ML20195F978
ML20195F978 | |
Person / Time | |
---|---|
Site: | Point Beach ![]() |
Issue date: | 06/10/1999 |
From: | WISCONSIN ELECTRIC POWER CO. |
To: | |
Shared Package | |
ML20195F976 | List: |
References | |
NUDOCS 9906150153 | |
Download: ML20195F978 (100) | |
Text
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Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee,WI 53201 Point Ileach Nuclear Plant, Unit 2 I
6010 Nuclear Road Two Rivers, WI 54241
)
Docket 50-301 Commercial Service Date IM)ln2 I
j UNIT 2 REFUELING 23 INSERVICE INSPECTION
SUMMARY
REPORT FOR FORM NIS-1 Written by:
x Date: 00
- 97
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9906150153 990610 Reviewed by:
Date: /-/B-71 PDR ADOCK 05000301
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[hvh Approved by; ate:
Page 1 of 26
l 1
Wisconsin Electric Power Co.
l.
331 West Mk;higan Avenue
[
Milwaukee, WI 53201
(-
Point Beach Nuclear Plant. Unit 2 6610 Nuclear Paed Two Rivers, WI 54241 Docket 50-301 j
conunercial service Date 10/01n2 Acronyms l
ASME American Society of Mechanical Engineers l
l CR Condition Report l
IDR Indication Disposition Report l
IN Information Notice i
I ISI Inservice Inspection LTP Long Term Plan MT Magnetic Particle Examination NDE Nondestructive Examination NRC Nuclear Regulatory Commission PBNP Point Beach Nuclear Plant PT Liquid Penetrant Examination PWA Professional Welding Associates RAYTHEON Raytheon Engineering (Formerly EBASCO Services Incorporated)
RRM Repair / Replacement / Modification SwRI Southwest Research Institute UT Ultrasonic Examination VT Visual Examination WE Wisconsin Electric Power Company WE-NDE Wisconsin Electric Power Company, NDE Group I
WO Maintenance Work Order Page 2 of 26
Wiscornin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI $3201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road i
Two Rivers, WI 54241 Docket 50-301 Conunercial service Date 10/01/72 Table of Contents
1.0 INTRODUCTION
2.0 CODE CASES AND INTERPRETATIONS 3.0 ABSTRACT OF EXAMINATIONS 3.1 Determination of Scope i
3.2 Scope of Component / Weld Examinations i
3.3 Completed Component / Weld Examinations l
l 3.4 Pressure Tests 3.5 Snubber Surveillance Tests 3.6 IWE/IWL Examinations l
4.0 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE MEASURES TAKEN 4.1 Component / Weld 4.2 Pressure Tests 4.3 Snubber Surveillance Tests Page 3 of 26
1 Wiscocin Electric Power Co.
- 231 West Michigan Aream
. Milwaukee. WI 53201 Point Beach Nuclear Plant. Uni: 2 6610 Nuclair Road Two Rivers. WI 54241 Docket 50-301 Commercial Service Date 10/01n2 UNIT 2 REFUELING 23 INSERVICE INSPECTION
SUMMARY
1.0 INTRODUCTION
From September 13,~ 1997 to March 14,1999, non-destructive examinations of selected components at PBNP, Unit 2, were performed. These examinations constitute the second examination of the second period, of the third 10-year interval at PBNP, Unit 2. The time interval for this examination period included the Unit 2 Refueling 23 outage (U2R23) that ran from December 6,1998 to March 1
4,1999.
2.0 CODE CASES AND INTERPRETATIONS This report and examinations were completed applying the following:
J 2.1 ASME Code Interpretation, Section VIII-1-83-17, which 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).
2.3 Code Case N-460 (Class 1 and Class 2 weld examination coverage).
2.4 Code Case N-481 (Alternate examinations for RCP Pump Casings).
2.5 Code Case N-491 (Alternate examinations for Supports).
3.0 ABSTRACT OF EXAMINATIONS 3.1 Determination of Scope Components and system areas were selected for examination in accordance with the following:
l 3.1.1 PBNP FSAR, Technical Specification Section 15.4.2.B.
j 3.1.2 Long Term Inservice Examination Plan for Class 1, Class 2, and Class 3 systems at Point Beach Nuclear Plant, Third Interval, Unit 2.
3.1.3 Augmented Examination Program of Section 4 of the Inservice Inspection Long Term Plan, Third Interval.
l l
Page 4 of 26 i
(-
1-Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant. Ursit 2 l
6610 Nuclear Road Two Rivers. WI 54241 Docket 50301 Conunercial service Date 10/0!n2 l3.2 Scope of Component / Weld Examinations Representative samples of the following components and system areas were examined with NDE techniques by WE-NDE, RAYTHEON, PWA, and SwRI personnel.
Pressurizer.
A Steam Generator B Steam Generator Residual Heat Removal Heat Exchanger Seal Water Heat Exchanger Class 1 Pressure Retaining Valve Bolting Class 1 Piping and Supports Class 2 Piping and Supports 1
Class 3 Pipe Supports 3.3 Completed Component / Weld Examinations CODE or HEADING DESCRIPTION Exam Type Defines the requirement or reason for the examination performed.
86E-03 Examination performed as required by ASME Section XI,1986 Edition, No Addenda.
A04-03 Additional examinations in accordance with N-491-2430(b).
B03-03 Augmented examinations performed on the Main Steam Bypass Line Energy Absorbers.
B04-03 Augmented examinations performed on Threaded Fasteners, per IEB 82-02.
Page 5 of 26
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee WI 53201 Point Beach Nucicar Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 Commercial Service Date 10/01n2 B07-03 Augmented examinations performed on safety injection accumulator nozzles in accordance with NRC Inforanation Notice 91-05.
C01-03 Additional examinations on supports on line SIS-02-SI-2003 (CR 99-0315).
C02-03 Additional examinations on FW-2H8 (CR 98-4174).
C03-03 Additional examinations on FW-2H2 (CR 99-0002).
i D02-03 Baseline examination on snubbers prior to placement into OM-4 program.
E01-03 Alternate examinations performed in accordance with Code Case N-481.
E02-03 Preservice examinations performed following the unit heat-up and cool-down l
cycle per Code Case N-491-2220(b).
P42-03 Preservice examination for RRM 98-0101.
I P43-03 Preservice examination for RRM 98-0092.
P44-03 Preservice examination for RRM 98-0102.
l P45-03 Preservice examination for RRM 99-0003.
R09-03 Examination performed per IDR 98U2-7P004.
l R10-03 Examination performed per W.O. 9901182.
R11-03 Examination performed per W.O. 9809879.
X18-03 Supplemental examination per IDR 98U2-7P018.
X19-03 Supplemental examination per IDR 98U2-7P014.
X20-03 Supplemental examination per IDR 98U2-7P016.
i X21-03 Supplemental examination per IDR 98U2-7P021.
Page 6 of 26
Wisconsin Electric Power Co.
231 West Michigan Areenue Mdwaukee, WI 53201 Point Beach Nuclear Plant, Urdt 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial Servke Date 10/01n2 Ind Type Description of Indications G
= Geometry I
= Insignificant or Non-Relevant Indica'. ions N
= No Indications R
= Recordable Indications Results Indicates the Outcome of a Particular Exam P
= Pass F
= Fail C
= Conditionally Accepted N
= No examinatior, performed Program Indicates whether or not ASME Section XI credit has been taken for the Credit exam. Augmented or other examinations not performed for an ASME Section XI requirement will be indicated by an N.
The following are database printouts that summarize the ISI examinations that were performed during the Unit 2 Refueling 23 outage, j
i Page 7 of 26
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t Wiscxrin Electric Power Co.
