ML19323A344
| ML19323A344 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/01/1980 |
| From: | Dahlman L, Hausen D, Krumpos P NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19323A338 | List: |
| References | |
| NUDOCS 8004180307 | |
| Download: ML19323A344 (150) | |
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- PRAIRIEISLAND NUCLEAR
, GENERATING PLANT m
pq Red Wing, Minnesota. ~
UNITS 1 AND 2 ~~
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i INSERVICE . INSPECTION-EXAMINATION ' SUmfARY - :
- PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT'2- -
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- JANUARY;2'.TO FEBRUARY 4, 1980.
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,t j;,t1 REFUELING OUTAGE-NO.14 7
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. INSPECTION PERIOD'2 -
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' l NORTHERN STATES POWER COMPANYL CommaCIAL SERVI
- April 1,.1980 MINNEAPOLIS. MINNESOTA - '
DATE: - DECi 21,?1974. t s
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NORTHERN STATES POWER COMPANY !
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 ;
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INSERVICE INSPECTION-EXAMINATION SUM 4ARY PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 l January 2 to February 4, 1980 REFUELING OUTAGE NO, 4 l l
INSPECTION PERIOD 2 Prepared by: D B Hansen, Assistant M&SP Engineer L C Dahlman M&SP Specialist April 1,198 ) "
. Reviewed by: N <
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Consnercial Service Date: December 21, 1974 PJKf%mpbs' Superintendent
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Materials
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. and Special Processes Approved by: A $/
Ra d A'nderson General Superintendent Production Plant Maintenance 7...
INSERVICE INSPECTION - EXAMINATION
SUMMARY
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2
- INDEX -
3 1.0 Introduction 2.0 ASME Class 1 Components and Flywheels 2.1 Examination Plan 2.2 Examination Methods 2.3 Examination Procedures 2.4 Equipment and Materials 2.5 Personnel 2.6 Evaluation 2.7 Examination Reports and Documentation 2.8 Summary of Results 3.0 Examination of the Reactor Vessel Internals 4.0 IE Bulletin No. 79-13 Examinations-Feedwater Piping 5.0 Examination of the Steam Generator Tubes Appendix A - ASME Class 1 Examination Inservice Inspection - Examination Summary Tables:
Table S1.1 - Reactor Vessels Table S1.2 - Pressurizer Table S1.3.1 - Steam Generators Table St.3.2 - Regenerative Heat Exchanger Table S1.3.3 - Excess Letdown lleat Exchanger Table S1.4 - Piping Pressure Boundary Table S1.5 - Reactor Coolant Pumps Table S1.6 - Valve Pressure Boundary
. Table II -
Baseline Comparison Summary y Table III -
Isometric Summary Appendix B - ASME Class 2 Examinations Inservice Inspection - Examination Summary Tables:
Table S2.2.1 - Piping-Circumferential Butt Welds Table S2.2.5 - Piping-Integrally Welded Supports Table S2.2.6 - Piping-Nonwelded Supports Table II -
Baseline Comparison Summary Table III - Isometric Summary Appendix C - FSAR Augmented Examination
- No Examinations scheduled this outage Page 1 of 2 k
Appendix D - Seismic Bolting Examination i Inservice Inspection - Examination Summary Table:
Table SB - Seismic Bolting Table II - Baseline Comparison Summary Table III - Isometric Summary i
Appendix E Table I - Personnel Listing Table II -
Ultrasonic Calibration Blocks
, Table III - Procedure Listing Table IV -
Equipment and Materials
. Appendix F - Steam Generator No. 21 Eddy Current Results and Tube Sheet Maps Appendix G - Steam Generator No. 22 Eddy Current Results and Tube Sheet Maps .
Appendix 11 Form NIS-1, Owners' Data Report for Inservice Inspections i e'
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INSERVICE INSPECTION - EXAMINATION
SUMMARY
PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 January 2 to February 4,1980
1.0 INTRODUCTION
This report is a summary of the examinations performed during the fourth scheduled inservice inspection at the Prairie Island Nuclear Generating Plant - Unit 2. This was the second inservice inspection conducted during inspection period two. The examinations were performed during the plant's 3 fourth refueling outage from January 2 to February 4, 1980. Prairie Island-Unit 2 began commercial operation on December 21, 1974.
This report identifies the components examined, the examination methods used, the examination report number; and, summarizes the examination results for each of the following areas:
- 1. Pressure retaining components, supports, and bolting of raismic supports classified as ASME Class 1, and reactor coolant pump flywheels.
- 2. Reactor pressure vessel interior surfaces and internal components.
- 3. Feedwater piping circumferential butt welds and piping base metal as required by IE Bulletin No. 79-13.
- 4. Eddy current examination of steam generator tubing.
2.0 ASME CLASS 1 COMPONENTS AND FLYk"dEELS 2.1 Examination Plan The examination plan focused on the pressure-retaining components and their supports of the reactor coolant and associated auxiliary systems classified as ASME Class 1. In addition, examinations were performed on seismic bolting of supports for ASME Class 1 components, as required by DRO Bulletin No. 74-03, and on the reactor coolant pump flywheels as required by Prairie Island's Technical Specification, Table 4.2.1.
The examination plan was based on the examination requirements of the ASME Boiler and Pressure Vessel Code Section XI,1974 Edition through and incr: ding the Summer 1975 Addenda, and complied with Prairie Is-J land's Technical Specification, Section TS4.2. The examination is in accordance with the program submitted to the United States Nuclear Reg-ulatory Commission on February 1, 1978 entitled, "ASME Code Section XI
- Inservice Inspection and Testing Program and Information Required for NRC Review of Requests for Relief from ASME Code Section XI Require-ments."
2.2 Examination Methods Ultrasonic examination methods and techniques stre used to perform the volumetric examinations. The ultrasonic test systems consisted of an ultrasonic digital analog tester and a two channel strip chart recorder.
One channel of the recorder was calibrated to reflect ultrasonic screen Page 1 of 8
height (amplitude) and the wcond channel was calibrated to indi-cat e met al path (ranne) to t he reflector. This approach to the examination gives a permanent record to the extent possible.
Liquid penetrant or magnetic particle examination methods were used to perform the surface examinations. The liquid penetrant examina-tions were performed using color contrast-solvent removable materials.
Magnetic particle examinations were performed using a yoke and dry powder.
All visual examinations were aided when necessary with artificial lighting and verified for adequacy with an 18% neutral grey card with a 1/32 inch black line.
2.3 Examination Procedures The ultrasonic examination procedure for pipe welds complied with the requirements of Appendix III of ASME Section XI that was issued in the Winter 1975 Addenda. All the other examination procedures complied with the requirements of the 1974 Edition through and in-cluding the summer 1975 Addenda of ASME Section XI. A listing of the procedures used for the examinations is shown in Table III of Appendix E.
2.4 Equipment and Materials All equipment and expendable materials used in the examinations are listed by either serial number or type along with their res-pective calibration date or batch number in . Table IV of Appendix E.
'The ultrasonic calibration standards used in the examination are listed in Table 11 of Appendix E. These standards are owned and maintained by NSP at the plant site.
2.5 Personnel Northern States Power Company contracted Lambert, MacGill, Thomas, Inc. to perform the examinations. Hertford Steam Boiler Inspection and Insurance Company, representing ANI, provided the Authorized Inspection.
All personnel involved in the performance or evaluation of exam-inations are listed along with their title, organization, and ASNT Level of certification in Table I of Appendix E. Certifications for examination personnel are maintained on file by Northern States
- Power Company.
. 2.6 Evaluation Any indications disclosed in the examinations were evaluated by the examiner at that time, in accordance with the rules of the procedure and ASME Section XI.
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! The ultrasonic examiner was aided in his evaluation by a calibra-l tion performed on a standard calibration block before each day's examination, checked before and after each individual examination and at intervals not exceeding four (4) hours. In addition, the ultrasonic data was recorded on strip charts which were made a p&rt of the inspection report, and permitted further evaluation.
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2.7 Examination Reports and Documentation All examination reports and documentation are maintained on file by Northern States Power Company. Table I of Appendixes A and D identifies the examination report number (s) for each item examined.
Many of the items identify more than one examination report be- ,
cause of the different types of examinations performed on the item.
Table I of Appendix A and D summarized all the examinations that have been performed to date and identifies the amount that will be examined in the future to complete the ten year examination 5 requirements. For retrieval purposes, the prefix of the inspection report number corresponds with the year that the inspection was performed. The examination report numbers for this outage are
- prefixed with "80 ".
Table II of Appendix A and D compares the baseline examination results with the results obtained during this examination. Table III of Appendix A and D identifies the isometric drawings that were used for the examinations. The personnel, ultrasonic calibration blocks, procedures, equipment and materials that were used for the inspection are identified in the tables of Appendix E. Appendix H contains the Form NIS-1, entitled " Owners' Data Report for Inservice Inspections".
2.8 Summary of Results There were no signs of degradation to systems scheduled for exam-ination. The only anomalies detected were: one nut not flush in RTD Cold Leg A Hanger "B1" (line 2-2RC-7A); two loose nuts in RTD Hot Leg B Hanger "Al" (Line 2-2RC-7B); three nuts not flush on Reactor Coolant Pump 22 Through Anchor Bolts, one linear PT indi-cation on Pressurizer Spray Weld 22B (Line 3-2RC-5); and five linear and severtl rounded PT indications on Pressurizer Safety Line A Welds 1 and 1A S.E. (Line 6-2RC-20A) .
