitle r*-l.,9 11
-_5_CERTIFICATEOFINSERVICE-INSPECTION -. .
I, the--d~ne*!d,--flding-avalid ommissi6-s--6 7b]-the-'N*-i--l Bo f Bfile- aVne
-dPfof II -
¶
-Inspectors and the State of Province of-Wisconsin -and employed-by-HSBII,-Co. of--Hartford,-CT-have inspected the components described in this Ownerks Reportduring-the-period_02115/96_to-04/04/00, 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, conce&rning thd exafminationsaFnd corrective measures d-H *--cbe--d ---- Owner-s-Rei-r£ Furthermore, ne ther the inspector-norihis employeroshalliable*_-_nynm*-q_-*p-ersona- y- *
- g*9ra4oss _fnny_
kind arising from or connected with this inspection. "
S4_.,,.* .......
-*/4/* - Commissions WI-100057 -
Inscter' Sinaur National Board, State, Province, and Endorsements Date: J4-L,L. ->13109
FORM NIS-2 O,WNEk'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Wisconsin Electric Power Company Date March 1, 2001 231 West Michigan, Milwaukee, WI 53201 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9924572, MR 99-069*B Repair Organization P.O. No., Job No. Etc.
- 3. Work Performed By: Wisconsin Electric Power Co. Type Code Symbol Stamp N/A 6610 Nuclear Road, Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
- 4. Identification of System: Chemical and Volume Control West Specs G676258 and G676272
- 5. (a) Applicable Construction Code USAS B31.1 19 67 Edition, N/A Addenda, N/ACode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, N/A 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)
CY-01298 Flowserve Corp. E083T-I-2 N/A CV-1298 Unknown Replacement No
- 7. Description of Work: Replace valve due to increase in RCS pressure.
I/
- 8. Tests Conducted: Hydrostatic [] Pneumatic L] Nrominal Operating Pressure Other L] Pressure psi Test Temp. OF
- 9. Remarks RRM 00-0015, Code Case N-416-1, CR 01-0312, CR 01-2030, CR 01-0603
"" - Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASMt Code,Section XI. repair or replacement
-Type Code Symbol Stamp: NIA .....
Certificate of Authorization No. Docket 50-301 Expiration Date NIA Signed . _,ISI CoordinatorDate_ .T,t , ,20 0/ ...
Owner or Owner's Designee, _Title
_ __ - CERTIFICATE OFINSERVICE-INSPECTION -....
I ,the untdaiisigni,-d,_ldiig -avalid coEmi s--on d b3,-th-*
jis na-r B6*-d-6f Boilerd PriiurfVeissl ---
' -Inspectors and the State of Province of-Wisconsiniand employed by-HSBII,-Co.-of-Hartford, CT-have inspected-
-_the components described in this Owner's Report-during-the-period-10125100_to -03/01101, 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,
-conf-erniing-the exfaminati6i -in.d c-rrective measures des-c-n-b-ed Own-r----fe- or.Frrth-rre,-Cith-r the lnspectornor-his employer shalIoe-iablI-__anyl ane_ _jotany-p ersona-linjuryr-property-damage oraioss of any__
_ kind arising from or connected with this inspection.
"Commissions WI 10°057 ..............
Inpector Sigt National Board, State, Province, and Endorsements Date: JC,,y ' (1 8
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS, As Required by the Provisions of the ASME Code Section XI
- 1. Owner Wiscoisin Electric Power Company Date January 31, 2001 Sheet: 1 of 1 231 West Michigan, Milwaukee, WI 53201 Unit 2
- 2. Plant Point Beach Nuclear Plant WO 9924867 6610 Nuclear Road, Two Rivers, WI 54241 Repair Organization P.O. No., Job No. Etc.
. . 4 4 **
- 3. Work Performed By: Wisconsin Electric Power Co. Type Code Symbol Stamp N/A 6610 Nuolear Road, Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
- 4. Identification of System: Safety Injection Bechtel Spec. M-21
- 5. (a) Applicable Construction Code API Standard 650 19 N/A Edition, 3rd Addenda, N/ACode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, N/A Addenda A* dentificaionn of Comnonents Renaired or Reolaced and Replacement Components Repaired, ASME National Replaced, Code Name of Name of Manufacturer Board Other Year or Stamped C6mponent Manufacturer Serial No. No. Identification Built Replacement (Yes or No) 2ý-013 Graver N/A N/A T-013 Unknown Replacement No
- 7. Description of Work: - Add new anchors and reinforce existing anchor bolt suteners.