L 231 West Michigna A"enue Milwaukee,WI 53201 j
Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Comnwrcial Service Date 10/01n2 i
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P F P F P F P F P F MCE MCE MCE MC MCE D
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F N0 M F N0 M N0 M F N0 M F N0 M F
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P F P F P F P F P F MCE MC MC MC MCE D
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66 66 66 66 66 88 88 88 88 88
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R R
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T TU O
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R R
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s2M 0
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1 2
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n 8
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s 1
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P
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1 0
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/0 ME
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0 0
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E E
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6 6
6 6
6 6
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8 8
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5c D
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1 1
1 1
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T T-T-
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m
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0 0
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9 9
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l Et e
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TN
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l I
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3 3
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1 1
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.ER ER ER ER ER ER RI RI RI RI RI RI ES DEMA=
HPC P
HC HPC P
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H H
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SE SE SE SE SE SE AR AR AR AR AR AR OO F=
PP E WU WU WU WU WU WU MMMIL=
VO5 VO5 VO5 VO5 VO5 VO5
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PL6 PL6 PL6 PL6 PL6 PL6 T
CCIR=
RCB RCB RCB RCB RCB RCB
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=
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2
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N N
N N
N N
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=
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=
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1 1
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P P
P P
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0 0
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7 7
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2 2
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tn n
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9 9
9 9
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c
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9 9
9 9
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9 9
9 9
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/
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/
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1 1
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c
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/
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/
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1 1
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0 0
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tn w
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P
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1 0
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0 0
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6 6
6 6
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1 1
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m S
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C
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NK
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C
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3 3
3 3
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w s
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cis ihi
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PC HC P
P HC P
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2 2
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H H
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SE SE SE SE SE SE AR AR AR AR AR AR OO F=
PP E
WU WU WU WU WU WU S0 S0 S0 S0 MMMIL=
VO5 VO5 VO5 VO5 VO5 VO5 S0
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PL6 PL6 PL6 PL6 PL6 PL6 T
CCIR=
RCB RCB RCB RCB RCB RCB
=
=
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3 DP 4
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N N
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=
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P P
P P
P P
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3 4
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2 2
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P P
P P
P P
P D
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0 0-0 0
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5 5
5 5
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7 7
7 7
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2 2-2 2
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n n
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8 8
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9 9
9 9
9 9
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rRo a
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1 1
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/
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l 1
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1 0
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3 3
3 3
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0 0
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6 6
6 6
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8 8
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5c D
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1 1
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V V
V V
V V
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Dm
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m S
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C
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0 0
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0 0
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3 me0
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0 0
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n eAi D
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9 9
9 9
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l B=
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FPICA=
3 3
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1 1
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2 2
2 2
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ER ER ER ER R
R R
RI RI RI RI I
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P HC HC HPC P
P P
P P
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S S
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2 3
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H H
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U U
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WU WU WU WU AD B BD0 4
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VO5 VO5 VO5 VO5 5
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0 2
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PL6 PL6 PL6 PL6 8
8 8
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RCB RCB RCB RCB SRF SRF SRF (llIl'
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N N
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N N
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6 6
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P P
P P
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4 4
4 4
4 4
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5 5
5 5
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7 7
7 7
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2 2
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tn n
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0 rRo 0
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9 9
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4 4
4 4
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/
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1 2
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0 0
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A A
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Wisconsin Electne Power Co.
231 West Michigan Avenue Milwaukee.WI 53201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial service Date 104)1/72 i
3.4 Pressure Tests 3.4.1 ASME Section XI Pressure Tests Following are pressure tests that have been conducted as part of the pressure test program at PBNP since the last refueling outage. The PBNP Pressure Test Program utilizes Code Case N-498 for pressure tests on ASME Class 1 and 2, N-498-1 (Relief Request PTP-3-05) for Class 3, and N-522 (Relief Request PTP-3-02) for containment penetrations. ASME Class 1,2, and 3 systems have been tested in accordance with the Pressure Test Program which was developed to meet ASME Section XI requirements. The PBNP Pressure Test Program is currently undergoing revision as outlined in NPM 99-0000, " Pressure Test Project Plan." It is the opinion of the Authorized Nuclear Inservice Inspector that the ASME Section XI requirements for periodic pressure testing were not completed in accordance with the Code requirements. The discrepancies are primarily associated with inadequate implementing procedures and are being resolved in accordance the corrective actions documented in Condition Report 98-3574 for Unit 1 and is also applicable to the Unit 2 pressure tests conducted during this reporting period.
Test
Description:
System Leakage Test of Class 1 Components Following Refueling Outage.
System:
Reactor Coolant Test Document:
IT-235 Completion Date:
02/24/99 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 Chemical and Volume Control System Outside Containment System:
Chemical and Volume Control Test Document:
IT-22 4
Completion Date:
03/02/99 Test Dr'cription:
40-Month Functional Test of ASME Class 2 Containment Sump B Suction Line System:
Safety Injection Test Document:
IT-536 Completion Date:
03/23/98 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 3 Component Cooling Water Outside Containment System:
Component Cooling Water Test Document:
IT-1125-2 Completion Date:
03/10/99 Page 9 of 26
Wisconsin Electric Power Co.
231 West Michigno Avenue Milwaukee,WI 53201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial service Dee 10/01/72 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 Chemical and Volume Control System Inside Containment System:
Chemical and Volume Control Test Document:
IT-235 Completion Date:
02/24/99 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 Residual Heat Removal System System:
Residual Heat Removal Test Document:
IT-535C/D/E Completion Date:
03/26/98 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 Containment Spray System Except Spray Nozzles -
System:
Containment Spray Test Document:
IT-06 Completion Date:
03/26/98 I
Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 High Head Safety Injection System System:
Safety Injection Test Document:
IT-535C/D Completion Date:
01/29/99 Test
Description:
40-Month Inservice Pressure Test Of ASME Class 2 Low Head Safety Injection System System:
Safety Injstion Test Document:
IT-535E Completion Date:
02/15/99 Test
Description:
40-Month Inservice Pressure Test Of Refueling Water Storage Tank System:
Safety Injection Test Document:
IT-1075 j
Completion Date:
11/10/97 j
i Test
Description:
40-Month Inservice Pressure Test Of Spray Additive Tank
(
System:
Safety Injection Test Document:
IT-1115-2 Completion Date:
10/05/98 4
i Page 10 of 26
1
)
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant, Unit 2 l
6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial service Date 104)1n2 3.5 Snubber Surveillance Tests 3.5.1 ASME Section XI Snubber Surveillance Tests Following are snubber inservice tests that have been conducted as part of the snubber surveillance test program at PBNP since the last refueling outage.
TEST DESCRIPTION: Snubber Inservice Tests
'ASME SECTION XI, Class 1,' < 50 kips Snubber:
HS-24 Test Documents:
WO 9809600 Completion Date:
01/16/99 Results:
\\cceptable Snubber:
HS-31 Test Documents:
WO 9809602 Completion Date:
01/16/99 Results:
Acceptable Snubber:
HS-2501R-15 Test Documents:
WO 9809607 Completion Date:
12/29/98 Results:
Acceptable Snubber:
HS-2501R-43 Test Documents:
WO 9809608 Completion Date:
01/13/99 Results:
Acceptable Snubber:
HS-2501R-49 Test Documents:
WO 9809609 Completion Date:
12/23/98 Results:
Acceptable Page 11 of 26 i
r Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee.WI 53201 Poim Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 5+301 Comnwrcial service Date 10/01n2 ASME SECTION XI, Class 2, > 50 kips Snubber:
HS-33 Test Documents:
WO 9809603 Completion Date:
01/22/99 Results:
Acceptable Snubber:
HS-34 Test Documents:
WO 9809604 Completion Date:
02/04/99 Results: Acceptable Snubber:
HS-41 Test Documents:
WO 9809605 Completion Date:
01/19/99 Results:
Acceptable Non-Code Class Snubber:
HS-29 J
Test Documents:
WO 9809601 Completion Date:
01/12/99 Results:
Acceptable Snubber:
HS-601R-37 Test Documents:
Completion Date:
12/22/98 l
Results:
Developed an O-ring leak during stroke testing (See CR 99-0147)
Snubber:
HS-601R-95B (Additional test due to HS-601R-37)
Test Documents:
Completion Date:
01/16/99 Results:
Acceptable 3.6 IWE/IWL Examinations l
In accordance with 10 CFR 50.55a, a program is being developed and implemented to perform baseline examinations of the Class CC and MC components during the outage. These preservice examinations are currently in progress. A separate summary report will be filed after the completion of these preservice examinations to document the IWE/IWL portion of ISI.
Page 12 of 26 i
L
l
!~
I Wisconsin Electric Power Co.
}
l-231 West Michigan Ave mae Milwaukee.WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI $4241 Docket 50-301 conunercialservice one som1m 4.0 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE MEASURES TAKEN 4.1 Component / Weld Nondestructive examinations were performed by PWA, WE-NDE, RAYTHEON, and SwRI personnel. The nondestructive examinations utilized were MT, PT, RT, UT, and VT techniques. All the examinations were performed in accordance with written procedures that conform to the applicable sections of the ASME Boiler and Pressure Vessel Code.' The following is a summary of the recorded indications found during the examinations and evaluated by WE personnel.
IDR 98U2-7P001, Class 2, SPRING HANGER, FW-2H1 i
Data Sheet No. 98U2-754P026, Drawing No. ISI-PRI-2250 Method: VT-3 Indication: Spring hanger setting out ofrange.
Disposition: Accept as is.
The condition found was evaluated in accordance with the guidance provided in a memorandum l
I written by Civil / Structural Engineering (NPM 94-0225), which provided acceptance criteria for as-found variable spring support settings, which do not conform, to documented design settings.
l The recommended tolerance for load settings on variable spring hangers, which are located adjacent to equipment nozzles (no other vertical supports prior to the nozzle), is
- 5%. The setting recorded was within 1.6% of the design value, therefore, the condition is considered j
allowable with no additional or successive examinations required.
j l
IDR 98U2-7P002, Class 2, CONSTANT SUPPORT, FW-2H2 Data Sheet No. 98U2-754P024 & 98U2-754P105, Drawing No. ISI-PRI-2250 Method: VT-3 l
Indication:. Rod with damaged threads.
l Disposition: Replace rod, reexamine.
The rod with damaged threads is not acceptable per Code Case N-491, 3410. Condition Report CR 99-0002 was initiated to document this condition. The threaded rod was replaced and is now in an acceptable condition. The other conditions which were noted on examination record 98U2-754P024 were documented during U2R22 on %U2-754P055 and IDR %U2-7P014. These conditions were determined at that time to be allowable in accordance with N-491. These conditions were evaluated on condition report CR 97-0449.