All indications, with the exception of the rounded PT indications on Pressurizer Safety Line A, were corrected. The nuts on Hangers "B1" and "Al" and the Through Anchor Bolts were all tightened.
The one linear PT indication on Weld 22B and the five linear PT indications on Welds 1 and 1A S.E. were all buffed off the surface.
All these indications were corrected and re-examined with the same method that detected them with no further indications.
The several rounded indications on Pressurizer Safety line A vere determined by etching the surface, to be located in the nozzle
." casting within " from the inconnel weld. The area was radio-graphed to aid in evaluation and possible repair. The radiographs were reviewed and the indications were determined to be gas poro-sity. The porosity was also determined acceptab1<s to Class 1 ASTM E446 Reference Radiographs for Category A gas porosity. Westing-house was contacted to aid in evaluation. They tecommended that' the porosity indications be accepted as is, based on the PT exam-ination results, radiographs, visual examination with 10% magnifi-cation, and ASME Section XI acceptance criteria.
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3.0 EXAMINATION OF THE REACTOR VESSEL INTERNALS Westinghouse was contracted to perform a visual examination of the reactor vessel internals. The examinations were performed with under-water television cameras and a video tape recording system.
Examinations were performed on representative regions of those interior surf aces and internals made accessible by the removal of components during normal refueling operation, as required by Item 1.15, Category N of Table 4.2-1 of the Plant Technical Specification.
" The upper internals assembly support columns, guide tubes, thermo-couple conduits, alignment keyways and fuel assembly guide pins were all examined when the assembly was removed from the vessel and located I on the storage stand. Guide tubes and support columns selected for examination included those subject to the highest flow loads and those considered to be subject to an " average" hydraulic loading. Guide tubes at the core locations of the " slow" nnd " fastest" drive lines were also reviewed. This inspection was to observe any evidence of physical dis-tortion and integrity of the fastening and locking devices.
Examinations were made of representative conduit runs and RTD's to verify freedom from distortion and integrity of the fastening clamps. The upper core plate alignment keyvay and fuel assembly guide pins were examined for any indication of galling or distortion.
Representative areas of the lower internals were examined above the fuel assemblies and to the extent accessible. Examinations were per-formed on the head and vessel alignment pin mating surfaces and attach-ments, upper core plate guide key, flange to core barrel weld, core barrel flange flow nozzle welds and the core barrel mid-plane weld were reviewed to verify their integrity and freedom from corrosion or dis-tortion.
The reactor vessel cladding at the 67 and 247' irradiation specimen sccess plug locatione was scheduled for examination. Due to equip-ment malfunction, these examinations were rescheduled for the next scheduled refueling outage.
Copies of the examination procedure, personnel qualifications and examination results is maintained on file by Northern States Power Company.
- 4.0 IE BULLETIN NO. 79-13 EXAMINATIONS - FEEDWATER PIPING All examinations required by IE Bulletin No. 79-13, Revision 2, were l completed for Prairie Island Unit 2 during this refueling outage.
These examinations were performed on feedwater circumferential butt welds, supports and basemetal classified as ASME Class 2.
Radiographic examinations were performed on the feedwater pipe-to-nozzle welds and of adjacent pipe and nozzle areas. The radiographic examinations were performed using a double wall exposure, single wall viewing technique. An Iridium 192 source was used in conjunction with multiple loaded Kodak "M" film. In addition, the radiographic examinations were performed to the 2T penetrameter sensitivity level; I
Page 4 of 8
and, where geometry permitted, for a distance equal to two wall thickness on each side of the weld. The radiographic examination procedure and acceptance criteria complied with the requirements of ASME Section III, Subsection NC,1974 Edition through and in-cluding the Winter 1976 Addenda.
The above areas were also ultrasonically examined in accordance with Appendix III of ASME Section XI, 1974 Edition through the Summer 1976 Addenda. The ultrasonic examination was performed using a calibration block fabricated to resemble the pipe-to-nozzle weld geometry, includ-ing the cosnterbore-taper area. In addition, these areas were visually and magnetic particle examined in accordance with ASME Section XI,
! 1974 Edition through the Summer 1975 Addenda. The results of these examinations showed no evidence of cracking. The magnetic particle examinations did, however, reveal several material irregularities I on the outside of the pipe and nozrle. These indications were buffed out and re-examined with no further indications.
Radiographic examinations were also performed on those areas required by Bulletin Item 2.a. These examinations, of feedwater loop B, consisted of the piping base metal from the auxiliary feedwater connection to the pipe-to-nozzle weld. The remainder of this line is encapsulated with guard piping and could not be examined. The con-tainment penetration-to-pipe weld, the circumferential butt welds from the last support to the steam generator, and the piping base metal from the auxiliary feedwater connection to the pipe-to-nozzle weld were all examined on feedwater loop A. All these areas examined by radiography were also examined by visual, ultrasonic, and magnetic particle methods referenced above. The results of these examinations revealed no evidence of cracking or other unacceptable indications.
All main feedwater piping supports and restraints in containment were examined visually in accordance with ASME Section XI, 1974 Edition through Summer 1975 Addenda. All accessible support attachment welds to the main feedwater pipe were also magnetic particle examined. During these examinations, the following minor descrepancies were noted: one missing nut on Loop A Hanger "K"; two loose nuts on Loop A Hanger "A";
two loose nuts on Loop B Hanger "A", and, one nut not flush on Loop B Hanger "G".
All indications disclosed during the examinations were resolved prior to plant heat up. The missing nut was replaced and the loose and not flush nuts were all tightened. All these areas were re-examined with the same method that detected them with no further indications.
Northern States Power Company contracted Peabody Testing Services to perform the radiographic examinations and Lambert, MacGill, Thomas, l Inc. performed the remainder of the examinations. All personnel involved in the examinations are listed in Table I of Appendix E.
All examination reports and documentation is maintained on file by Northern States Power Company. The radiographs were filed with the Work Request Authorizations; Feedwater loop A with C6357-FW-Q and Feedwater Loop B with D006-FW-Q. Table I of Appendix B identifies the items examined and the corresponding report numbers that are prefixed with "80 ". Table 11 compares the baseline examination results with the results obtained during this examination and Table III identifies the isometric drawings used for the examination.
Page 5 of 8
5.0 EXAMINATION OF STEAM GENERATOR TUBES Eddy current examinations of steam generator No. 21 and 22 tubing was also performed during this outage. In addition to complying with Technical Specification requirements, the examination plan was focused on the peripheral tubes in the inlet side of both steam generators.
These examinations of the peripheral tubes were planned to determine if there were any signs of tube damage due to foreign objects.
Westinghouse, along with technical support from Zetec Corporation, was contracted to perform and evaluate the data from the eddy current examinations. These examinations were performed using Westinghouse's new multi-frequency eddy current testing system. This system provided increased analytical capability for determining tube integrity. The four frequencies and their mcdes that were used for each examination were 400 KHz,100 KHz and 10 KHz in the differential mode and 100 KHz in the absolute mode.
In addition, Westinghouse was contracted to perform a visual examina-tion, using mirrors and fiber optics, of both steam generators to detect the presence of foreign objects. "
During the completion of the eddy current inspection for the inlet side of S.G. No. 21, one tube (row I column 1) was detected as having a 66%
OD indication approximately 17 inches above the tube sheet. Due to the location of this tube and the indication, and with no other indications detected, foreign object damage was suspected. (This tube damage was later confirmed as being caused by the improper installation of the tube lane blocking device which is a plate assembly used to redirect flow across the tube sheet.) Thus, the examination plan for the outlet side of S.G. No. 21 was increased to include the entire periphery of the tube bundle.
The results of the tube inspection for the outlet side of S.G. No. 21 revealed signs of tube deterioration in six of the peripheral tubes.
These indicstions were located at either the first or second tube support. The inspection plan of the outlet side was expanded until it was sufficiently demonstrated that this tube deterioration was primarily confined to the tubes at the periphery of the tube bundle at the first and second tube supports.
A similar inspection was performed on S.C. No. 22 and resulted in similar findings. Table I identifies the percentage of tubes that
, were inspected and Table II provides a tabulation of the number of deteriorated tubes for each steam generator.
Page 6 of 8
TAllLE 1 Steam Generator Examination Tube i Munber Araou n t 'I Extent Percent age f 21 Inlet 119 Past 7th suppart 3.5%
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315 Around li-!!cnd 9.0%
l 63 Ti;;b t radius 1-Bend 1.9% !
21 Outlet 429 Past 3rd support 12.77. !
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266 Past 7th support 7.9% l 1
1 27 Ti;;h t radius ll-lle nd 1.07. '
1 22 Inlet 80 Past 1st support 2.0% !