- 8. Tests Conducted: Hydrostatic [] Pneumatic [] Nominal Operating Pressure []
Other 11 Pressure _ psi Test Temp. OF
- 9. Remarks RRM 2000-0020, CR 01-1985, CR 01-0312; CR 01-0603 rt* tn h* *ttn*h*d CERTIFICATE OF COMPLIANCE We 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 replacement
-Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed 2__ *..Z'.Pv L_ -t ,ISI CoordinatorDate_..._V,(t, 20 I
- -- Owner or Owner's Designee,_Ttl'
...... -CERTIFICATE OFINSERVICE-INSPECTION -_
____Ith- idholdng- ah d comnssi iss-d b i-thi-NalB6-od-6f B*iler -and Pfessure VdFel
-_------ L-Inspectors and the State of Province of-Wisconsin-and-employed-by-HSBII,-Co.-of-Hartford, CT--have inspected
-the components described in this Owner's Report during-the-period--04/13/00 to-01/31/01, 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 eaminationsand -rretve measures eO r --- rthe Y--
ore,Iieth-e- the 3nspector-nr his employer shalUleliable- 3-n _ erieonypersmiiIrjury v-propertyiiamage or-aoss ofmany
- kind arising from or connected with this inspection......
. ".... .Com**mComissions WI-100057 Inspectoes Signature National Board, State, Province, and Endorsements
,Date: Jay4 If, of
SFORMPNIS-2.OWNER'S REUORT FOR REPAIRS OR REPLACEMENTS..
As ieciuired by the Provisions of the ASME C6de Section XI
- 1. Owner Wisconsin Electric Power Company Date March 4, 2001 231 West Michigan, Milwaukee, WI 53201 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9920011 Repair Organization P.O. No., Job No. Etc.
- 3. Work Performed By: Wisconsin Electric Power Co. Type Code Symbol Stamp N/A 6610 Nuclear Road, Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
- 4. Identification of System: Main Steam
- 5. (a) Applicable Construction Code ASME III 19 80 Edition, 1980 Winter Addenda, N/ACode 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 I Repaired, ASME
- 0 National Replaced, Code Name of Manufacturer Board Other Year or Stamped Name of Serial No. No. Identification Built Replacement (Yes or No)
Component Manufacturer MS-05959 Copes Vulcan N/A NIA MS-5959 Unknown Replacement No
- 7. Description of Work: Replacement of valve plug.
- 8. Tests Conducted: Hydrostatic [] Pneurrtat ic [] Nominal Operating Pressure EI Other El Pressure _ psi Test Temp. OF 0 Remnarks RRM 2000-0032.
Applicable Manufacturer's Data Reports to be attached.
te - CERTIFICATE OF COMPLIANCE We 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 replacement
-Type Code Symbol Stamp: N/A Certificate of Authorization No.- Docket 50-301 Expiration Date N/A Signed /_ w6e DegeeTt-
, SICoordinator__Date - /oA /0 ,20 c'" __
_____Owner or Owneres DesigneeTitle I
CERTIFICATE-OFJNSERVICEINSPECTION .... - __
= eommission issued by---the-N-fi-il Bi-ad-f B~ilf--a-d Presi-u*-Vess--e ige-d,_h-olin-g-a-Valid cI,-. -1 Y
-Inspectors and the State of Province of-Wisconsin-and-employed by-HSBII Co.-of-Hartford, CT-have inspected the components described in this Owner's Report during-the-period-0-7!27/00 to_03/04/01, 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, concerfnigthe &xafiioisfi isiand Core-ctiviemeasres descrtbeidi---ttOw--O-n'-Rep-rt----TrL theFln-oe, neither the-inspectornor his employer shall be liableiiny for-ny_ ersa--on yr- p ropertydmage ra -lossofny_
kind arisin from or connectedwith this inspection.