IDR 98U2-7P003, Class 2, CONSTANT SUPPORT, FW-2H8 Data Sheet No. 98U2-754P025, Drawing No. ISI-PRI-2251 Method: VT-3 Indication: Loose nut on threaded rod.
Page 13 of 26
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee.WI $3201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road i'
Two Rivers.WI 54241 Docket 50-301 Conunercial service Date 10/0!n2 Disposition: Tighten nut, reexamine.
A review of previous data was performed on FW-2H8, and it was determined that this support was examined during U2R22 and found to have no recordable indications. The Civil / Structural group was consulted regarding this condit. ion, and it was determined that the nut which was loose was~ in fact, not required for the proper operation of the support. The nut on the bottom side of the structure is the threaded rod's load bearing member. Due to the fact that the loose nut is not a " support item," the condition found on FW-2H8 is acceptable i
per Code Case N-491,3410. However, a condition report /W.O. request was generated.
After tightening, the support was reexamined with no recordable indications noted. No
- additional or successive examinations are required.
IDR 98U2-7P004, Class 2, RIGID SUPPORT, H-21 Data Sheet No. 98U2-754P018, Drawing No. ISI-PRI-2262
. Method: VT-3 Indication: Nut with incomplete thread engagement, paint on sliding stanchion.
Disposition: Re-torque nut, reexamine.
The first condition is not allowable per Code Case N-491,3410(a). This condition was
. addressed by tightening the nut and reexamining it. The nut then had full thread engagement and was acceptable per Code Case N-491.. The 2"' indication is allowable per Code Case N-491, 3410(6). Paint on tire support will not affect the operability of the support, as it is not a close tolerance machined or sliding surface. This support will be scheduled for a subsequent i
examination during the next period.
As a result of indication nuinber 1, additional examinations were performed in accordance with N-491,2430(a). These examinations found no evidence of any failures on any of the additional supports, therefore, no additional or subsequent examinations are required on any of the additional supports. Per N-4912420(b), the support will be scheduled for successive examinations during the next period.
IDR 98U2-7P005, Class 2, COMPONENT SUPPORT, SG-A-MAIN S'UPPORT-1 Data Sheet No. 98U2-754P034, Drawing No. ISI-PRI-2112 Method: VT-3 Indication: Nutloose.
Disposition: Re-torque nut, reexamine.
A review of previous data was performed, and it was determined that the support was examined for preservice during SGRP (U2R22) and found to be acceptable. The loose nuts violate the acceptance criteria of N-491, 3410. However, after tightening, the condition is
)
. acceptable per N-491, 3122.2(a)(1). Therefore, the condition after correction can be Page 14 of 26
l Wisconsin Electric Power Co.
l 231 West Michigan Avenue Milwaukee, WI 53201 Poira Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 Commercial service Date 10/01/72 I
considered allowable. Per N-4912420(b), the support will be scheduled for successive examinations during the next period.
IDR 98U2-7P006, Class 2, PIPE TO ELBOW, SIS-02-SI-2010-08 Data Sheet No. 98U2-451P009, Drawing No. ISI-PRI-2257 Method: PT Indication: 0.13-inch rounded indication it base material.
Disposition: Accept as is.
The indication was evaluated by the WE, NDE Level III to the acceptance criteria of ASME Section XI, IWC-3500. Since IWC does not have acceptance criteria, the acceptance criteria of I
IWB-3514 was applied. The indication is allowable in accordance with Table IWB-3514-2. No i
additional or successive examinations required.
IDR 98U2-7P007, Class 2, ELBOW TO PIPE, AC-08-RHR-2005-05 Data Sheet No. 98U2-451P030, Drawing No. ISI-PRI-2223 Method: PT Indication: Two adjacent rounded indications in the base material.
Disposition: Accept as is.
The indications were evaluated by the WE, NDE Level III to the acceptance criteria of ASME Section XI, IWC-3500. Since IWC does not have acceptace criteria, the acceptance criteria of IWB-3514 was applied. The indications are allowable in accordance with Table IWB-3514-2.
No additional or successive examinations required.
IDR 98U2-7P008, Class 1, RIGID SUPPORT,11-PHC Data Sheet No. 98U2-754P038, Drawing No. ISI-PRI-2156 Method: VT-3 Indication: Plate pulled away from wall approximately 0.10 inches.
Disposition: Accept as is.
A review of previous data was performed, and it was determined that no previous examinations had been performed on this support. This support was added to the program as a result of the Third Interval program upgrade. The indication, which was recorded on 11-PHC, was evaluated by the WE Seismic Group and determined to have been caused by improper rigging on the supports. Therefore, this indication is not inservice related. Two adjacent supports were also found to be in similar condition. Supports 11-PHA,11-PHB, 11-PHD, and 11-PHE were examined to ensure that this was not an inservice related condition. Condition Report CR 99-0315 was initiated to document the conditions found on i
the three affected supports. Sargent and Lundy performed an Operability Evaluation for the i
line SIS-02-SI-2003 and determined that even with assuming the three supports, which had pulled anchor bolts, were inactive, the piping and support loads meet the PBNP operability Page 15 of 26 1
L__
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI 53201 Poim Beach Nuclear Plam. Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial service Date 10/0102 criteria for piping. Therefore, the piping can be left in the as-found condition and repair work
)
will be performed during U2R24. This evaluation was transmitted to WE via transmittal form DIT-PB-EXT-0497-01, and the analyses will be documented in Stress Report WE-200087, Revision 01, Addition C. After the completion of the repairs during U2R24, the affected supports will be reexamined.
IDR 98U2-7P009, Class 2, COMPONENT SUPPORT, SG-A-MAIN SUPPORT-3 i
Data Sheet No. 98U2-754P036, Drawing No. ISI-PRI-2112 Method: VT-3 l
Indication: Nutloose.
Disposition: Re-torque nut, reexamine.
A review of previous data was performed, and it was determined that the support was examined for preservice during SGRP (U2R22) and found to be acceptable. The loose nuts l
violate the acceptance criteria of N-491,3410. However, after tightening, the condition is 1
acceptable per N-491, 3122.2(a)(1). Therefore, the condition after correction can be considered allowable. Per N-4912420(b), the support will be scheduled for successive examinations during the next period.
I I
IDR 98U2-7P010, Class 2, RIGID SUPPORT, H-205A Data Sheet No. 98U2-754P073, Drawing No. ISI-PRI-2259 Method: YT-3 Indication: Bent rod.
Disposition: Accept as is.
The indication does not appear to be inservice in nature, due to the fact that the adjacent supports were examined this outage and did not exhibit any sign ofinservice degradation. The cross-i sectional area of the rod has not been significantly reduced, and the load-carrying capabilities of the support have not been affected, therefore, the support is operable. No additional or successive examinations are required.
IDR 98U2-7P011, Class 2, RIGID SUPPORT, H-205B Data Sheet No. 98U2-754P074, Drawing No. ISI-PRI-2259 Method: VT-3 Indication: Bentrod.
Disposition: Accept as is.
The indication does not appear to be inservice in nature, due to the fact that the adjacent supports were examined this outag; and did not exhibit any sign ofinservice degradation. The cross-sectional area of the rod has not been sign.ificantly reduced, and the load-carrying capabilities of the support have not been affected. therefore, the support is operable. No additional or successive examinations are required.
Page 16 of 26
{'
Wisconsin Electric Power Co.
331 West Michigan Avenue i
L Milwaukee, WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 l
Docket 50 301 j
Conunercial service Dane 10/01n2 IDR 98U2-7P012, Class 2, COMPONENT SUPPORT, RHR-A-LEG-2 Data Sheet No. 98U2-754P080, Drawing No. ISI-PRI-2204 Method: VT-3 Indication: Nut not torqued against base plate Disposition' Accept as is.
1 The indication, which was recorded on RHR-A-LEG-2, violates the acceptance criteria of N-491-3410. This condition was reported in CR 99-0269, and an operability determination was performed which stated that this condition is acceptable as is. The basis for determining i
the structure operable is the fact that this condition was reviewed as part of the USI A-46 Seismic Verificetion Project and was determined to be seismically adequate. During a 1994 walkdown, the gaps were found on all four bolts / nuts. ' This is not considered to be an operability concern, because the bolts themselves provide adequate shear capacity. In addition, the top of the heat exchanger is supported in both lateral directions, therefore, there is not a potential for the heat exchanger to overturn. Although not required for operability of j
the supports, a Work Order Tag (WOT #141483) was issued to tighten these nuts, so that this issue does not arise in the future. Due to the above evaluations, this indication is considered to be allowable per N-491,3122.3.
This condition was documented in 1994 in Condition Report CR 94-465. At that time, the evaluation was that the base bolt nuts not being seated were not an operability issue, and they were accepted as is. Due to ALARA concerns, it was stated that the nuts would not be tightened, as they did not affect the operability of the component.
Although the conditions are considered acceptable as it, all the component supports on the "A" Heat Exchanger, as well as the adjacent "B" Heat Exchanger, will be scheduled for successive examinations. This does not appear to be inservice in nature due to the fact that the threads beneath the nuts were painted, j
IDR 98U2-7P013, Class 1, SAFETY INJECTION NOZZLE TO SHELL AT 108.5,
RPV-687-01-B Data Sheet No. 001130, Drawing No. ISI-PRI-2101 Method:' UT Indication: Seven subsurface indications.