105 Past 7th support 3.0% !
- I 318 Around li-!!end 9.0%
(
89 Tight raslius tr-Bend 2.67.
22 outlet 3 Past 1st support 0.01% [
928 Past 3rd support 27.0%
212 Past 7th support 6.07. L i
l TAllLE 11 i S.G. No. 21 NliMllER OF TliBES OF WALL TilINN1NG INLET GUTI.ET 250% 1 1 220%, 4 50^ 0 10
< 2 07. 0 29 S.G. No. 22 250% 0 4 ;
2 20% . <507 0 39
< 20% 0 53 j i
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. amu I The plugging criterion of the Technical Specification is 50% of tube wall l thinning. Additional conservatism was used and all tubes that had areas of wall thinning greater than 43% were plugged. In addition, as a preven- i tive measure, the tubes that are directly in line with the tube lane block-ing devices, which are the row 1 column 1 and the row I column 94 tubes, were plugged in both steam generators. (This measure was taken even though improvements in design were made to assure proper location and locking of these blocking devices.) Table III identifies all the tubes that were plugged during this outage.
TABLE III
, STEAM GENERATOR TUBE NUMB,ER PERCENTAGE OF NUMBER ROW COL. WALL TilINNING REMARKS S.C. No. 21 1 1 66%
1 94 --- Preventive 35 78 72%
S.C. No. 22 1 1
--- Preventive 1 94 --- Preventive 34 79 43% Pulled 34 18 48%
42 34 54%
43 37 47%
44 37 47%
45 37 51%
44 41 49%
46 48 48%
38 74 49%
34 76 56%
33 78 70%
35 78 46%
33 79 46%
Westinghouse was also contracted to pull one of the degraded tubes and per-form the necessary analysis to determine the mechanism for tube wall deter-
- ioration. The results of this analytical work substantiated the eddy current results. -
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APPENDIX A j i
EXAMINATIONS I I
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NORTHERN STATES POWER CO. TABLE R1 1 PRAIRIE ISLAND UNIT ~> PAGE 1 OF s INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: REACIOR VESSEL N 8 SUB INSP, R E Q'D. AMT. ITEM INSPECTION E- N DE R1 Tl N0 ITEM PER. AMT. EXAM IDE NTIF acATION REPORT NO.
GCRY ITEM TO BE EXAMINED Bl.1 B-A IOtCI'IUDINAL AND CIRCUM-EERENTIAL WEIDS IN ODRE REGION IONGI'IUDINAL WEIIS - - -
-tote-CIRCtMFERENfIAL WELDS 'IHREE 50% -
Bl.2 B-B IONGI'IUDINAL Ato CIRCUMFERENTIAL WEIDS IN SHEIL (OIEER 'IMAN
'IMOSE OF CATEIDRY B-A AND B-C) b MERIDINAL AND CIRCUMFERENTIAL SEAM 4EIDS IN BOfIOM HEAD AND CWSURE HEAD (OIRER 'IMAN 'IROSE AT CATEGORY B-C IONGITJDINAL WEIES - - -
-f10NE-MERIDICNAL WEIDS - - -
-NONE-CIRCIMFERENfIAL WEILS 'DIREE 5% -
hED 10. 2 5% -
hED to. 4 5% -
WELD 10. 5 B1.3 B-C VESSEL 'IO FLANGE AND HEAD 'IO FIAICE CIRCUMFERENTIAL wrnR VESSEL 'IO FIANGE CNE 33% 33% No . 1, S' IUD HOIE 77_W RW REIORT 12 'IO 22 & 29 'IO 35
. 'IWO 33% -
'IEREE 33% -
rosessv-aste el7e ronne seo.ese-sees PP9-A-1 ._ __ _ _
NORTHERN STATES POWER CO. TA~LE SI 1 PRAIRIE ISLAND UNIT 2 PAGE 2 OF 5 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: REACIOR VESSEi.,
SUB M "" 8 M INSP. R EQ'O. AMT. ITEM INSPECTION 8 EM E. DESCR4 Tl N EXAM GORY ITEM TO BE EXAMINED PER. AMT. IDENTIFICATION REPORT NO.
B1.3 B-C (00NP'D)
HEAD 'IO FIANGE GE 33% 33% No. 6, SIUD H02 77-4f RW RIGORP &
1 THRU 16 77-74,73,75
'Iwo 33fs -
'IHREE 33% -
Bl.4 B-D PRIMARY N0ZZM-40-VESSEL N m W AND !OZZLE INSIDE RADIUSED SECTIO 4S REACIOR CORE C00IAlff 10ZZIES OUTIEr IOZZIES OE 1 1 BCC-A-1 77-4_t RW REIORT
'INO 1 -
INLET IOZZIES 'IHREE 2 -
SAFETY I!UECTION OE 1 1 IOOP A 77-4_t RPV REEORT IOZZIES 'IHREE 1 -
B1.5 B-E VESSEL PENETRATIONS, INCIUDING CQfflOL 10D DRIVE ABO INSTRLDENTATIQ4 Pf2ETRATIO3S (DNTROL ROD PEIETRATIONS QE 3% *3 *EACH ITfM INSPECTED
'IWO 3% -
BY PLANT PERSOGEL THREE 4% -
DURING EADI RFACIOR VESSEL IEAKME TEST Fones t7.aave e/ve pones soo, ses.sses PP9-A-2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - . . _ _ ., . - . . - ._.
NORTHERN STATES POWER CO. TABLE S1.1 PRAIRIE ISLAND UNIT 2 PAGE 3 OF 5 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: REAC' LOR VESSEL EUS 8 E N DE RI Tl N INSP. R EQ'O. AMT. ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED B1.5 B-E (CONT'D)
INSTRUMENTATION PENETRATIONS ONE 3% *3 *EACH ITEM INSPEC11D
'INO 3% -
BY ETANP PERSO;NEL
'IHREE 3% -
DURING EAQI REACIOR VESSEL IEAIGGE 'IEST REAC'IOR VESSEL HEAD VENT *- 1 *1 1-2RC-36 '10 2-BC-8-5 D1.6 B-P N0ZZE 'IO SAFE END WEIDS REAC'IOR CCRE CODIRrr IOZZES CUTET IOZZES CNE 1 1 ICC-A-1 S.E. 77-W RW REIORP &
'IND 1 -
77-620,112 INLET IOZZIES 'IHREE 2 -
REACIOR VESSEL SAFETY INJECTION IOZZES
!OZZE A S.E. CNE 1 1 10. 1 77-W RW REIORP &
77-023,113 EZZ E B S.E. 'IEREE 1 -
Bl.8 B-G-1 CDOSURE SIUDS AND NL'fS GE 16 16 il 'IERU #16 77-W RW REIORP &
77-T06
- 1 'IERU #16 78-84,99 (MP CNLY)
'IWO 16 -
'IHREE 16 -
D1.9 B-G-1 LIGAMENTS BEIWEEN OE- 16 16 SIUD IDIE #i2 - 22 77_W RW REFORP
'IHREADED SIUD HOES & 29 to 35
'IND 16 -
'If5 TEE 16 -
ro. n.aus one .. no. .-i .
NORTHERN STATES POWER CO. TABLE S1.1 PRAIRIE ISLAND UNIT 2 PAGE 4 OF S INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: REACIOR VESSEL
^M N " 8 M SUB AMT.
ITEM hTE- DE I TI N INSP. R EQ'D.
AMT. EXAM BTEM INSPECTION GORY ITEM TO BE EXAMINED PER. IDENTIFICATION REPORT NO.
B1.10 B-G-1 CWSUPE WASHERS AND BUSHINGS WASHERS CNE 16 16 PAIRS,1 'IERU 16 77-W RW REEORT
'INO 16 -
h" TEE 16 -
BUSHINGS - - -
-NONE-Bl.11 B-G-2 PRESSURE RETAINING BOLTING ONE 3 9 AIL 9 BOLTS 774! RW REPORP
'IWO 3 -
'IHREE 3 -
B1.12 B-H INTEGRALLY WEWED VESSEL SUPPORTS 'IHREE 2 -
Bl.13 B-I-1 CLOSURE HEAD CLADDING OtE 2 2 HCP-1 & ICP-2 77-W RW REIORP
'INO 2 -
'IHREE 2 -
B1.14 B-I-1 VESSEL CLADDING CNE 2 2 NCP-1 & VCP-2 76-W INTERNMS RPI
'IWO 2 -
'IHREE 2 -
B1.15 B-N-1 VESSEL INTERIOR UPPER INTERNALS AND GE * *
- 76-W INTERNMS RPT ICWER INTERNAIS 'INO * *
- 80{INTERNMS RPf
'IHREE -
, REPRESENTATIVI; RBGICNS OF 'IBOSE INTERIOR SURFACES AND INTERNME MAIE ACCESSIBIE BY TIE g
RDOVAL OF CCMION-I!NTS DURING NORMAL REFtELING OPERATION ro sas tv-save e/re comes peo.ess-sees
NORTHERN STATES POWER CO. TACLE R1_1 PRAIRIE ISLAND UNIT 2 PAGE 9 OF 9 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: RFA N YW VPA W ,
SUB M TE. N DE I Tl N INSP. R EQ'D. AMT. ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED Bl.16 B-N-2 INTERIOR ATTACIDOTTS - - - Myr APPLICABIE AND OORE SUPIORP EUR PWR'S STRUCIURES Bl.17 B-N-3 REMNABLE CORE SUPPOl
W I D M t OIT T O - DT E E D 0 ET E B N Y D W OM R I A 0 MA A R O I NE - S L E L [ R ER Y C M T E D L W T C D R1 LI E R A I R U A R E TE P E" R N R2 X U T R L I L T SN MN U N E S S G E K E P NE AE S A E S B S S S M IP SP S M W N - E R D N f S N E S E E X E R O P A V V E P PTO I I I SNT EUC T E 2 EY 1 2 ADP R - - P TN S O G- H- I G-SAIN G B B B B B N _ N LSE RI C EEI HI V T RR RA E I BM UE ST 56.O. 22! 2 BBAB 7 8 2 B 9 2 B 0 1 2 B 1 1 2 B . W S I OR NPI N M NORT ~) STATES POWER CO. TABLE _Sl.3.1 PRAIRI ISLAND UNIT _._2 PAGE__ 1 OF 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: STEAM GENERIGORS SUS " "
A D SCRI I INSP. R E O*D AMT. ITEM IN SPE CTION "I GORY PER AMT. EXAM IDE N TIF ICATION R E POR T NO.