S ....... p * - Commissions WI-100057
_ Inspectofs Signatuire National Board, State, Province, and Endorsements Date: 17411u- i'd 2&
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date May 3, 2002 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 9947297 Repair Organization P 0 No., Job No Etc
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A narme 6610 Nuclear Road Authorization No. N/A
-Two Rivers, WI 54241 Expiration Date N/A
- 4. Identification of System: Reactor Coolant/Chemical and Volume Control, ASME Class 1 Bechtel Spec : M-78 Revision 6
- 5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, NoCode 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)
S&Aitached
- 7. Description of Work: Piping supports were installed or modified in order to bring all piping and other in-line" components within their applicable design stress code requirements
- 8. Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El
-t Other "Pressure T psi Test Temp. OF None
- 9. Remarks RRM 2001-0076, CAP 028770 Applicable Manufacturer's Dais Reports to be attached CERTIFICATE OF COMPLIANCE We 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 replacement.
Type Code Symbol Stamp: N/A Certificate of Authorization No. Expiration Date N/A
-Signed ---- ---ISI Coordinator Date Owner or Owner's Designee, Title - "¶___ _____-"_
--- - _ _CERTIFICATE OF INSERVICE INSPECTION
___Ithe undersigned, holding --valid-commissionissued-b-yi e National Board-of Bailer andiEressureessel 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 September 27, 2001 to May 3, 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.
-- Bysigning this certificate;neither-the Inspector nor his employer makes any warranty,-expressed or implied, conceming the examinations andccan'ectivemneasuresdescribed in this Owner's Report. -urthermore,iieitherthe 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.
- I*°nspectores Silgature -- -C omBvissions WI-100128i . . m.
National Board, State, Province, and Endorsements p os .
sd Date: gob J_~
PBF-7050 Revision 1 05/17/02 .SEM 7.11.1
FORM NIS-2 CONTINUATION, OWVNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI t
- 1. Owner Nuclear Management Corporation Date Ma) (3,2002 Sheet: 2 of 2 700 First Street, Hudson, WI 54016 Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 9947297 6610 Nuclear Road, Two Rivers, WI 54241 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 Expiration Date N/A Two Rivers, WI 54241 address
- 4. Identification of System: Reactor Coolant/
Chemical and Volume Control Bechtel Spec M-78, revision 6
- . (a) Applicable Construction Code B31"1 19 67 Edition, N.o Addenda, NCode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition, No Addenda 6 T4entifieation of Comnonents Repaired or Replaced and Replacement Comp onents 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)
N/A N/A N/A SI Unknown Replacement No RC250IR-13-SI N/A N/A N/A S2 Unknown Replacement- . No RC250IR-13-S2 N/A N/A N/A S3 Unknown Replacement No RC2501R-13-S3 .
N/A N/A N/A S5 Unknown Replacement No RC2501R-13-S5
-RC250IR-13-S6 N/A N/A N/A S6 Unkr-oý-R -placement No N/A N/A N/A S9 Unknown Replacement- No RC250IR-13-S9 RC250IR-13-S10 _N/A _N/A . .. N/A Replacement- __No____
Unknown - -S10__
A - S1l... Unkiown -Re-p-lacement No
-RC2501R-I13-S I1 N/A -N/A
..N/A - N/A- -N/A- L' I 'I __ -17 -[*ýPmpnf- U P r--) -;ni R- T-1-S 12 - -.
-RC2501R-13SNI N/A - -N/A- -N/A SNI Unknown -Replacement--No -
q _______________________
PBF-705Ca Revision 1 05/17/02
-SEM-7.11 ... .
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I. Owner Nuclear Management Corporation Date lun* 13, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0205986 Repair Organization P 0. No Job No Etc.
- 3. Work Performed By: We Energies Type Code Symbol Stamp N/A nmme 6610 Nuclear Road Authorization No. N/A Two Rivers, WI 54241 Expiration Date N/A
- 4. Identification of System: Component Cooling Water 10 CFR 50 Appendix B
- 5. (a) Applicable Construction Code ASME VIII 19 65 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)
CC-00763A Crosby N78089-00-flC N/A CC-763A Unknown Replacement No
- 7. Description of Work: Like for like replacement of relief valve.