Disposition: Accept asis.
The seven indications that were recorded were subsequently sized and determined to be allowable in accordance with IWB-3512-1. Five of these flaws were determined to have no measurable through-wall dimension. Due to the location of these flaws, they appear to be fabrication related. No additional or successive examinations are required.
Page 17 of 26
I Wisconsin Electric Power Co.
331 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 Commercial service Date 10/Oln2 IDR 98U2-7P014, Class 1, SAFETY INJECTION NOZZLE TO SHELL AT 288.5,
RPV-687-01-A
' Data Sheet No. 001120, Drawing No. ISI-PRI-2101 i
Method: UT Indication: Two subsurface indications.-
Disposition: Accept as is.
The two indications that were recorded were subsequently sized and determined to be allowable in accordance with IWB-3512-1. Due to the location of these flaws, they appear to be fabrication related. No additional or successive examinations are required.
IDR 98U2-7P015, Class 1, SAFE END TO SAFETY INJECTION NOZZLE AT 288.5,
RC-04-SI-2001-26 Data Sheet No. 001310, Drawing No. ISI-PRI-2130 Method: UT Indication: Foursubsurfaceindications.
Disposition: Accept as is.
Three of the four indications that were recorded were subsequently sized and determined to be allowable in accordance with IWB-3512-2. The fourth indication was sized and determined to be allowable in accordance with IWB-3514-2. These indications were not previously recorded due to the fact that this weld had not been examined for 100% of the volume. Due to the location of these flaws, they appear to be fabrication related. No additional or successive examinations are required.
l IDR 98U2-7P016, Class 1, SAFE END TO SAFETY INJECTION NOZZLE AT 108.5,
RC-04-SI-2002-29 Data Sheet No. 001320, Drawing No. ISI-PRI-2132 Method: UT Indication: Five subsurface indications.
Disposition: Accept as is.
Two of the five indications that were recorded were subsequently sized and determined to have
- c no measurable through-wall dimension. Therefore, they are allowable in accordance with
, IWB-3512-2. The other three indications were sized and determined to be allowable in i
accordance with IWB-3514-2. These indications were not previously recorded due to the fact that this weld had not been examined for 100% of the volume. Due to the location of these flaws, they appear to be fabrication related. No additional or successive examinations are required.
Page 18 of 26
Wisconsin Electric Power Co.
331 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301
. J.: service Dane 10 Min 2 IDR 98U2-7P017, Class 2, COMPONENT SUPPORT, RHR-A-LEG-1 Data Sheet No. 98U2-754P095, Drawing No. ISI-PRI-2204 Method: VT-3 Indication: Nut not torqued against base plate.
Disposition: Accept as is.-
The indication that was recorded on RHR-A-LEG-1 violates the acceptance criteria of
- N-491-3410. This condition was reported in CR 99-0269, and an operability determination was performed which stated that this condition is acceptable as is. The basis for determining the structure operable is the fact that this condition was reviewed as part of the USI A-46 Seismic Verification Project and was determined to be seismically adequate. During a 1994 walkdown, the gaps were found on all four bolts / nuts. This is not considered to be an operability concern, because the bolts themselves provide adequate shear capacity. In addition, the top of the heat exchanger is supported in both lateral directions, therefore, there is not a potential for the heat exchanger to overturn. Although not required for operability of the supports, a Work Order Tag (WOT #141483) was issued to tighten these nuts, so that this issue does not arise in the future. Due to the above evaluations, this indication is considered to be allowable per N-491, 3122.3.
This condition was documented in 1994 in Condition Report CR 94-465. At that time, the evaluation was that the base bolt nuts not being seated were not an operability issue, and they were accepted as is. Due to ALARA concerns, it was stated that the nuts would not be tightened, as they did not affect the operability of the component.
Although the conditions are considered acceptable as it, all the component supports on the "A" Heat Exchanger, as well as the adjacent "B" Heat Exchanger, will be scheduled for successive examinations. This does not appear to be inservice in natwe due to the fact that the threads beneath the nuts were painted.
IDR 98U2-7P018, Class 2, COMPONENT SUPPORT, RHR-A-LEG-3 Data Sheet No. 98U2-754P096, Drawing No. ISI-PRI-2204 Method: VT-3 Indication: Nut not torqued against base plate.
Disposition: Accept as is.
The indication that was recorded on RHR-A-LEG-3 violates the acceptance criteria of N-91-3410. This condition was reported in CR 99-0269, and an operability determination was performed which stated that this condition is acceptable as is. The basis for determining the structure operable is the fact that this condition was reviewed as part of the USI A-46 Seismic Verification Project and was determined to be seismically adequate. During a 1994 walkdown, the gaps were found on all four bolts / nuts. This is not considered to be an operability concern, because the bolts themselves provide adequate shear capacity. In Page 19 of 26 I
4 i
e:
l Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee.WI 53201 i
Point Beach Nclear Piara. Unit 2 6610 Nuclear Road Two Rivers, WI 54241 i
Docket 50-301 Commercial service Dane 10/0102 j
addition, the top of the heat exchanger is supported in both lateral directions, therefore, there is not a potential for the heat exchanger to overturn. Although not required for operability of the supports, a Work Order Tag (WOT #141483) was issued to tighten these nuts, so that this issue does not arise in the future. Due to the above evaluations, this indication is considered to.
l be allowable per N-491, 3122.3.
l This condition was documented in 1994 in Condition Report CR 94-465. At that time, the evaluation was that the base bolt nuts not being seated were not an operability issue and they..
were accepted as is. Due to ALARA concerns, it was stated that the nuts would not be d
tightened, as they did not affect the operability of the component.
l Although the conditions are considered acceptable as it, all the component supports on the "A"
]
Heat Exchanger, as well as the adjacent "B" Heat Exchanger, will be scheduled for successive 1
examinations. This does not appear to be inservice in nature due to the fact that the threads j
beneath the nuts were painted.
IDR 98U2-7P019, Class 2, COMPONENT SUPPORT, RHR-A-LEG-4 i
Data Sheet No. 9802-754P097, Drawing No. ISI-PRI-2204 1
Method: VT-3 Indication: Nut not torqued against base plate.
Disposition: Accept as is, i
The indication that was recorded on RHR-A-LEG-4 violates the acceptance criteria of i
N-491-3410. This ' condition was reported in CR 99-0269, and an operability determination I
was performed which stated that this condition is acceptable as is. The basis for determining L
the structure operable is the fact that this condition was reviewed as part of the USI A-46 i
Seismic Verification Project and was determined to be seismically adequate. During a 1994 i
walkdown, the gaps were found on all four bolts / nuts. This is not considered to be an l
operability concern because the bolts themselves provide adequate shear capacity. In addition, the top of the heat exchanger is supported in both lateral directions, therefore, there is not a potential for the heat exchanger to overturn. Although not required for operability of the l
supports, a Work Order Tag (WOT #141483) was issued to tighten these nuts, so that this l
issue does not arise in the future. Due to the above evaluations, this indication is considered to be allowable per N-491, 3122.3.
I" This condition was documented in 1994 in Condition Report CR 94-465. At that time, the evaluation was that the base bolt nuts not being seated were not an operability issue, and they were accepted as is. Due to ALARA concerns, it was stated that the nuts would not be tightened, as they did not affect the operability of the component.
Although the conditions are considered acceptable as it, all the component supports on the "A" Heat Exchanger, as well as the adjacent "B" Heat Exchanger, will be scheduled for successive
- Page 20 of 26
I
)
I Wisconsin Electric Power Co.
I 231 West Michigan Avenue Milwuutee.WI 53201 l
Point Desch Nuclear Plant. Unit 2 l
6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 Conunercial servke Date 10M)1n2 i
examinations. This does not appear to be inservice in nature due to the fact that the threads
{
beneath the nuts were painted.
IDR 98U2-7P020 j
THIS IDR NUMBER WAS CANCELLED l
IDR 98U2-7P021, Class 1, B PIPE TO ELBOW, RC-03-PSF-2002-04 Data Sheet No. 98U2-451P042, Drawing No. ISI-PRI-2137
)
Method: PT Indication: 0.15-inch linear indication in weld material.
Disposition: Accept as is.
The indication was evaluated by the WE, NDE Level III to the acceptance criteria of IWB-3514-2, and determined to be allowable. In addition, a UT sizing examination was performed in accordance with IWB-3514.3(b) in an attempt to determine if there was any through-wall extent to the PT indication. The UT examination determined that there was no discernable through-wall extent to the indication. This indication does not appear to be service related. No additional or successive examinations are required.
IDR 98U2-7P022 THIS IDR NUMBER WAS CANCE'LLED IDR 98U2-7P023, Class 2, SPRING HANGER, MS-2HS Data Sheet No. 98U2-754P117, Drawing No. ISI-PRI-2243 Method: VT-3 Indication: Incomplete thread engagement.
Disposition: Accept as is.
This condition was noted during U2R22 and accepted as is. The function of the bolt with incomplete thread engagement is only to hold the pipe clamp in place on the pipe when the clamp is disconnected from the spring hanger and thus maintaining the spacing dimension of the clamp. This bolt has no load bearing requirements. The nut is not loosened, and there is no evidence of damage to the insulation and the clamp spacing is being maintained. No additional or successive examinations are required.