ITEM TO BE EXAMINED B3.1 B-B IDJGITUDItJAL AND CIRCUMFERENTIAL WELDS ON THE PRIMiaY SIDE-IDJGI'IUDINAL hTLDS - - -
-tOJE-(CW)
CIRCUMFERENTIAL WELDS FIOi NAMEPIATE:
STEAM GENERA'IOR 10. 21 OJE 1.9% 37% +8" 'IO +13 ' 8"76-111,101,118
'IVD 1.9% 8% +23 '8" 'IO +26 ' 8"78-108,110,120
'IEREE 1.8% -
STEAM GENERATOR 10. 22 OJE 1.9% 31% +2' TO +13'76-112,102,119 y 'n o 1.9% 17% +21'10" 'IO +28 '78-109,111,123 7 'IUREE 1.8% -
e B3.2 B-D lOZZLE TO HEAD WELDS - - -
-NONE-B3.3 B-F lOZZLE 'IO SAFE END hTLDS
~
STEAM GENERATOR NO. 21 11 0 1 -
THREE 1 SPEAM GENERATOR 10. 22 CNE 1 1 ROC-B-5 S.E. 76,136,139 THREE 1 -
B3.4 B-G-1 PRESSURE RLTAINING BOLTS - - -
-NONE-B3.5 AND STUDS (2 2 IN. DIA.)
AND B3.6 B3.7 B-H INTBGRALLY WELDED - - -
-NONE-VESSEL SUPPORTS ro o.is.-i...
PPi -A-8
NORTq y STATES POWER CO.
TABLE Sl.3.1 PRAIRk ISLAND UNIT 2 PAGE 2 OF 3
'lNSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: SPEN 4 GENERNIORS SUB 8 E DE IP INSP. R E O 'D. AMT. BTEM INSPECTION STEM GORY ITEM TO BE EXAMINED PER. AMT EXAM (DENTIFICATION REPORT NO.
B3.8 B-I-2 VESSEL CLADDING STEN 4 GENERNIOR NO. 21 INLEP SIDE ONE 36 SQ. 36 SQ. CP-1, BEIIM MANWAY 76-124 IN. IN. .
PATO1 OUTIRP SIDE ONE 36 SQ. 36 SQ. CP-2, BELOW MANWAY 76-124 IN. IN.
PAIGI STEAM GENERATOR NO. 22
,N INIEP SIDE ONE 36 SQ. 36 SQ. CP-3, BEIIM MANWAY 76-123 7 m. IN.
5 PA101 OUTLET SIDE ONE 36 SQ. 36 SQ. CP-4, BEIIM MANWAY 76-123 IN. IN.
PA101 B3.9 B-P EXEMPTED COMPONErffS - - -
-NOE-B3.10 -B-G-2 PRESSURE RETAINING BOLTING (< 2 IN. DIA.)
STEAM GENERNIOR 10. 21 MANWAY BOLTING INIEP MA!MAY ONE 5 6 BOLTS 1 TIEU 6 76-99
% 10 5 5 BOLTS 6 niFU 10 78-83 HIREE 6 -
l' Os.am 9 7 2 4 70 FORed 800. 359-9999
- . - - ~, ,
, , i .
NORTH STATES POWER CO.
PRAIRI .., LAND UNIT 2 TABLE SI 3 1 3
(.
op 'a PAGE INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: STEAM GEtERKIORS S8 EXAM COMPONENT OR SYSTEM CA TE. AND DESCRIPTION OF INSP R E Q'O' AMT ITEM INSPECTION LT M GORY ITEM TO DE EXAMINED PER~ AMT' EXAM ID E N T t F ICA T IOrd REPOR T NO.
B3.10 B-G-2 (CONr'D)
OUILET MAWAY OtE 5 6 BOLTS 1 THIU 6 76-99
'IVD 5 5 BOLTS 6 'IEIU 10 78-83 THREE 6 -
STEAM GENERNIOR 10. 22 MAtMAY BOLTING
-INLET SWMAY OtE 5 6 BOLTS 1 THIU 6 76-120
'E O 5 5 BOLTS 6 THIU 10 "/d-77 THREE 6 -
.y OUTLET MAtaMY ore 5 6 BOLTS 1 THIU 6 76-120
.~ 'n o 5 S DOLTS 6 THIU 10 78-77
'HIREE 6 -
. ro . .... . .
-PP9-A . . .- .
NOR ;N STATES POWER CO. TABLE Sl.3.2 (
PRAI ISLAND UNIT 2 PAGE 1 O F' 1 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: RII;ENERATIVE HEAT EXQWEER M CO 9 PONE ORS S M SUB INSP AMT.
R E O'O ITEM INSPECTtON ITEM PER. AMT. EXAM GORY ITEM TO BE EXAMINED ID E N TIF ICATION REPORT NO.
-B3.1 B-B IDNGITUDINAL AND CIRCUMFERENTIAL hTLDS ON THE PRIMARY SIDE IDNGITUDINAL hTLDS - - -
-TOE-CIRCUMFERENTIAL hTLDS EXQIANGER A ONE 1 1 NO.1, SIELL hTID 76-100 EXQlANGER B TVO 1 1 10. 2, SHELL hTID 78-74 EXQlANGER C THREE 1 -
. B3.2 B-D. tOZZLE 'IO LEAD WELD - - -
-TOE-B3.4 B-G-1 PRESSURE RETAINItG BOLTS - - -
-t0NE-B3.5 AND STUDS ( 2 2 IN. DIA.)
AND B3.6 B3.7 B-H INTDGRALLY hTLDED - - -
-TOE-VESSEL SUPPORTS B3.8 B-I VESSEL CLADDING - - -
-TOE-B3.9 B-P EXEMPTED COMPONEtITS - - -
-NONE-B3.10 B-G-2 PRESSURE RETAINING - - -
-NONE-BOLTING (< 2 IN. DIA.)
ro. no. ese-. .
0%)=&-38
NORT ..b STATES POWER CO. TABLE S1.3.3 PRAIRIE ISLAND UNIT 2 ___
PAGE 1 OF 1 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: EXCESS LETDOCJ HEAT EXCIRNGERS C
SUB [, Ar) DES I I J INSP. R E O'O AMT. ITEM INSPE CTION GORY ITEM TO BE EX AMINED PER AMT EXAM IDENTIFICATION R E POR T NO.
B3.1 B-B^ IDIGI'IUDINAL AND CIRCUMFERENTIAL WELDS ON ' HIE PRIMARY SIDE IO!EI'IUDINAL WELDS - - -
-TOE-CIRCUMFERENTIAL hELDS ONE 33% -
(tore PERIOD 'IND)
'IWO 66% 100% W-1, HEAD 'IO FIRGE 78-73 .
'HIREE 34% -
~B 3.2 B-D POZZLE 'IO VESSEL WELDS - - -
-!OE-B3.3 B-F IOZZLE 'IO SAFE END WELDS - - -
-!OE-7 B3.4 B-G-1 PRESSURE RETAINItU BOLTS - - -
-TOE-C B3.5 AND STUDS (? 2 IN. DIA.)
AND B3.6
~
B3.7 B-II It7rB3RILLY WELDED - - -
-10NE-VESSEL SUPPORTS B3.8 B-I-l VESSEL CLADDItU - - -
-NCtE-B3.9 B-P -
E}2MPTED COMPONENTS - - -
-NOE-B3.10 B-G-2 PRESSURE RETAINING ONE 4 -
~(NCTTE PERIOD 'IND)
BOLTItU (< 2 IN. DIA.) 'D O 8 8 BOLTS 1 THBO 8 78-72
'HIREE 4 -
F E Hme 17*2 476 FOBOtt 900. $S0-1999
NORTHERN STATES POWER CO. TABLE s1 A PRAIRIE ISLAND UNIT 2 PAGE 1 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: proTm pomc:rnm nnrwnany SUS ^ " 3 M TE. ND DE RI I N INSP. R EQ'D. AMT. ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION R EPORT NO.