- 8. Tests Conducted: Hydrostatic E] Pneumatic EL Nominal Operating Pressure "
Other [ Pressure NOP psi Test Temp. NOT *F System Leakage Test
- 9. Remarks RRM 2002-0030 Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We 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 replacement
-Type Code Symbol Stamp: N/A -
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed .. ISI Coordinator- Date-- > 7 -/*L*°-o 2 "" - -
- - -weorOnsDesignceTitl
___CERTIFJCATEOF-INSERVICE INSPECTION - _. .. .
_-_,___ I -dsignp-d,-holdinfg-avali'd co e-dth ss ue b-yth*-Ntioi-al B oad of Boiler---ndPressure l ...
"-Inspectors and the State of Province-of-Wisconsin -and employed by HSB CT have inspected the-components
_descnrbed in this Owner's Report during the-period- April 25, 2002 to June 13. 2002. and state that-to-the-best-of-my knowledge and belief, the Owner has performed examinations and taken corrective measures descnrbed in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
By signipg this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied,
-concerning the examinations and corrective-measures-describedin-this Owner's Report.Furthermoreneither-the-
_ _ spectormor his employer shall be liable'in nnyimanner for-any'personal injury or-property damage or-a toss of-any.
kind arising from or connected with this inspection.
I--.. ... .Commssions WI-100128 Inspector's S/gnature . National Board, State, Province, and Endorsements Date: e1+/-,.t, g -
PBF-7050
"-:T7-. 1 ACIl-71A)"
iv sl'lll on d I*1
-_- SEM7.I---
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Managemenit C6oporation Date June 13, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0205878 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 4oddren g
- 4. Identification of System: Component Cooling Water Westinghouse Spec G-676257 Rev. 2
- 5. (a) Applicable Construction Code ASME VIII 19 65 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)
Ck-00763B Crosby waow-m-C2- N/A CC-763B Unknown Replacement No
- 7. Description of Work: Like br like replacement of relief valve.
Nominal Operating Pressure [
- 8. Tests Conducted: Hydrostatic El Pneumatic nl Other Z Pressure NOP psi Test Temp. NOT °F
% System Leakage Test 9.-Remarks RRM 2002-0028 A....1.,-..h!. flt, iirt, enh ,t'hed A pplicable manufacturtes Data Re r_arts to be a=ched.
CERTIFICATE-OF COMPLIANCE We 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 replacement
-Type Code Symbol Stamp: N/A -
Certificate of Authorization No. Docket 50-301 Expiration Date N/A
-Signed - ISI Coordinator-Date -- ____"____-__-_
____________ - Ownr owri Own esgnee. I itle rF ii
_.... ___-- CERTIFICATE-OFINSERVICE INSPECTION
-I,the---dig-eýd hold__g a-validL commission issued lythe National B-oard of Boiler and Pressure Vessel I
-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-April 28-2002 to June 13. 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,
-t on-ceimin-gthex--&xaminations and corretiVe-easu-res-des*cnbd in this-Owner's Report.-Furthermored,-neitha*'fe----
inspector -nortisv-mployer shall be iiableinaunymanerformnypersonal injuryor-property d age-,ra oss'vfmny
_ kind arising from or connected with this inspection.
-T --.. ... Commissions--WI-100128 -
Inspector's Sigrfature . . National Board, State, Province, and Endorsements
-D ate: _ _ _ _.-__ _ _ _. _ . . .....
PBF-7050
-- SEM-7.1 11-
-Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner -Nuclear Management Coporation Date MalS4, 2002 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 9939921 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 addr -;%
- 4. Identification of System: Containment Westinghouse Spec 677020
- 5. (a) Applicable Construction Code ASME III 19 65 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Edition, 1992 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)
CA3 Unknown N/A N/A None Unknown Replacement No
- 7. Description of Work: Replacement of fuel transfer tube flange bolting.
- 8. Tests Conducted: Hydrostatic El Pneumatic 0 Nominal Operating Pressure El Other El Pressure 62.2 psi Test Temp. OF b ORT-12 (Pneumatic Leak Test) Performed
- 9. Remarks RRM 2002-0040.......
Apphcable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We 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 replacement Type Code Symbol Stamp: -N/A --- _..
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed /tO -- 2 /l*
SO~ ncr-or Ownei's-,signe,7tle
( - - ISI Coordinator-Date--- g-_ 2....
_ CERTIFICATE OF INSERVICE INSPECTION . .. ......