IDR 98U2-7P024, Class 2, SPRING HANGER, MS-2H6 Data Sheet No. 98U2-754P118, Drawing No. ISI-PRI-2244 Method: VT-3 Indication: 2"d nut and bolt assembly on top of pipe clamp spins.
Disposition: Accept as is.
Page 21 of 26 l
esfMichigan ll MGwoukee.WI 53201 Point Beach Nuclear Plant. Unit 2 I
6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 Commercial service Date 10/0102 The assembly being able to move does not violate the criteria of N-491,3410, since the nut is tight. The function of the bolt is only to hold the pipe clamp in place on the pipe when the clamp is disconnected from the spring hanger and, thus, maintain'ing the spacing dimension of the clamp. This bolt has no load bearing requirements. The nut is not loosened, and there is no evidence of damage to the insulation and the clamp spacing is being maintained. No additional or successive examinations are required.
IDR 98U2-7P025, Class 2, SPRING HANGER,2H-03A Data Sheet No. 98U2-754P125, Drawing No. ISI-PRI-2224 Method: VT-3 Indication: Nut three threads down from flush, cold setting not within specified range, missing anchor bolt, debris in spring can.
Disposition: Accept as-is.
The nut which is three threads down from flush is acceptable per Code Case N-491, 3410, as there are no missing, detached, or loosened support items. The jam-nut with incomplete thread engagement does not violate the acceptance criteria, as the nut is tight against the first nut and there is sufficient thread engagement to allow it to perform its function.
The cold setting indication is acceptable per Code Case N-491, 3122.3. The evaluation of the as-found condition of this spring hanger was performed in accordance with the guidance provided by a memorandum written by Civil / Structural (NPM 94-0225). This memorandum a
provided acceptance criteria for as-found variable spring support settings, which do not conform, to documented design settings. The recommended tolerance for load settings on variable spring hangers which are isolated from equipment nozzles by at least one other vertical support may have load setting which exceed the design load settings by up to 20%. It l
is also allowable to have load settings, which are within 95% of the design load setting. The setting recorded on 2H-03A was 3000 lbs., which is within 1.2% (98.8%) of the design load setting value.
The missing anchor bolt violates the acceptance standards of N-491, 3410 (2), but is allowable per N-491, 3122.3. This condition was reported in CR 99-0422 and an operability determination was performed which stated that the support was operable with no further action required. It has been determined that since this is a variable spring can support, it provides gravity support only to this line. No upward or side loading on the support's floor mounted l
base plate is considered. Since there is only vertical downward loading of this baseplate, the anchors are installed for support stability reasons only. A DCN will be issued to properly reflect the as-left condition of the support.
)
The minor debris (paper / paint chips) located in the top of the spring can will not affect the
)
operability of the spring can, and is therefore allowable per N-491, 3410.
Page 22 of 26
]
j Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50 301 Commercial service Date 10/01n2 The above conditions can be considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P026, Class 2, SNUBBER, HS-41 Data Sheet No. 98U2-754P141, Drawing No. ISI-PRI-2201 Method: VT-3 Indication: Lack of thread engagement on snabber housing, evidence ofoil.
Disposition: Accept as is.
The conditions found on HS-41 are acceptable per Code Case N-491. The incomplete thread engagement is on the snubber housing plate, which is planned and is shown in Anker-Holth Manual 00013. Therefore, the condition is as designed, and is not an indication. The evidence of oil on the paddle, and the scoring of the brass ring are acceptable per Code Case N-491, as they do not affect the operability of the snubber. The scoring is slight, and has no detrimental effect on the snubber. The oil was wiped off the snubber by Maintenance, and the snubber was then checked for evidence of any leakage. No leakage was found, therefore, it i
can be assumed that the oil was from spillage during installation of the snubber, and not a leak. Therefore, all the conditions recorded can be considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P027, Class 2, SNUBBER, HS-34 Data Sheet No. 98U2-754P140, Drawing No. ISI-PRI-2245 Method: VT-3 Indication: Lack of thread engagement on plate connection to wall.
Disposition: Accept as is.
The conditions found on HS-34 are acceptable per Code Case N-491. The incomplete thread engagement on the plate connections to the pipe and wall were found during U2R22, and evaluated by Sargent and Lundy in letter SL-WE-97-105. It was determined that the capacity of a properly torqued bolted connection exceeds the tensile capacity of the threaded rod. The recommended thread engagement for steel fasteners is stated to be at least 0.8 times the nominal bolt diameter. The bolting on this connection meet this minimum requirement, therefore, the conditions recorded can be considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P028, Class 2, SNUBBER, HS-33 Data Sheet No. 98U2-754P139, Drawing No.1SI-PRI-2243 Method: VT-3 Indication: Lack of thread engagement on snubber housing and plate connection, evidence of oil.
Disposition: Accept as is.
Page 23 of 26
c j
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 l
onunercial service Date 10/0!n2 The conditions found on HS-33 are acceptable per Code Case N-491. The incomplete thread l-engagement is on the snubber housing plate, which is planned and is shown in Anker-Holth
' Manual 00014. Therefore, the condition is as designed, and is not an indication. The lack of thread engagement (one thread from flush) on the connection to the pipe is acceptable, as the l
connection is tight, and there is no evidence of inservice degradation. The evidence of oil on the paddle and on the wall is acceptable per Code Case N-491, as it does not affect the operability of the snubber. The oil was wiped off the snubber by Maintenance, and the snubber was then checked for evidence of any leakage. No leakage was found, therefore, it can be assumed that the oil was from spillage during installation of the snubber, and not a leak. Therefore, all the conditions recorded can be considered allowable with no additional or subsequent examinations required.
i IDR 98U2-7P029, Class 1, SNUBBER, HS-26 Data Sheet No. 98U2-754P138, Drawing No. ISI-PRI-2128 Method: VT-3 Indication: Snubber mtates approximately 45*, washers not installed.
l Disposition: Accept asis.
The conditions found on HS-26 are acceptable per Code Case N-491. The movement of the snubber is allowable, as the snubber should be able to move due to the spherical bearings, which are installed for this purpose. Washers are not required to be installed on either side of the bearing. Therefore, all the conditions recorded can be considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P030, Class 1, SNUBBER, HS-23 Data Sheet No. 98U2-754P137, Drawing No. ISI-PRI-2131 Method: VT-3 L
Indication: General corrosion on bearing, snubber pivots, washers located on outside of pipe clamp, bearing race approx.1/32" out of position.
Disposition: Accept as is.
The conditions found on HS-23 are acceptable per Code Case N-491. The slight corrosion on the spherical bearing does not affect the operability of the bearing, and is therefore allowable.
The lack of movement of the snubber on the pipe clamp connection is allowable, as the snubber's installation location does not require movement in the side-to-side direction, and this does not affect the operability of the snubber. The 1/32-inch offset of the spherical bearing is allowable, as it does not affect the operability of the snubber. Therefore, all the conditions recorded can be considered allowable with no additional or subsequent examinations required.
Page 24 of 26
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee, WI $3201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI 54241 Docket 50-301 corninercini service one to/0tm IDR 98U2-7P031, Class 1, SNUBBER, HS-22 Data Sheet No. 98U2-754P136, Drawing No. ISI-PRI-2135 Method: VT-3 Indication: Oil leak, paddle hitting pipe clamp, bolt on pipe clamp is 2 threads from flush.
Disposition: Accept as is.
l The conditions found on HS-22 are acceptable per Code Case N-491. The movement of the snubber is allowable, as the snubber should be able to move due to the spherical bearings, which are installed for this purpose. The lack of complete thread engagement on the pipe clamp is allowable because the bolted connection in question sees shear loads and the connection is tight. This does not affect the operability of the snubber. The oil was wiped off by maintenance personnel, and the snubber was then checked for evidence of leakage. No leakage was found, therefore, it can be assumed that the oil was from spillage during installation of the snubber, and not a leak. Therefore, all the conditions recorded can be l
considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P032, Class 1, SNUBBER, HS-25 Data Sheet No. 98U2-754P126, Drawing No. ISI-PRI-2129 Method: VT-3 Indication: Paddle hitting on weld beam attachment.
Disposition: Accept as is.
The conditions found on HS-25 are acceptable per Code Case N-491. The movement of the snubber is allowable, as the snubber should be able to move due to the spherical bearings which are installed for this purpose. This does not affect the operability of the enubber.
Therefore, all the conditions recorded can be considered allowable with no additional or subsequent examinations required.
IDR 98U2-7P033, Class N/A, SNUBBER, HS-27 Data Sheet No. 98U2-754P142, Drawing No. N/A Method: VT-3 Indication: Snubber pivots.
Disposition: Accept as is.
The indication found on HS-27 are acceptable per Code Case N-491. The movement of the snubber is allowable, as the snubber should be able to move due to the spherical bearings, which are installed for this purpose. Therefore, the snubber is operable and no additional or subsequent examinations are required.
Page 25 of 26
Wisconsin Electric Power Co.
231 West Michigan Avenue Milwaukee. WI $3201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road
)
Two Rivers, WI 54241 l
Docket 50-301
]
Commercial Service Dnee 10/01n2 i
4.2 Pressure Tests No reportable indications observed.
4.3 Snubber Surveillance Tests During the testing of snubber HS-601'R-37, the snubber developed a leak at an O-ring seal.