GORY ITEM TO BE EXAMINED B4.1 B-P SAFE END 'IO PIPING AND SAFE END IN BRANCH PIPING WEIDS REAC'IOR VESSEL REACIOR CORE COOLANT CNE 1 1 W-1A, 29-2RC-1A 77_W RW REMRP &
77-022,112 SYSIEMS 'INO 1 -
'IHREE 2 -
SAFETY INJECTION CNE 1 1 W-2, 4-2RC-14A 77-W RW REPORF &
77-524,113 SYSlr)tS 'IHREE 1 -
STEAM GENERA'IOR NO. 21 REACIOR CORE COOLANT 'INO 1 -
SYS'IEM 'IEREE 1 -
STEAM GENERA'IOR NO. 22 REACIOR CORE COOIANT CNE 1 1 W-5, 31-2BC-2B 76-136,139 SYSIM 'IHREE 1 PRESSURIZER SAFETY LINES CNE 2 2 W-1, (8010A) 76-26,53 W-1, (80108) 76-61,52
'IWO 2 2 W-1, (8010A)80-187,192,192R,192Ra W-1, (8010B)80-190,191,191R SURGE LINE 'IWO 1 1 W-15 SE, 10-2RC-4 78-31,100 RELIEF LINE 'INO 1 1 W-1B 80-58,88,169
'IHREE 1 -
SPRAY LINE 'IWO 1 1 W-22B 80-56,56R,86,167
'DREE 1 -
""" R
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r u
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E p 7 7 77 78 7 78 _
LET BGp
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. : I T 5, 3, 0 M A 46 84 8, 69 E MC T EIF 2, 3, 5, 3, A 3, 3, _
I TI 25 53 2 38 BT R N E
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NORTHERN STATES POWER CO. TABLE S1.4 PRAIRIE ISLAND UNIT 2 PAGE 3 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: PIPING PRESSURE BOLNDARY SUS EXAM COMPON ENT OR SYSTEM INSP. R EQ'D. AMT. ITEM INSPECTION ITEM y' PER. AMT. EXAM IDENTIFICATION REPORT NO.
mfd E EX M NED B4.5 B-J (ODNT'D)
IETDOWN LINE AND CNE 1 1 W-22 77-27 DRAIN LINE 'IWO 2 2 W-6,7 80-94,95
'IHREE 2 -
AUXILIARY SPRAY ONE 1 1 W-1 77-28
'ID PRESSURIZER TWO 1 1 W-11 78-71 THREE 2 -
RESIDUAL TIMPERATURE CNE 1 1 W-20 77-42 DETECIUR TAKE OFF- 'iWO 1 1 W-6 80-177 ODID IEG A 'IHREE 1 -
RESIDUAL TIMPERATURE CNE 1 1 W-18 77-60 DETECTOR TAKE OFF- 'IWO 2 2 W-8,9 80-116,117 CDID LEG B THREE 1 -
RESIDUAL 'IEMPERATURE (NE 1 1 W-24 77-58 IETECTOR 'DEE OET- IMO 1 1 W-29 80-178 HOT IEG A 'IHREE 2 -
RESIDUAL T1MPERATURE CNE 1 1 W-19 77-59 DEHECTOR 'DGE OFF- IWO l' 1 W-23 80-104 IDT IEG B THREE 2 -
SAFE 1Y INJECTION OE - -
HIGI IEAD A TWO 1 1 W-2 78-15
'IHREE 1 -
SAFEIT INJECTION CNE 1 1 W-7 77-43 HIGi HEAD B TWO - -
'!HREE 1 -
m namrn rYm _ _ _. . _ _ . _ _ _
Cg3D C3 ess-a est
q NORTHERN STATE'd FOWER CO. TABLE S14 PRAIRIE ISLAND UNIT ~> PAGE 4 OF 19 INSERVICE INSFECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING PRESSURE BOUNDARY EXAM COMPONENT OR SYSTEM I M RY M O E EX M NED PE ." AM EXAM IDEN FICATION EO NO.
B4.5 B-J (CONT'D)
DRAIN LINE 01 CNE 1 1 W-14 77-26 CROSSOVER A TWO 1 1 W-7 78-13 HIREE 1 -
REACIOR VESSEL CFE 1 1 W-12 77-17 SAFEIT INJECTION 'IWO 1 1 W-9 78-19 IDW HEAD A HIREE 1 -
REACIOR VESSEL CNE - -
SAFEIT INJECTION TWO .1 1 W-2 78-23 IDW HEAD B HIREE 1 -
(3.0 IN. NOM. DIA. SYSTEMS)
SPRAY 10 PRESSURIZER CNE 3 3 W-5,7,8 77-38,40,39 BRANCH A 'IWO 3 3 W-20,24,25 80-121,120,119 HIREE 4 -
SPRAY TO PRESSURIZER CNE 2 2 W-18,19 77-48,46 BRANCH B 7WO 3 3 W-3,4,5 80-118,122,103 DIREE 2 -
RESIDUAL TEMPERA 1URE CNE 1 1 W-5 77-41 DETIEC10R RE1 URN A iMO 1 1 W-2 78-66 HIREE 1 -
RESIDUAL TEMPERATURE GE 1 1 W-7 77-56 DETBCitR RETURN B TWO 1 1 W-6 78-85 DIREE 1 -
PRESSURIZER pr.Tw CNE - -
LINE A TWO - -
HIREE 1 -
_ __ ____ "_**3t* M E* ________-__
NORTHERN STATES POWER CO. TABLE R1 4 PRAIRIE ISLAND UNIT 2 PAGE 5 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPIIT; PRESSURE BOUNDARY SUB N 8T E. N DE i Tl N0 INSP. R EQ'D. AMT. ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED B4.5 B-J (00NP'D)
PRESSURIZER RELIEF CNE 1 1 W-4 77-47 LINE B TWO 1 1 W-9 80-99 mREE 1 -
(4.0 IN. NOM. DIA. SYSTENS)
SAFETY INJECTION CNE 1 -
TONS CF MIESE IOW HEAD A TWO - -
WELT ARE ACCES-mREE - -
SIBIE; TIIEY APS IOCATED WrDIIN HIE ONCRETTE SHIEID WALL SAFEIY INJECTION CNE - -
(SAME AS IOOP A)
ILW HEAD B TWO - -
WREE 1 -
(6.0 IN. NOM. DIA. SYSTEMS)
REACIOR VESSEL CNE - -
SAFErY INJECTION TWO 1 1 W-6 80-100 IOWHEAD A EREE 1 -
REACTOR VESSEL CNE 1 1 W-9 (4W-8) 76-37 (+76-38)
SAFETY INJECTION WO - -
IDW HEAD B WREE 1 -
~
SAFETY INJECTION CNE - -
HIGH HEAD A TWO - -
WREE 1 -
- SAFE 1T IR1ECTION -
CNE 1 1 W-1 76-143 -
HIGI HEAD B TWO - -
WREE - -
"**"4t"'f#"
NORTHERN STATES POWER CO. TACLE S1.4 PRAIRIE ISLAND UNIT 2 PAGE 6 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING PRESSURE BOLNDARY M N SUB E. N DE I Tl N INSP. R EQ'D. AMT. ITEM INSPECTION ITEM GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
B4.5 B-J (00NT'D)
PRESSURIZER SAF M OE - -
LINS A 'IWO 1 1 W-8 80-102
'mREE 1 -
PRESSURIZER SAFM WE 1 2 W-1 (+W-2) 76-54 (+76-61)
LINE B. 'IWO - -
'DIREE 1 -
PIO-CAP A GE - -
1g0 - -
'mREE 1 -
PIO-CAP B OE - -
'IND 1 1 W-1 80-101
'mREE - -
(8.0 IN. NOM. DIA. SYSTEMS)
RESIDUAL HEAT REMOVAL GE 2 2 W-11,12 77-33,32 TAKE OFF A 'IWO 3 3 W-5,6,8 78-90,94,92
'DIREE 3 -
RESIDUAL HEAT REMOVAL OE 3 8 W-25,27,28 76-74,58,56
'IRRE OFF B (+W-8,10,11,12,26) (+76-70,71,72,73,58)
'INO 2 2 W-12,14 78-95,91
'NREE 3 -
(10.0 IN. NOM. DIA. SYSTEMS)
RESIDUAL HEAT REMOVAL OE 1 2 W-1 (4W-9) 76-9 (+76-7)
REIURN B 'IWO 1 1 W-7 78-102
'DIREE 1 -
_ _ """ 't *'M?_ _ . _ _ - . _ _ _
NORTHERN STATES POWER CO. TABLE c:1 A PRAIRIE ISLAND UNIT ? PAGE ~1 OF to
. INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PTPThn PRN3fDR WNRRY SUB
" YS M E. DE I TIO INSP. R EQ'D. AMT. BTEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION R EPORT NO.
ITEM TO BE EXAMINED B4.5 B-J (CDNr'D)
PRESSURIZER SURGE CNE 1 4 W-12 (4W-11,13,14) 76-81 (+76-78,81,79)
LINE B 'IND 1 1 W-14 78-101
'IEREE 2 -
(12.0 IN. NOM. DIA. SYSTEMS)
ACCUMULMOR DISCHARGE A CNE 1 1 W-11 77-35
'IWD 1 1 W-7 80-35,36
'IHREE 1 -
5 W-1,15 (4W-13,14,76-146,18 (+76-20, ACCLMULMOR DISCHARGE B CNE 2
- 16) 21,19)
'INO 1 1 W-13 80-34,37
'IHREE 2 -
B4.5 B-J (27.5 IN. NOM. DIA. SYSTDtS)
REAC'IOR CORE CODUNT CNE - -
00[D LEG (INLET) A 'INO - -
'IHREE 1 -
REACIOR CCRE COO [JNr CNE - -
00[D IEG (INIET) 3 'IWO 1 -
1sagg _ _
(29.0 IN. NOM. DIA. SYSTD Q REACICR CORE CODIJNr CNE 1 1 W-3, 29-2RC-1A 77-044 EKyr IEG (OUTIET) A 'IWO - -
.innes _ _
l-m.. . .n. . . . . . . . .