I,th*tide-signed,h-lding agrlid commission isued by-theNatioB.
S d"lf 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 4. 2002, and-statedthatto-the-best-ofmy-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 signipg 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-Furfh*ermore, n-either-tlfe
_ nspectornor his emplooer shallbe liableinnny manner for any-personalinjury qpjperty2anmge pr-a4oss'ofany
- kind arising from or connected with this inspection.
______ _. __.......... _.. ... Commissions WI-100128 Inspector's Sigmature National Board, State, Province, and Endorsements Date: , , ....
PBF-7050 '
Revision 1 05/17/02 .- ..-... . SEM 7.11.1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
.As Required by the Provisions of the-ASME Code Section XI I Date August 9, 2002
- 1. Owner Nuclear Managemerit Coiporation Sheet: 1 of 1 700 First Street, Hudson, WI 54016 Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 0203103 6610 Nuclear Road, Two Rivers, WI 54241 Repair Organization P 0. No., Job No Etc.
Type Code Symbol Stamp N/A
- 3. Work Performed By: We Energies 6610 Nuclear Road Authorization No. N/A Expiration Date N/A Two Rivers, WI 54241 sdldrer
- 4. Identification of System: Safety Injection West Specs G-676262, G-677264, DG-M02
- 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 Manufacturer Board Other Year or Stamped Name of Manufacturer Serial No. - -No. Identification Built Replacement (Yes or No)
Component Conval N/A N/A SI-845E -. Unknown Replacement No S?-00845E
- 7. Description of Work: Replacement of check valve.
- 8. Tests Conducted: Hydrostatic LI Pneuma tic LI Nominal Operating Pressure NOP psi Test Temp. NOT *F SOther El -Pressure System Leakage Test 9.--Renfiarks . RRM 2002-0021C6ode-Cae-N416-I *D Applicable Manufacturer's Data Reports to be attached.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the repair or replacement ASME Code,Section XI.
Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date N/A Owinr ISI Coordinatr atee A
' I Owner or Owres's Designee. Title -
-. __CERT1IICATE-OF-INSERVICE-INSPECTION. .
Vessel
-- I;the undersigned, holding avalid-conmmissionrissued-by-the-Nafional Board of-Boiler and Pressure Inspectors and the State of Province of Wisconsin and employed by HSB CT have mspeced-th-i-components
-described in this Owner's Report-dur h-e pe---iod----I- 2,--20021toAu-usft872002. and state that to-the best of described in this my knowledge and belief, the Owner has performed examinations and taken corrective measures Owner's Report in accordance with the requirements of ASME Code,Section XI.
orimplied,
By signing this certificate, neither-the-Inspector-nor-bis employermakes-any-warranty, expressed Owner's Report. Furthermore, neither the
.concernýg The examinations and corrective measuresdescribedin-this or property damage or a loss of any
-Inspector nor his employer shall be liablei-ranymiannerforanypersonallnjury kind arising from or connected with this inspection.
- Con..issions-4/,1/jt.'.
Inspector'esignature National Board, State, Province, and Endorsements Date: -., Z 0-. 2 .
PBF-7050 SEM 7.11.1 -
Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
- - As Required by the Provisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date August 1,2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 0205497 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 Westinghouse Spec 676270
- 5. (a) Applicable Construction Code None 19 No 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 Senal No... -.-No.- -Identification Built Replacement (Yes or No)
St100839B Copes Vulcan N/A N/A SI-839B Unknown Replacement No
- 7. Description oTWork: Replaced valve trim.
8.-- Tests Conducted: Hydrostatic El Pneumatic El Nominal Operating Pressure El Other E] -Pre,ssure _ psi Test Temp. OF None RRM 2002-0023-
-9_- Remarks RRM 2002-0023 1. - -ý. n " D__ - 1'. amche(j CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repar or replacement Type Code'Symnbol Stamp: N/A-Certificate of Authorization No. Docket 50-301 Expiration Date N/A Sign-eedr o-Ownes Dsigde, TtleD_-_
- Owner or Ownier's Designee, Title -
S . ...... ER--IFI CATEAIOF:INSERVICEINSPECTION _......