An additional snubber, HS-601R-95B, was removed and tested per Technical Specification i
requirements. Subsequently, an operability determination (as a result of CR 99-0147) was performed by the Seismic Group, which stated that HS-601R-37 was operable. Consequently, the additional testing of HS-60lR-95B was not required. All 11 snubbers Were determined to be operable. The frequency for the next testing interval remains at 18 months.
j 1
Page 26 of 26 l
[
Wisconsin Electre Power Co.
231 West Michiscn Avecae Milwaukee, WI 53201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Conunercial Service Date 10/01n2 UNIT 2 REFUELING 23 REPAIR / REPLACEMENT
SUMMARY
REPORT FOR FORM NIS-2 l
l I
Written by:QL q dimg Date: n.m Aq Reviewed by: [,t., f/w[b Date: /-/0-ff Approved by
) ate: //
/
i PAGE 1 of 6 1_
e Wisconsin Electric INrwer Co.
231 West Michigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Conunercial Service Date 10/01/72 Acronyms ASME American Society.of Mechanical Engineers CR Condition Report MR Modification Request MT
-Magnetic Particle Examination NDE Nondestructive Examination
~NRC Nuclear Regulatory Commission PBNP-Point Beach Nuclear Plant PT Dye Penetrant Examination RT Radiographic Examination RRM Repair / Replacement / Modification UT Ultrasonic Examination VT Visual Examination WE Wisconsin Electric Power Company WO Maintenance Work Order l
1 i
PAGE 2 of 6
)
f-
m Wisconsin Electric Power Co.
j.
231 West Michigen Avece Milwaukee, WI 53201 Point Beach Nuclear Plant. Unit 2 6610 Nuclear Road l
Two Rivers, WI 54241 DocLet 50-301 Commercial Service Date 10/01/72 l
Table of Contents
1.0 INTRODUCTION
2,0 CODE CASES ANDINTERPRETATIONS J
l 3.0 ABSTRACT OF REPAIR / REPLACEMENT l
l i
i 1
)
i PAGE 3 of 6 l
\\
t
G Wisconsin Electric Power Co.
231 West Michigan Avenue
[
Milwaukee. WI 53201 i
Point Beach Nuclear Plant, Unit 2 -
6610 Nuclear Road Two Rivers, WI 54241 Docket 50-301 Commercial service Date 10/01/72 UNIT 2 REFUELING 23
]
l REPAIR / REPLACEMENT
SUMMARY
l i
1.0 INTRODUCTION
l From September 13,1997 to March'14,1999, repairs and replacements were performed on items at PBNP
' Unit 2. These repairs and replacements were completed in the second examination of the second period, l
of the third 10-year interval at PBNP Unit 2. The time interval for this examination period included the Unit 2 Refueling 23 outage (U2R23) that ran from December 6,1998 to March 4,1999.
)
2.0 CODE CASES AND INTERPRETATIONS This report utilized the following Code Cases and Interpretations:
l l
2.1 ASME Code Interpretation, Section VIII-1-83-17, which allows for computer generated data report j-forms to be used in place of Code forms as long as size, arrangement, and content are identical, l
I l
2.2 Relief request PTP-3-06 which allows the use of Code Case N-416-1.
3.0 ABSTRACT OF REPAIR / REPLACEMENT Repairs / replacements performed on ASME Class 1,2, MC and CC items are documented on the attached l
NIS-2 forms. Repairs / replacements on ASME Class 3 items are documented on NIS-2 forms and l
maintained on file at PBNP. They are summarized here, but are not included in this report in accordance with ASME Section XI,IWA-6210(c).
l RRM 97-0017 and 97-0073, WO 9701772 and 9712288 i
COMPONENT: MS-00244, HX-001B Steam Generator MS-02015 Dump to Atmosphere Inlet Valve CLASS: 2 DESCRIPTION: Replace body to bonnet studs and nuts and repair body bonnet joint.
RRM 97-0080,97-0081, and 97-0083, WO 9714948 and 9714949 COMPONENT: PS EB-08-2H19, PS EB-08-2H22, PS EB-08, Main Steam Piping Supports CLASS: 2 l
l-DESCRIPTION: Modify pipe supports and repair pipe.
RRM 97-0085 and 97-0092, WO 9711923 COMPONENT: MS-02082, P-029 Auxiliary Feed Pump Overspeed Trip Valve CLASS: 2 DESCRIPTION: Replace valve and flange bolting.
PAGE 4 of 6 j
Wiscocin Dectric Power Co.
231 West Michigan Avenue Milwaukee.WI 53201 Point Deach Nuclear Plant. Unit 2 6610 Nuclear Road Two Rivers. WI $4241 -
Docket 50-301 Comnwrcial service Date 10/01/72 RRM 98-0004,98-0005,98-0006,98-0007 and 98-0008, WO 9800662,9800663,9800664 and 9800665 COMPONENT:l Piping 11B-19, Service Water CLASS: 3 DESCRIPTION: Replace inlet and outlet piping to fan motor cooling of HX-015A, replace 2" piping to
. HX-0158, liX-015C and HX-015D.
RRM 98-0017,98-0018,98-0070,98-00W,98-0111,98-0112,99-0014, WO 9800321,9802194, 9802275,9805686,9806925,9806983 COMPONENT: C-1, C-2, C-1-SI, C-1-S6, Access Air Locks, Bulkhead Shaft Door Latches l
l CLASS: MC
. DESCRIPTION: Fabricate and install bushings, bulkhead shafts and door latch shafts. Replace seals and rebuild vent valves.
RRM 98-0020, WO 9710823 COMPONENT: P-002A, Charging Pump CLASS: 2 DESCRIPTION: Replace No. I cage and all valve discs.
RRM 98-0089,98-0109,99-0016 and 99-0021, WO 9812290,9812291,9901182 and 9901475 COMPONENT: Various Piping Supports, Residual Heat Removal CLASS: 2 DESCRIPTION: Modify, remove, install piping supports.
RRM 98-0091 and 98-0099, WO 9812290 and 9812291 COMPONENT: Various Piping Supports, Safety Injection CLASS: 2.
DESCRIPTION: Install, remove, modify piping supports.
RRM 98-0103, WO 9816555 COMPONENT: Boric Acid Tank Pump Spare CLASS: 2 '
DESCRIPTION: Remove flow orifice and tack welds.
RRM 98-0120, WO 9818022 COMPONENT: T-070C, Charging Pump Discharge Accumulator CLASS: 2 DESCRIPTION: Replace charging pump discharge pulsation dampener retaining ring.
PAGE 5 of 6 t'
Wisconsin Electric Power Co.
231 West Mhhigan Avenue Milwaukee, WI 53201 Point Beach Nuclear Plant, Unit 2 6610 Nuclear Road Two Rivers, WI $4241 Docket 50-301 Commercial Service Date 10/Oln2 RRM 98-0128, WO 9818131 COMPONENT: FE-02902, Service Water Heat Exchanger Flow Element CLASS: 3 DESCRIPTION: Replace flange studs and nuts.
RRM 99-0003, WO 9809600 COMPONENT: HS-24, Safety Injection Line Snubber CLASS: 1 DESCRIPTION: Replace like-for-like tailpiece on snubber.
RRM 99-0005, WO 9820054 COMPONENT: PS EB-09-FW-2H2, Feedwater Piping dupport CLASS: 2 DESCRIPTION: Replace like-for-like rod andjam nuts ofpipe support.
PAGE 6 of 6
w e
Sheet 2
of 2
1 Form NIS-2 Continued 9.
Remarks RRM 99-0005 f.pplicable 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 repiacement l
Type Code Symbol Stamp N/A 4
i i
Certificate of Authorization No.
Docket 50-301 Expiration Date N/A 0
"L5T f.4AA h Signed /m
,ISI Coordinator Date hh
,19 k VOdnd or Owner's Designee Title
~
V CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin' and employed by HSBII, Co. of Hartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective
)
i measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions 10731, Wi 100057, l.N.A.
[
Inspector's 6ignature National Board, State, Province, and Endorsements
/k g{
g9 g Date r
. FORM NIS-2 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 March 10,1999 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet 1
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI 54241-WO 9820054 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Powei Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Feedwater 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case AISC Sixth Edition, MSS-SP 581967, Bechtel Specification M-78 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, No AddenA 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)
PS EB-09-FW 2112 N/A N/A N/A
. FW-2112 N/A Replacement No I
i 7.
Description of Work:
Replace like-for-like rod and jam nuts of pipe support.
8, Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.
'F
= VT-3 NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8H in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
l L
}
r h
Sheet 2
of 2
Form NIS-2 Continued 9
Remarks RRM 99-0003 Applicable Manufacturer's Data Reports to be anached.
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 444/h
,19 Signed MN70 A
, ISI Coordinator Date owner or owner's Designee. Title f
'~
'r CERTIFICATE OF INSERVICE INSPECTION i
1 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel j
Inspectors and the State of Province of Wisconsin and employed by HSBil, Co. of Hartford, CT have inspected f
the components described in this Owner's Report during the period September 13,1997 to March 14,1999,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 h'is employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
A /sA Cemmissiens i 0,31, Wi.iOO0s,.
i.s.A.