N- 2
NORTHERN STATES POWER CO. TABLE SI 4 PRAIRIE ISLAND UNIT _ 2 PAGE 8 op 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING PRESSURE BOUNDARY SUB M M 0NE R YS M I EM h^E. D INSP.
PER.
R EO'O.
AMT.
AMT.
EXAM ITEM IDENTIFICATION INSPECTION R EPORT NO.
GORY 6..M TO BE EXAMINED B4.5 B,J (CONr'D)
REACIOR OORE CDOLANT ONE - -
HOT IEG (OUITET) B 'D O - -
'IHREE 1 -
(31.0 IN. NOM. DIA. SYSTEMS) -
REACIOR CDRE (DOLANT CNE - -
CROSSOVER A 'IWO 2 -
THREE - -
REACIDR CDRE CDOIANT ONE 1 3 W-6 (+W-7,8)76-140 (+76-141,142)
CIOSSOVER B 'INO - -
THREE 1 -
B4.6 B ,J BRANCH PIPE CONNECTICN WEIDS EXCEEDING SIX INCH DIAMETER ACCUPOIA70R DISOIAIGE A - - -
ACCUPOLATOR DISOIARGE B CNE 1 1 W-R 76-145,137
~
. RESIDUAL HEAT RDDVAL - -
TAKE OFF A RESIDUAL HEAT RDOVAL 'D O I -
TAKE OFF B PRESSURIZER SUIGE 'DIREE 1 -
LINE B vsuu n.we
. ro no. wei .
NORTI J STATES POWER CO. SI 4 TA2LE PRAIRic sSLAND UNIT 2 PAGE 9 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR BYEM: PIPING PRESSURE BOL.NDARY sw [jpg, CpNgES INSP. R EO*D. AMT.
IT N 1 10 ITEM INSPECTION GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
B4.7 ih7 BRANCH PIPE 03NECTICN WEIDS SIX INCH DIAMETER AND SMALIER (6.0 IN. NOM. DIA. SYSTEMS)
PID-CAP A - - -
PID-CAP B - - -
SAFEIY IRTECTICN - - -
HIGi HEAD A SAFETY IRTECTICN CNE W-R 1 1 76-138,144 HIGI HEAD B (3.0 IN. NOM.-DIA. SYSTEMS)
SPRAY TO PRESSURIZER - - -
BRANCH A SPRAY TO PRESSURIZER 'DIREE 1 -
BRANCH B
. RESIDUAL TEMPERATilRE - - -
DEHECIOR RETURN A RESIDUAL TEMPERATURE - - -
DETECIOR RE'IllRN B (2.0 IN. NOM. DIA. SYSITMS)
RESIDUAL TEMPERATURE - - -
DETECIOR 'DJCE OFF CDLD IEG A Fs68ts 9 F*24 74 restes 800, 098-8001 PP9-A-21
NORTHERN STATES POWER CO. TABLE S1,4 PRAIRIE ISLAND UNIT 2 PAGE 10 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: PIPING PRESSURE BOUNDARY SUB M COM ONE T YS M INSPECTION INSP. R E Q'O. AMT. ITEM I PER. AMT. EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINEO I
B4.7 B ,7 (CONT'D)
RESIDUAL TEMPERA'IURE E 1 -
DETECIOR TAKE OFF COID LEG B DRAIN LINE ON - - -
CROSSOVER A DRAIN LINE ON CNE 1 1 W-R 76-131 .
ClOSSOVER B Q1AIGING LINE CVCS - - -
REACIOR VESSEL - - -
SAFEIY INJECTICN IIM HEAD A REACIOR VESSEL WREE 1 -
SAFETY INJECTICN IIM HEAD B B4.8 B,7 SOCKETF WELDS (2.0 IN. NOM. DIA. SYSTEMS)
SEAL INJECTION A ONE - -
'INO 1 1 SW-9 78-25 WREE 1 -
SEAL INJECTION B ONE 1 1 SW-64 76-5 E - -
THREE 1 -
'*"""m' ,,,, . . ,,,,_,,,,
NORTHERN STATES POWER CO. TABLE R1 4 PRAIRIE ISLAND UNIT 2 PAGE 11 OF 10 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PTPTE PRPAqfRE AnfMIRRY SU8
^ NN Y M TE- N DESCRI TION O INSP. R EO'D. AMT, ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION GORY ITEM TO BE EXAMINED REPORT NO.
B4.8 Ih7 (CDNT'D)
CHARGING LINE B OE 1 1 % 54 (+ % 57,87) 76-49 (+76-49,6)
'INO 1 1 SW-27 78-28
'IHREE 1 -
DRAIN LINE AND GE 1 1 SW-1 (+SW-24)76-131 (+76-40)
IEIDOWN LINE B 'INO 1 1 SW-10 80-158
'IHREE 1 -
AUXILIARY SPRAY CtE 1 1 SW-4 76-42
'IO PRESSURIZER 'INO - -
'IHREE - -
RESIDUAL TIMPERA'IURE GE 1 1 SW-13 77-117 DE'IEC'IOR TAKE OFF 'IND 1 1 SW-4 78-27 COID IEG A 'IHREE 1 -
RESIDUAL TEMPERA'IURE GE 1 1 SW-15 77-120 DEIECTOR TAKE OFF 'IWD 1 1 SW-4 78-26 COLD IEG B 'IEREE 1 -
BESIDUAL 'IEMPERA'IURE GE - -
DETECIOR TAKE OFF 'IND 1 1 SW-31 80-154 HOT IEG A 'IHREE 1 -
RESIDUAL T!MPERA'IURE OE - -
DE'IEC'IOR 'IRKE OFF 'INO 1 1 SW-29 80-157 IKyr LEG B 'IHREE 1 -
SAFETY IR7BCTION OE - -
HIGI IEAD A 'INO - -
THREE 1 -
s'orns s7 a47s e/7e sposens seo. sse-sees No . __ . _ . __ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
NORTHERN STATES POWER CO. TAELE S1 4 PRAIRIE ISLAND UNIT 2 PAGE 12 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPIfG PRESSURE BOUNDARY SUB
^ " S M INSP. R EQ'D. AMT. ITEM INSPECTION TE- DE Tl N ITEM GORY PER. AMT. EXAM IDENTIFICATION REPORT NO.
ITEM TO BE EXAMINED B4.8 B-J (CDNT'D)
SAFEIY INJECTION CEE 1 1 SW-8 77-110 HIGI HEAD B 'IWO - -
'IHREE - -
DRAIN LINE CN CNE 1 1 SW-13 77-114 CICSSOVER A 'IWO - -
'IHREE - -
REACIOR VESSEL QE 1 1 SW-13 77-111 SAFETY IRTECTION 'INO - -
IDW HEAD A 'DIREE - -
REACIOR VESSEL CNE - -
SAFETY INJECTION 'INO - -
IOW HEAD B 'IHREE 1 -
B4.9 B-K-1 INTEGRALLY WELDED SUPPO1HS SEAL INJECTION A 'IND 1 1 H 78-18,30,39 RESIDUAL TEMPERA'WRE - - -
DETEC'IOR TAKE OFF HOT IEG A SAFETY IR7ECTION - - -
HIGi EEAD A SPRAY 'IO PRESSURIZER BRANCH A 'IWO 1 1 L 80-76,123,156
_ BRANCH B 'DIREE 1 -
RESIDUAL HEAT 'IWO 1 1 0 78-29,50,93 REMOVAL TAKE OFF A ro= = i1 a u s size co== no. .-i .
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NORTHERN STATES POWER CO. TA"LE R1 4 PRAIRIE ISLAND UNIT PAGE 15 OF 19 INSERVICE INSPECTION-12KAMINATION
SUMMARY
MAJOR ITEM: PIPING PRESSURE BOUNDARY SUS
^ " YSTEM INSP. R EO'D. AMT. ITtiM INSPECTION ITEM TE. N DE RI Tl GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
B4.10 B-K-2 (00Nr'D)
RESIIXJAL HEAT GE 5. 5 O,P,Q,S,T 76-41 REKNAL TAKE OFF A 'IWO 5 5 B,C,D,H 78-46,47,48,49 C.E 80-54,23
'IEREE 6 -
ACCLNLT.ATOR DISCHARGE A GE 2 2 H,I 76-33
'INO 3 3 D,E,G 80-25,50,51
'HIREE 3 -
SEAL INJECTION B OE 4 4 O,P,N/Q 76-32/77-157 7WO 4 4 D,E,L,M 80,53,52,47,46
'DIREE 5 -
CIARGING LINE CVCS GE 5 5 R,S,V,W,Y 76-51,85
'INO 7 7 K,M,N,0 78-53,53,52,51 0,0,T,V 80-80,127,126,125
'IHREE 8 -
RESIDUAL TEMPERATURE GE 2 2 A,A1 77-156 DETECTOR 'EAKE OFF 'IWO 2 2 B,C/C 78-54,55/80-145 00tD IEG B 1HREE 2 -
RESIDUAL TEMPERATURE OE 1 1 A2 77-134 DEHEC70R 'mKE OFF 7WO 2 2 A1,A 80-73-73R,72 K7r LEG B 'DIREE 2 -
DRAIN LDE AND GE 2 2 F/C ~n-135/76-108 LEIDOWN LINE B 'IWO 2 2 A,B 80-79,78 THREE 2 -
.. . RESIDUAL TEMPERATURE GE - -
DE'IECIOR REIURN B TWO 1 1 A 78-56
'IHREE - -
NORTHERN STATES POWER CO. TABLE R1 4 PRAIRIE ISLAND UNIT 9 PAGE in OF to INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: pTPIE PRFR9URE TfYNTMPJ SUB ^M NEN R S M TE- N D CIT INSP. R EQ*D. AMT. BTEM INSPECTION LTEM PER. AMT. EXAM IDENTIFICATION GORY ITEM TO BE EXAMINED REPORT NO.