¶ 1;-the-undersigned, holding-a valid commission-issued by the-National-Board-of-Boiler and Pressure Vessel ---
-Iý_ecitors-aind the State-of Proviiin---f-Wisconsin and employedby-HSBCT have insMtPd th-components
-des*cibed in this Owner's Report during thep-eHiod-ApnT-l-2002-t--AW-f-8,-20022-ah-d 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 signihg this certificate, -neitherthe Inspector nor his employerimakesany yrarranty, expressed or implied, concerning the exaniinations and corrective-measures describedin-this Owner's Report. Furthermore, neither the
-Inspector nor his employer shallbe liable in any-manner-for-any personamlijury or-property damage or a loss of any kind arising from or connected with this inspection. -_-_-___.....
Commissions t.J 1 100 1 2-8
.nspectoe- ignature National Board, State, Proiince, and Endorsements Date: Axý PBF-7050
- .Revision 1 05/17/02 SEM 7.11.1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
_As Required by the Provisions of the-ASME Code Section X)
- 1. Owner Nuclear Management Corporation Date May31, 2002 700 First Street, Hudson, WI 54016 Sheet: 1 of 2.
- 2. Plant Point Beach Nuclear Plant Unit: - 2 6610 Nuclear Road, Two Rivers, M97 54241 WO 9936175, 9948259 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: Reactor Coolant
- 5. (a) Applicable Construction Code See Remarks 19_ Edition, _Addenda, 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)
"[z, Attached Page
- 7. Descriptioin of Work: Replacement vent valves, piping, and pipe support..
- 8. Tests Conducted: Hydrostatic El Pneumatic F1 Nominal Operating Pressure [
Other [ Pressure NOP psi Test Temp. NOT *F System Leakage Test
- 9. Renrtarks RRM 2002-0001, 2002-0002,_2002-0034; Code-Case N-416-_1, Construction Codes: ASME Section III, Class 2 of 1980 Edition, Summer 1981 Addenda; ASME Section III, Class 2 of 1977 Edition thru Winter 1978,-ASME Section III,-Subsection NF, 1974 Edition thru Summer of 1976.
Applicable Manufacturer's Data Reports to be attacheed.
CERTIFICATE OF COMPLIANCE
We 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 replacement Type Code Symbol Stamp: N/A Certificate of AuthorizationNo. DocketS0-301 - Expiration Date _N/A.
ISI Coordinator Date r-1-/1-aA d Z ---
S.................
nrwner's Desenee*wwy .....
Title - - ------ - - -- - -
ii- -h DeiniTil
-&e
___ CERTIFICATEOFINSER-VICENSPECTlON--
__I,_the undersigned, holding valid commission issued-by the.NationalBoard-of Boiler and Pressure Vessel a
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 April 30, 2002 to May 31, 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-ofASME Code,-Section-XI.
-.By siglnig this certificate,ineither the Inspectornortliis eimpoyErzMakl:nyxmwanty, 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 Inspectorsrgnature '-. National Board, State, Province, and Endorsements Date: "w* r ,A,, ._ .
I 9I PBF-7050 Revision 1 05/17/02 SEM 7.11.1
FORM NIS-2 (ONTINUA.ON OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME-Code Section XI
- 1. Owner Nuclear Management Corporation Date May 31, 2002 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 9936175, 9948259 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 address
- 4. Identification of System: Reactor Coolant Construction Codes: ASME Section III, Class 2 of 1980 Edition, Summer 1981 Addenda, ASME Section III, Class 2 of 1977 Edition thru Winter 1978, ASME Section III, Subsection NF, 1974 Edition thru Summer of 1976
- 5. (a) -Applicable Construction Code See Above 19 Edition, ___ Addenda, _ 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 0 Name of Name of Manufacturer Board Other Year or Stamped Component. Manufacturer Serial No. No. Identification Built Replacement (Yes or No)
RC-00570A" Target Rock N/A N/A RC-570A Unknown Replacement Yes Co rp . _ . . ... . . .
RC-00570B Target Rock N/A N/A RC-570B Unknown Replacement Yes Corp. -. "
RC-00575A Target Rock N/A N/A RC-575A Unknown Replacement Yes Corp.
RC-00575B Target Rock N/A - N/AI-- RC:575B- -Ufikn-dwn Replacement Yes
_ __ _Corp.