[ Insp4ctor's Signature National Board, State, Province, and Endorsements jkAy Z7 19 ff Date l
FORM NIS-2 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 February 24,1999 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet,1 of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road. Two Rivers, WI $4241 -
Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Safety injection 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case Bechtel Specification 6118-C-27 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
IIS-24 Grinnell 3370 N/A N/A N/A Replacement No Company, Inc.
7.
Description of Work: Replace like-for-like tailpiece on snubber.
8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure O Other Pressure psi Test Temp.
- F RMP 61 and VT-3 NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is SM in. x 11 in.,(2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
F Sheet 2
of 2
Form NIS-2 Continued L
9, Remarks RRM 98-0120, CR 99-1441 L
/
Apphcabic Manufacturer's Data Reports to be attached.
l l
l
. CERTIFIC. ATE OF COMPLIANCE 1
l 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 replacem.nr l
l.
Type Code Symbol Stamp N/A 1
i l
Certificate of Authorization No.
Docket 50-301 Expiration Date N/A
/
Signed M
, ISI Coordinator ' Date
_,19 Owner /r O/nerT LA,signec, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSBII, Co. of liartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999,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.
l l
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neiaer the Inspector nor his employer shall be liable in any manner for any personal injury or propeity damage or a loss of any kind arising from or connected with this inspection.
]
Commissions 10731, W1 100057, l.N.A.
[
h6pectoFf Signature National Board, State, Province, and Endorsements 7
19 %
Date c
1 L
3.
t 5
FORM NIS-2 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' November 20,1998 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet I
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI 54241 WO 9818022 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wiscensin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Chemical Volume Control 5.
(a) Applicable Construction Code B31.1 19 73 Edition, None Addenda, N/A Code Case ASME Section ill Class 21974, Specification PB 56 and PB-66 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
T.070C Greer Ilydraulics, N/A N/A N/A N/A Replacenient No inc.
7.
Description of Work:
Replace charging pump discharge pulsation dampener retaining ring.
8.
Tests Conducted: liydrestatic O Pneumatic Nominal Operating Pressure Other Pressure 1990 psi Test Temp.
I13
- F I
NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8h in. x 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
I
]
Sheet 2
of 2
Form NIS-2 Continued 9.
Remarks RRM 98-0103 Applicable Manufacturer's Data Reports to be attached.
T 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.
repairorrepin ment Type Code Symbol Stamp N/A Certificate of Authorization No.
Docket 50-301 Exp.iration Date N/A b
,ISICoordinatar Date A / 7, 19 99 Signed
+1, ow per'or 0%ner's Designec, Title
/' {
i
)
CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel inspectors and the State of Province of Wisconsin and employed by HSBil, Co. of Hartford, CT have inspected the components described in this Owner's Repott during the period September 13,1997 to March 14,1999. 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 AS.ME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for aity personal injury or property damage or a loss of any kind arising from or connected with this inspection, j
[
Commissions 10731, Wi-100057, l.N.A.
[ Insp6ctor's Signature National Board, State, Province, and Endorsements k 25 19 ff Date S
r m
FORM NIS-2 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 January 4,1999 j
Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet I
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name i
6610 Nuclear Road, Two Rivers, WI 54241 WO 9816555 1
Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Chemical Volume Control System 5.
(a) Apphcable Construction Code B16.5 19 68 Edition, None Addenda, N/A Code Case Westinghouse Spec G-676372 Revision 0,1966 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
" BAT" Pump Spare Crane Company 9834475 2 N/A N/A N/A Repair No 7.
Description of Work: Remove flow orifice and tack welds.
8.
Tests Conducted: Ilydrostatic Pneumatic 0 Nominal Operating Pressure O Other Pressure psi Test Temp.
'F PT NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8h in. x 11 in.,(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
7 l
Sh et 2
of 2
Form NIS-2 Continued L
,7.
Description of Work:, Install, remove, modify piping supports.
. 8c Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure O Other Pressure psi Test Temp.
'F Visual-AWS DI.1,1988 NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8M in. x 11 in., (2) infonnation in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
l
- 9. ' Remarks ' RRM 98-0091,98-0099, CR 99-1441 Applicable Manufacturer's Data Reports to be attached.
l l
l CERTIFICATE OF COMPLIANCE We certify thht 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
,ISICoordinator Date
, 19 N Owner 6r Owner's Designee, Title f
CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSBil, Co. of Hartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor h;s employer Aall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or conne-
' ls inspection.
i Commissions 10731, Wi-100057, l.N.A.
pg
~
Inspeitor's Si[;n'ature National Board, State, Province, and Endorsements Date j/gge..
i 19 7i w-i
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As R: quired by the Pr: visions cf the ASME Code Section XI 1.
Owner Wisconsin Electric Power Company Date September 23,1998 j
Name j
231 W. Michigan Ave., Milwaukee, WI 53201 Sheet 1
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI 54241 WO 9812290,9812291 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Safety injection 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case Westinghouse Spec G-676262, Bechtel Spec M80, AISC 6th Edition, MSS-SP58 - 1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, No Addenda 6.
Identification of Components Repaired or Replaced and Replacement Components
- 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 Nol PS SI 151R-1-S3 N/A N/A N/A PS JG-1.S12 N/A Replaced No PS SI 151R l S4 N/A N/A N/A PS JG-1-Sil N/A Replaced No PS SI 151R-1-S9 N/A N/A N/A N/A N/A Replaced No PS SI 151R 1 S10 N/A N/A N/A N/A N/A Replaced No PS SI 151R-1-Sil N/A N/A N/A N/A N/A Replaced No PS SI 151 R-I-S12 N/A N/A N/A N/A N/A Replaced No PS SI 151R-1 S20 N/A N/A N/A N/A N/A Replaced No PS SI 151R-I-S2l N/A N/A N/A N/A N/A Replaced No PS SI 151R-1-S22 N/A N/A N/A N/A N/A Replaced No PS SI 151R-1-S23 N/A N/A N/A N/A N/A Replaced No PS SI 151R 1-SND N/A N/A N/A N/A N/A Replaced No PS SI 151R 1-SNJ N/A N/A N/A N/A N/A Replaced No PS SI 151R-1 SNK N/A N/A N/A N/A N/A Replaced No PS SI 151R-1 SNT N/A N/A N/A N/A N/A Replaced No PS SI 150lR-4-S25 N/A N/A N/A N/A N/A Replaced No PS SI 150lR-4-S27A N/A N/A N/A N/A N/A Replaced No
F 1
l i
1 Sheet 2
of 2
Form NIS-2 Continued l
l 9.
Remarks. RRM 98-0089,98-0109,99-0016,99-0021, CR 99-1441 CR 99-1526 Applicable Manufacturer's Data Reports to be attached.
l l
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 repiacement Type Code Symbol Stamp N/A Certificate of Authorization No.
Docket 50-301 Expiration Date N/A Signed 1
,ISICoordinator Date
[-
k W
Ownerbt Owfier's Designec, Title
,19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of' oiler and Pressure Vessel B
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 September 13,1997 to March 14,1999, 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, I
concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the l
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 10731, Wl-100057, l.N.A.
Inspectsfr's Signsture National Board, State, Province, and Endorsements
(,v68 h 19 9 9 Date _
h yfg CMM i
l l
w
FORM NIS-2 OWNERcS REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI l.
Owner Wisconsin Electric Power Company Date September 23,1998 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet 1
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI 54241 WO 9812290,9812291,9901182,9901475 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Residual Heat Removal
- 5. - (a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case Westinghouse Spec G-676262, Bechtel Spec M78 and M80, AISC 6th Edition, MSS-SP58 - 1967 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986. No Addenda 6.
Identification of Components Repaired or Replaced and Replacement Components Repaired.
ASME National
- Replaced, Code Name of Component Name of :
Manufacturer Board Other Identification Year or Stamped Manufacturer Serial No.
No.
Built Emlacement (Yes or No) l Rll-00733A N/A N/A N/A Piping 2" AC 60lR-3 N/A Repaired No PS AC 60lR-2-S3 N/A N/A N/A PS JG-1-S12 N/A Repaired No PS AC 601R-2-S4 N/A' N/A N/A PS JG-1-Sii N/A Repaired No PS AC 60lR-2-S7 N/A N/A N/A PS SI 151R-1-S8 N/A Replaced No PS AC 60lR-2-S8 N/A-N/A N/A N/A N/A Replaced No PS AC 60lR 2-S10 N/A N/A N/A N/A N/A Replaced No PS AC 601R-2-Sii N/A N/A
' N/A N/A N/A Replaced No PS AC 60lR-2-S12 N/A N/A N/A N/A N/A Replaced No PS AC 60lR-2-S13 N/A N/A N/A N/A N/A Replaced No PS AC 60!R 2-S14 N/A N/A N/A N/A N/A Replaced No PS AC 60lR-2-S18 N/A N/A N/A N/A N/A Replaced No i
PS AC 60lR-2-S21 N/A N/A N/A N/A N/A Repaired No q
PS AC 60lR-2-SNE N/A N/A N/A PS SI 151R-1 SND N/A Repaired
- No PS AC 60lR-2-2113 N/A N/A N/A 211-03A N/A -
Repaired No 7.