B4.10 B-K-2 (ENf'D)
RESIDUAL IEAT RENOVAL QE 5 5 E/L,M,N,0 76-63/77-145,149 TARE OFF B TWO 5 5 A,B,C 78-57,57,58 C,D,K 80-65,64,133 HIREE 6 -
RESIDUAL HEAT REMOVAL QE 1 1 A 77-132 RE71 URN B IWO 1 1 B 78-59 HIREE 1 -
ACCENUIATOR DISCHARGE B GE 3 3 E,F,C 77-138 7WO 3 3 B,B1/A 78-60/80-48 mREE 4 -
SAFETIY IMJECTION OE 1 1 C 77-127 HIG1 HEAD B 7WO - -
DIREE 1 -
AUXILIARY SPPAY OtE 1 1 A 76-46 TO PRESSURIZER IWO 1 1 B 78-61 DIREE 2 -
r!. CIOR VESSEL GE 1 1 A 77-128 SA RIY IMIECTION TWO - -
IDW HEAD A 3HREE - -
REACIOR VESSEL QE - -
SAFETY IR7ECTION TWO 1 1 A 80-134 IDW HEAD B SIREE - -
PRESSURIZER RELIEP OE - -
LINE B TWO - -
DIREE 1 -
REACIOR VESSEL GE 1 1 D 77-130 SAFETY IRTECTION 7WO 1 1 B 78-4 2 IDWHEAD B f6 x 4") DIREE 2 -
POstM 9 7-8478 Gs,8 postu seo. ess-teet
Y NORTHERN STATES POWER CO. TABLE c1 1 PRAIRIE ISLAND UNIT 2 PAGE 17 OF to INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: orpru pomc:rm wwwnany SU8 INSP. AMT. INSPECTION ITEM hTE. N DE I Ti N PER.
R EQ*D.
AMT. EXAM BTEM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED B4.10 B-K-2 (CONT'D)
REACIOR VESSEL CNE 1 1 D 77-129 SAFEIY INJECTION 'IWO 1 1 A 80-75 I N HEAD A (6x4") 'IHREE 2 -
PRESSURIZER SAFETY CNE 1 1 A1 77-152 LINES A & B 'INO 1 1 A2 80-128
'IHREE - -
PRESSURIZER SURGE B CNE 3 3 K,J,I 76-48
'IWO 4 4 A,B/C,D 78-64,63/80-70,71
'IHREE 5 -
REACIOR CDRE COOUNP CNE - -
CROSSOVER A 'IWO I -
'IHREE 1 -
REAC10R CCRE CODIANr CNE 1 1 B1 76-106 CBOSSOVER B 'IWO - -
'!HREE 1 -
B4.11 B-P EXEMPP AND NON-EXEMPP - * -
- ALL CCMIONENTS PEREDBMED BY COMFWENTS EXAMINED IN FIANT PER90tNEL ACCDRDANCE WTIH BYDROSTATICAILY PRESSURE IWA-5000 AND
'IESTED 'IO IWA-5000 Ar 12-5000 DURING END OF TEN YEAR INIERVAL SYS'ITM IEAKACE PLUS SYS'ITM IEAKEAGE 'IEST EXAM EAG SCHEDUIED REFrFLTNG OUTAGE ronessp.a47s stre pones seo, ese-seen N
NORTHERN STATES POWER CO. TABLE R1 4 PRAIRIE ISLAND UNIT ? PAGE 1R OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: PIPING PRESSURE BDEN RIN SUS INSP. R E O'D. AMT. ITEM INSPECTION ITEM E AN O I N GORY' ITEM TO BE EX AMINED ER. AMT. EXAM IDEN NI W ION R EN NO.
B4.ll B-P (CONT'D)
EXEMPT:
RESISTANCE TEMPERATURE DEIECIOR TAKE OFF -
1-2RC-7A EXCESS LE1DC6M LINE A 1-2RC-8 1-2VC-7 2VC-9 RESISTANCE TEMPERATURE DETECIOR 1AKE OFF 1-2RC-7B REACIOR VESSEL CICSURE HEAD VENT 1-2RC-36 REACIOR VESSEL C[DSURE HEAD FLANG3 1-2RC-9A l-2RC-9B B4.12 B-G-2 PRESSURE RETAINING BOLTING (CNLY SYSTEMS APPLICABLE TO THIS ITEM ARE LISTED)
SEAL INJECTION A ONE 4 4 BOLTS 1-4 9 W-2 76-76 TWD 4 4 BOLTS 1-4 9 W-4 78-81 RESISTANCE TEMPERATURE THREE 8- --
DEIECTOR RETURN A co. . . .
NORTHERN STATES POWER CO. TABLE SI 4 PRAIRIE ISLAND UNIT 2 PAGE 19 OF 19 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING PRESSURE BOLNDARY M N 8E M SUS INSP. R EQ'O. AMT. STEM INSPECTION ITEM E- N DE RI 0 EXAM GORY ITEM TO BE EXAMINED PER. AMT. IDEN W W ION REPMT NO.
B4.12 B-G-2 (CINr'D)
PRESSURIZER SAFE'rY '1:0 12 12 Bolts 1-12 8 80-135 LINE A 2-8010A SEAL INJECrION B DD 4 4 lblts 1-4 e w-2 80-172
'DIREE 4 -
RESISTANCE 'IEMPERA'IURE 'IHREE 8 -
DE'IEC'10R RE'IURN B PRESSURIZER SAFETY CNE 12 ,
12 BOLTS 1-12 76-17 LINE B T"
comm n. san sfu coma no. ms-s ee
NORTHERN STATES POWER CO. TABLE SI M PRAIRIE ISLAND UNIT _ 2 PAGE 1 OF. 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: REACIOR CORE GXXANT PLMPS SUB I E- DE I I N INSP. R EO'O. AMT. ITEM INSPECTION GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
B5.1 B-G-1 PRESSURE RETAINING BOLTS MO AND SIUDS, IN PIACE B5.3 (2 2 IN. DIA.)
FLANGE BOLTS PUMP A ONE 8 8 BOLTS 1 m 8 76-87
'IWO 8 8 BOLTS 9 M 16 78-67
'IHREE 8 -
PUMP B CNE 8 8 BOLTS I M 8 76-86
'IWO 8 8 BOLTS 9 'IHRJ 16 78-68
'IHREE ITEM -
B5.2 SEAL HOUSE BOLTING PLMP A ONE 4 4 BOLTS 1 'IHRU 4 76-89
'IWD 4 4 BOLTS 5 W 8 78-69
'IHREE 4 -
PUMP B ONE 4 4 BOLTS 1 THRU 4 76-88
'IND 4 4 BOLTS S M 8 78-70
'IHREE 4 -
B5.2 B-G-1 PRESSURE RETAINING BOLTS AND AND S' IUDS, WHEN REMOVED B5.3 ( 42 IN. DIA.)
PUMP B 'IHREE 24 -
FIANGE BOLTING PLMP B THREE 12 -
SEAL HOUSE BOLTIIG vs . i,.a.,.
roman m . me-seen
NORTHERN STATES POWER CO. TABLE S1.5 PRAIRIE ISLAND UNIT 2 PAGE 2 OF 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: RFACIOR CDRE COOIANT P(DIPS SUB COM ONENT R SYS M AMT. ITEM INSPECTION I
hkM INSP.
PER.
R EQ'O.
AMT. EXAM IDENTIFICATION REPORT NO.