RC-00580A Target Rock N/A" N/A RC-580A Unknown Replacement Yes RC-00580B Target Rock N/A N/A RC-580B Unknown Replacement Yes Corp. -I- _ I ___ Id_
-- PS-12 N/A N/A iN/AV N/A-- -Unknown i-Replacement- -- No 4 4 1 + +/-
PBF-7050a Revision 1 05/17/02 SEM7.11.1 -
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS A3-R*-quired by the Provisions'of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date June 13.2002 7,00 First Street, Hudson, WI 54016 Sheet: 1 of 2 Unit: 2
- 2. Plant Point Beach Nuclear Plant 6610 Nuclear Road, Two Rivers, WI 54241 WO 0206367 Repair Organization P 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 "zddrem
- 4. Identification of System: Reactor Coolant West Specs 676258, 676262, G-569866, Bech Spec M-78 Rev. 6, AWS DLI.1, AISC 6h1Edition
- 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
- j Component Manufacturer -Serial No. No. Identification Built Replacement (Yes or No)
See Attached Page
- 7. Description of Work: Replacement of valve, small sections of pipe, U-bolt and adjacent support.
- 8. Tests Conducted: Hydrostatic El Pneumatic n Nominal Operating Pressure [
Other ' -Z 'Pressure NOP psi Test Temp. NOT OF System LeakageTest
- 9. Remarks RRM 2002-0043, 2002-0044, Code Case N-416-1
- Applicable Manufacturer's Data Reports to be attached. -
CERTIFICATE OF COMPLIAM'*E We 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 replacement Type Code Symbol Stamp: N/A Certificatd of Authorizatiofi No. Docket 50-301 -- Expiration Date NIA
-Signed -SIt-Goordinator-Date
__Owner or Owners Designee, Title __-____- .... _ _ _ _ _ _ _ _
- III-I -
_-- - CERTIFICATE-OFJINSERVICE-INSPECTION
_I, the undersigned, holding a valid commission issued by-the-National Board-ofBoiler-andP-ressure-Vessel
-Inspectors and the State of Province of Wisconsin and-employed-byi.SB CT-have inspected the components described in this Owner's Report during the period May 7, 2002 to June 13, 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 bfASME Code;Section XI.
-By signing this certificate;neither the Inspectornor his-ermployer-makes-anywarranty,-expressed or implied,
!oncerning lhe examinations and corrective measures describedinthisiOwn ,z~epart-Frthermore,-meither 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-J .. . Commissions-WI-100128 Inspector's Signhlture .. National Board, State, Province, and Endorsements f -/A '-o 21-- "',
Date:
PBF-7050 SEM 7.11.1 __
Revision 1 05/17/02
-- FORM NIS-2 CON1INUATION" "
OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Req-uired by the Provisions of the ASIVIE Code Section XI
- 1. Owner Nuclear Management Corporation Date Junt e13, 2001 700 First Street, Hudson, WI 54016 Sheet: 2 of 2 Unit: 2
- 2. Plant Point Beach Nuclear Plant WO 0206367 6610 Nuclear Road, Two Rivers, WI 54241 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 Expiration Date N/A Two Rivers, WI 54241 address
- 4. Identification of System: Reactor Coolant West Specs 686258, 686262, G-569866, Bech Spec M-78 Rev. 6, AWS Dl. 1, AISC 6 t"Edition
- 5. (a) Applicable Construction Code B31.1 19 67 Edition, No Addenda, NoCode Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986 Edition No Addenda
- 6. Identification of Components Repaired or Replaced and Rep)lacement Comp onents 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)
Darling Valve N/A N/A RC-427 Unknown Replacement No RC-00427 Co.
RC-00427 Piping N/A - N/A N/A N/A Unknown Replacement No 6R-C-250 iR-1c0- o N/A Rep N/A N/A N/A Unknown -Re-placement No
]___________ NIA rA I
______ I I I I I t
-I I I PBF-7050a SEM 7.11.1 Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Piovisions of the ASME Code Section XI
- 1. Owner Nuclear Management Corporation Date Aug,ust2, 2002 7,00 First Street, Hudson, WI 54016 Sheet: I of I1
- 2. Plant Point Beach Nuclear Plant Unit: 2 6610 Nuclear Road, Two Rivers, WI 54241 WO 9940403 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 addre* q --
- 4. Identification of System: Component Cooling Water West Spec 676262
- 5. (a) Applicable Construction Code USAS 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 Comp~onents 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)
P~e AC 0152N-04 I N/A N/A N/A N/A Unknown Replacement No
- 7. Description of Work: Replacement of piping for realignment.