Description of Work:
M'odify, remove, install piping supports.
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure O Other Pressure psi Test Temp.
'F Visual-AWS DI.1, VT-3 NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is SM in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
I
y L
1 Sheet 2
of 2
Form NIS-2 Continued 9.
Remarks RRM 98-0020, CR 991441 Applicable Manufacturer's Data Reports to be attached.
l l
l l
CERTIFICATE OF COMPLIANCE l
We cenify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI.
repair er repiument Type Code Symbol Stamp N/A Certificate of Authorization No.
Docket 50-301 Expiration Date N/A Signed 9
,ISI Coordinator Date
[~2
,19 h Ownerhr Owne:YDesignec. Title CERTIFICATE OF INSERVICE INSPECTION l
1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel I
Inspectors and the State of Province of Wisconsin and employed by llSBII, Co. of Ilartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999, 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.
l l
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, I
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.
j Commissions 10731, Wi 100057, l.N.A.
/
Ins 1(ector's Signature National Board, State, Province, and Endorsements Date ng ?
19 W 1
L
FORM NIS-2 OWNEP.'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
,o 1.
Owner Wisconsin Electric Power Company Date February 27,1998 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet 1
of 2
~
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI $4241 WO 9710823 Address -
Repair Organization P.O. No., Job No. Etc.
3.
. Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A
~
Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Chemical and Volume Control 5.
(a) Applicable Construction Code N/A 19_ Edition, N/A Addenda N/A Code Case Westiaghouse Spec G676370 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
P 002A Ajax tron Works 6456 N/A N/A N/A Replacement No 7.
Description of Work:
Replace No. I cage and all valve discs.
8.
Tests Conducted: liydrostatic 0 Pneumatic O Nominal Operating Pressure @
Other O
Pressure psi Test Temp.
- F IT 22 NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8M in. x 11 in., (2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
p r-Sheet 2
of 2
Form NIS-2 Continued 9, ' Remarks. RRM 98-0017,98-0018,98-0070,98-0098,98-0111,98-0112,99-0014, CR 99-1441 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, Sectieri XI.
rermir or replacement Type Code Symbol Stamp N/A
?
l 1
Certificate of Authorization No.
Docket 50-301 Expiration Date N/A s
[-M
, 19 ff Signed
, ISI Coordinator Date Owner 6r OwnerTDesignee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSBil, Co. of Hartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Commissions 10731, WI-100057, I.N.A.
[ Inspo6 tor's Signature National Board, State, Province, and Endorsements 7
19 ff Date a g.
[
FORM NIS-2 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 February 26,1998 Name 231 W. Michigan Ave., Milwaukee, WI 53201 Sheet 1
.of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
j Name
{
WO 9800321,9802194,9802275,9805686, l
6610 Nuclear Road. Two Rivers, WI $4241 9806925,9806983 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road. Two Rivers, WI 54241 Expiratien Date N/A I
Address 4.
Identification of System: Containment S.
(a) Applicable Construction Code ASME Sect. Ill 19 65 Edition, None Addenda, N/A Code Case j
Bechtel Spec C-8 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, No Addenda 1
)
6.
Identification of Components Repaired or Replaced and Replacement Components
]
I
- 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-1 Pittsburgh Des None N/A N/A N/A Repaired No Moines Steel C-2 Pittsburgh Des None N/A N/A N/A Repaired No Moines Steel -
C-1 SI None None N/A N/A N/A Replacement No C-1-S6 None None N/A N/A N/A Replacement No 7.
Description of Work:
Fabricate and install bushings, bulkhead shafts and door latch shafts. Replace seals and rebuild vent valves.
8.
Tests Conducted: liydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.
'F TS-10 NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8h in. x 11 in.,(2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
m--
g s.
Sheet 2
of 2
Form NIS-2 Continued
' 9.
Remarks RRM 97-0085,97-0092 Applicable Manufacturer's Data Reports to be attached.
i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of l
the ASME Code,Section XI.
repair or replacement Type' Code Symbol Stamp N/A l
Certificate of Authorization No.
Docket 50-301 Expiration Date N/A P.
Signed dh I
,ISICoordinator Date M
/7
, 19 99 Owner or Owner's Designee, Title l
l CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel.
Inspectors and the State of Province of Wisconsin and employed by HSBII, Co. of Hartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective l
measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
I By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, I
concerning the examinations and corrective n asures 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 10731, WI-100057, I.N.A.
[ Insp/ctor's Signature National Board, State, Province, and Endorsements Da'te w
19 r
y
4
)
FORM NIS-2 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 July 6,1998
)
Name 231 W. Michigan Ave. Milwaukee,WI 53201 Sheet 1
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road. Two Rivers, WI $4241 WO 9711923 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Perfonned By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road. Two Rivers, WI 54241 Expiration Date N/A Address 4.
Identification of System: Main, Extraction, Gland Seal and Reheat Steam 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case Bechtel Spec M-78, Pipe Class EB-8 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
MS-02082 Gimpel Machine 68-10371-2 N/A N/A N/A Replaced No Works, Co."
t 7.
Description of Work: Replace valve and flange bolting.
8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Test Temp.
F Inservice Leak Test j.
NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8M in. x 11 in.,(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet 1
s is numbered and the number of sheets is recorded at the top of this form.
' f..
4
.i
+,
i
. M
(
.I~
Sheet 2
of 2
Form NIS-2 Continued 9.
Remarks RRM 97-0080,97-0081,97-0083 and Code Case N 416, CR 99-1441 Applicable Manufacturcr's Data Reports to be attached.
l l
l CERTIFICATE OF COMPLIANCE l
We certify that the statements made in the report are correct and this repair confbrms to the rules of I
the ASME Code,Section XI, repair or repl=e=nt Type Code Symbol Stamp N/A l
Certificate of Authorization No. Docket 50-301 Expiration Date N/A J
Signed; M A
,ISI Coordinator Date
[-
, 19 ff "Owny or Owner's Designec, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSBil, Co. of Hartford, CT have inspected the components described in this Owner's Repon during the period September 13,1997 to March 14,1999, and i
state that to the best of any 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.
l By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
[
Commissions 10731, Wl 100057, l.N.A.
l Inspettor's Signature National Board, State, Province, and Endorsements j
19 ff _
Date :
f}e e
FORM NIS-2 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 March 27,1998 Name 231 W. Michigan Ave., Milwaukee, WI $3201 Sheet 1
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road, Two Rivers, WI $4241 WO 9714948,9714949 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address l
4.
Identification of System: Main, Extraction, Gland and Reheat Steam 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case (b) Applicable Edition of Section Xi Utilized for Repairs or Replacements 1986, No Addenda 6.
Identification of Components Repaired or Replcced and Replacement Components i
- Repaired, ASME National Replaced.
Code Name of Name of Manufacturer Board Other Year or Stamped Component Manufacturer Serial No.
No.
Identification lluilt Replacement (Yes or No)
PS EB-08-21119 None N/A N/A None N/A Replaced No PS EB-08-2il22 None N/A N/A None N/A Replaced No PS EB-08 None N/A N/A None N/A Repaired No 7.
Description of Work: Modify pipe supports and repair pipe.
8.
Tests Conducted: liydrostatic Pneumatic Nominal Operating Pressure Other Pressure 935 psi Test Temp.
536
F NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8H in. x 11 in.,(2) information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
1 l
Sheet 2
of 2
Form NIS-2 Continued 9.
Remarks RRM 97-0017,97-0073, CR 99-1441 Apphcable Manufacturer's Data Reports to be attached.
)
i 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 Erpiration Date N/A Signed N
, ISI Coordinator Date
,19 f
/
Owner or Oper's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of Wisconsin and employed by HSBII, Co. of flartford, CT have inspected the components described in this Owner's Report during the period September 13,1997 to March 14,1999, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of ASME Code,Section XI.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthennore, 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 10731, Wi-100057, l.N.A.
Inspftor's Signature National Board, State, Province, and Endorsements
[7 Date 19
E
' FORM NIS-2 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 February 25,1998
.Name 231 W. Michigan Ave., Milwaukee, W1.53201 Sheet I
of 2
Address 2.
Plant Point Beach Nuclear Plant Unit 2
Name 6610 Nuclear Road Two Rivers, WI 54241 WO 9701772,9712288 Address Repair Organization P.O. No., Job No. Etc.
3.
Work Performed By:
Wisconsin Electric Power Co.
. Type Code Symbol Stamp N/A Name Authorization No.
N/A 6610 Nuclear Road, Two Rivers, WI 54241 Expiration Date N/A Address
- 4.
Identification of System: Main, Extraction, Gland and Reheat Steam
- 5.
(a) Applicable Construction Code B31.1 19 67 Edition, None Addenda, N/A Code Case Becthel Spec 6118-M-81, ASA 16.5 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1986, 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)
MS-00244 William Powell 35738 N/A N/A N/A Repaired No 7.
Description of Work: Repbce body to bonnet studs and nuts and repair body bonnet joint.
8.
Tests Conducted: 11ydrostatic Pneumatic Nominal Operating Pressure Other
(@
Pressure 800 psi Test Temp.
520
'F VT2
. NOTE: Supplemental sheets in form oflists, sketches, or drawings may be used, provided (1) size is 8M in. x 11 in.,(2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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