- 8. Tests Conducted: Hydrostatic ED Pneumatic El Nominal Operating Pressure 0 0
Other 0 Pressure NOP psi Test Terp. NOT F Seat Leakage Test ,¢
- q-
___9-__Rem~arks __ RRM 2001-0075_
Applicable Manufacturetes Data Reports to be attached.
.. - CERTIFICATE-OF-COMPLIANCE-- _
We 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 replacement
-Type Code Symbol Stamp: -N/A -
Certificate of Authorization No. Docket 50-301 Expiration Date N/A Signed - ISI Coordinator-Date -. .. /*-/ 0))2
___ II - - -- - -
"fl,,,,ernr Ownaer's Destwnee. Title - . - . r owner or Owner's Dest-ce, Title -- - - , -.
___________ i1]
... "- CERTIFICATE -OF-INSERVVICEINSPECTION I the undersigned, holding a alid commission issued by thFeNational-B-oard-f Boile--ancd-Pressure Viessl q
I -Inspectors and the State of Province of-Wisconsin-and employed by-HSB=-T-have-inspected the-components
-described in this Owner's Report during the-periodSeptember-20-2001 toAugust2,2002,-and state that to.the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Ownpes Report in accordance with the requirements of ASME Code,Section XI.
By sigfiing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, coeiimaig the examinations and -corrective-measures-des-cribedin this-Owner'Is-Report7-Furthermore, neither the jnpeatornor his employer shall be liable in anynannerIfortnyypstmalinTy* _petydamage cra'loss cf&ny .
kind arising from or connected with this inspection. "
-7'-' / Commissions-WI-100128- - -
Inspector's Signature Natio-nal Board,-State, Province, and Endorsements Date: t ' /0,r z v.
PBF-7050 SEM 7.11.1 -....
-Revision 1 05/17/02
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the ProVisions of the ASME Code Sectioxi XI
- 1. Owner Nuclear Management Corporation Date - August 8, 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 0205496 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 siddreq
- 4. Identification of System Safety Injection Westinghouse Specs G676262, G677264, DG-M02
- 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 of-r - Stamped
- Component Manufacturer Serial No. No..-- Identification Built Replacement- -(Yes or-No)
Sht00845A Conval N/A N/A SI-845A Unknown Replacement No
- 7. Description of Work: Like for like replacement of check valve.
- 8. Tests Conducted: Hydrostatic E Pneumatic [] Nominal Operating Pressure SOther [E -Pressure NOP psi Test Temp. NOT-- *F
- -- System Leakage Test 9--R*emiarks- -RRM 2002-0025, Code Case-N-416-1 be attached.
to Data Manufacturegs At*olieable Reoorts Annlicable Manufacturer's Data Renarts to be attached.
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repahor ieplacement Type Code Symbol Stamp: N/A Certificate of Authorization No. Docket 50-301 Expiration Date-.-N/A .
Sign-e " ISI Coordinator Date __!-
Owner or Owner's Designee, Title c_ - X CERTIFICATE-OF-INSERVICE INSPECTION S- I,-the-undersigned.holdinga valid commission-issued bythe-National Board of Boiler and Pressure-Vessel Inspectors and the State of-Province of Wisconsin and employed by HSB CT hVe-insj-ed-the components d rb-.-- drin-the p- -d--Ap-I15,2002t6 -AKilst 8, 2002 andstaeat 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: - - - ----- -M
- -By-signing this certificate, neitheritheInspector-nor-his employer makes any-warranty, expressed-orimplied,
. ...rnceing the examinations and corrective measures described in-tbis Owner's Report. Furthermore,-ieither-the
-Inspector-nor-is employer-shall be-liable in-anymanner-for-any-personal injury or property damage-or-&loss oT-any kind arising from or connected with'this inspection.
____________________ Commissions-. ,________
Inspector's Sig&ature National Board, State, Province, and Endorsements Date: , /:-O2.- 2 -
PBF-7050 Revision 1 05/17/02 _SEMý71_TA1