GORY l TEM TO BE EMAMINED B5.4 B-K-1 INTEGRALLY hTLDED SUPPORPS RNP A - - -
-RELIEF NO. 47-PLMP B 'IHREE 3 -
-RELIEF NO. 47-B5.5 B-K-2 SUPPORP COMPONENIS* *CDINCIDEhT WITH SEISMIC BOLTING REP A 00wMN AND ' ONE 1 1 COLUMN 1 77-67,163,158 IATERAL SUPPORTS 'IWO 1 1 COwMN 2 80-181,107,174
'IHREE 1 PUMP B CDLUMN AND ONE 1 1. COwMN 1 77-64,162,161 IATERAL SUPPORTS 'IWO 1 1 COwMN 2 80-181,107,108
'IHREE 1 B5.6 B-L-1 PUMP CASING hTLDS PUMP A - - -
-BONE-RJMP B - - -
-NONE-B5.7 B-L-2 PUMP CASINGS REP A & B 'IEREE 1 B5.8 B-P EXEMPTED COMPONENIS - - -
-NONE-B5.9 B-G-2 PRESSURE RETAINING - - -
-NONE-BOLTING (< 2 IN. DIA.)
ro - ronu wrm. isi-seen ge one
NORTHERN STATES POWER CO. TABLE S1.5 PRAIRIE ISLAND UNIT 2 PAGE 3 OF 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: REAC'IOR CORE 000LANT PUMPS SUB
^ NE oR M TE. D pp q INSP. R E Q'D. AMT. BTEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION R EPORT NO.
ITEM TO BE EXAMINED
-
- PUMP FLYWEFErs RMP A & B CNE 2 2* RMP-21, FLYWHEEL 76-113,117,116 RJMP-22, FLYhTEEL 76-93,82,92
'INO 2 2 RMP-21, FLYWHEEL 80-141,142,143
'IHREE - -
RMP-22, FLYWHEEL 80-124,139,140
. *BOIH FLYWinvrA WERE RDIOVED AS A RESULT OF MODIFICA-TION 'IO 'DE PUMP WBRICATION SYS'IEM
'DE BORE AND KEY-1&Y'S WERE PI EXAM-INED & 'DE RD'AIN-ING SURFACES WERE MT EXAMINED. U.T.
WAS USED 'IO VOWPE-
'IRICALLY EXAMINE
'DE FLYWHEEIS (NOIE
'IECH SPEC 4.2-1)
.. . ..m. .n. m.. . . .
. W _ .-. .
NORTHERN STATES POWER CO. TABLE SI.6 PRAIRIE ISLAND UNIT 2 PAGE 1 OF 4 INSERVICE INSPECTION-EXAMINATION SUM *AARY M AJOR ITEM: VALVE PRESSURE BOLNRRY SUS
^ "
ITEM $TE. N DE RI Tl N INSP. R EQ'D. AMT. ITEM INSPECTION GORY ITEM TO BE EXAM:NED PER. AMT. EXAM IDENTIFICATION R EPORT NO.
B6.1 B-G-1 PRESSURE RETAINING - - -
-f0NE-B6.2 BOLTS AND SIUDS AND (< 2 IN. DIA.)
B6.3 B6.4 B-K-1 INTEGRALLY WEIDED - - -
-NONE-SUPPORTS B6.5 Br-K-2 SUPPORP 00MPCNENTS - * -
- INCIIDE IN
'IRBIE 1.4 UNIER B4.10 B6.6 B-M-1 VALVE BODY WEIDS - - -
-N3E-B6.7 B-M-2 VALVE BODIES
(> 4 IN. NOM. PIPE SIZE)
REACIOR VESSEL 'IHREE 1 -
SAFEIT INJECTICE IDW HEAD A RESIDUAL HEAT 'IHREE 1 -
REMOVAL TAKE OET A PRESSURIZER SAFETY THREE 1 -
LINE A RESIDUAL HEAT 'IHREE 1 -
RENNAL RETURN B ACCtMULA'IDR DISCHABCE A 'IHREE 1 -
B6.8 B-P EXEMPTED COMPCMENTS
- 100%
- ITEMS INSPECTED IEPECTED BY DURING EACH PIANT PERSCttEL IEAKACE 'IEST
"" "0"a"" _ - _ __ ""_" "?_' " '_.__
NORTHERN STATES POWER CO. TABLE SI.6 PRAIRIE ISLAND UNIT 2 PAGE 2 OF 4 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: VALVE PRESSURE BOWDARY SUB E- N DE I I N INSP. R EO'D. AMT. ITEM INSPECTION REM GORY PE3. AMT. EXAM IDENTIFICATION REPORT NO.
ITEM TO BE EXAMINED B6.9 B-G-2 PRESSURE RETAINING *N7IE SUPPIDENT BOLTING
- B6.9 AT 3.4.3 ACCIMJLMOR DISCHARGE CNE 16 16 CHBCK, 2-8841A 76-12 IOOP A - 12" 'IHREE 16 -
ACCLMULMOR DISCHARE 'IWO 16 16 CHBCK, 2-8841B 80-82 IOOP B.- 12" 'IHREE 16 -
RESIDUAL HEAT CNE 16 16 M.O. GME, 2-8703 76-13 BEMOVAL REIURN B-10" RESIDUAL HEAT 'IWO 16 16 M.O. GME, 2-8701 A 78-80 REMOVAL TAKE OET A-8" "IHREE 16 -
RESIDUAL HEAT CNE 16 16 M.O. GME, 2-8701B 76-16 REMOVAL TAKE CFF B-8" CNE 16 16 M.O. GME, 2-8702B 76-16 SAFETY INJECTION 'IWO 12 12 GECK, 2-8842A 80-166 HIGH HEAD A - 6" SAFETY INJECTION 'IHREE 12 -
HIGH HEAD B - 6" PRESSURIZER SPRAY IOOP A - 3" 'IHREE 8 -
IOOP B - 3" CBE 8 8 G DRR(2-PCV-431B) 76-28
'IHREE 8 -
RESISTANCE 'ITMPERMURE 'IWO 12 12 GME, 2-8001A 78-79 DETECIOR RETIURN IOOP A - 3"
- -- RESISTANCE 'ITMPERMURE . 'INO . 12 12_ GME, 2-8001B 78-78 DETIBCIOR RE'IURN IDOP B - 3" renes tv-seve, s/7s comes seo. ess-toes
NORTHERN STATES POWER CO. TA!LE S1.6 PRAIRIE ISLAND UNIT 2 PAGE 3 OF 4 INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: VALVE PRESSURE BOLNDARY
" R EQ'O, SUB E. N i Ti N INSP. AMT. ITEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION REPORT NO.
ITEM TO BE EXAMINED B6.9 B-G-2 (CONr'D)
RESISTPNCE 'IDiPERA'IURE OtE 2 2 2r58, 2RC-1-6 76-95 DEIEC7DR 1RKE OFF TNO 2 2 2r58, 2RC-1-7 80-152 ODID IEG A - 2" 'IHREE 2 -
RESISTANCE 'ID(PERATURE TWO 2 2 2r58, 2RC-1-15 80-137 DE'IECTOR TM(E OFF INO 2 2 2r58, 2RC-1-16 80-165 CDID IEG B - 2" 'IHREE 2 -
RESISTANCE TDiPERATURE 'INO 2 2 2r58, 2RC-1-9 80-150 DE7EC'IDR 1RKE OFF TWO 2 2 2r58, 2RC-1-10 80-151 IUr IEG A - 2" "IHREE 2 -
RESISTANCE TEMPERATURE (NE 2 2 2r58, 2RC-1-12 76-103 DETECIDR TAKE OFF 7WO 2 2 2r58, 2RC-1-13 80-136 IUr IEG B - 2" 'IHREE 2 -
PRESSURIZER RELIEF ONE 12 12 M.O. GATE, 2-8000B 76-14 LINES 3" OE 6 6 GDBE, 2PCV-431C 76-14 TWO 6 6 GDBE, 2PCV-430 80-149 THREE 12 -
REACIOR VESSEL SAFETY IlUECTION IOW HEAD A - 6" CNE 12 12 OIECK, 2-6843A 76-91 TWO 12 12 OIECK, 2-8844A 80-171 ,
IDW HEAD B - 6" OE 12 12 CHECK, 2-8843B 76-36 THREE 12 -
AUXILIARY SPRAY 'IHREE 6 -
CVCS - 2" rosess7-save e/7e mens no.ese-me
_________.__. N 72_______ _ _ __ _ _ _ _ ______ _ __ _ __ _ __ - - _ . .
NORTHERN STATES POWER CO. TABLE. S1,6 PRAIRIE ISLAND UNIT 2 PAGE 4 OF 4 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: VALVE PRESSURE B0lNDARY SUS ^M N M TE- N DE Tl N INSP. R EQ'D. AMT. ITEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION REPORT NO.
ITEM TO BE EXAMINED B6.9 B-G-2 (CDNT'D)
. DRAIN LINE OE 2 2 2r58, 2RC-1-3 76-11 CN CROSSOVER B 'IHREE 2 -
DRAIN LINE CNE 2 2 2r58, 2RC-1-2 76-15 ON CROSSOVER A- 2" 'IHREE 2 -
IEHXMi LINE B - 2" QE 8 8 A.O. (TN, 76-10 2IEV-427
'IWO 2 2 2r58, 2RC-1-5 80-81
'IHREE 8 -
CHARGING IJNE B - 2" 'IND 6 6 A.O. GDBE, 78-24 2-8142 SEAL INJECTION A - 2" QE 2 2 2T-58, 2VC-7-18 76-94 SEAL INJECTION B - 2" OE 2 2 2T-58, 2VC-7-19 76-84 s -
Poness7-aare stre rones peo.see-seen PP9-B-8 . , _ _ . . _ _ .
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 1 0F 10 BASELINE COMPARISON
SUMMARY
i NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM _
ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS REACTOR VESSEL Bl.15 VESSEL INTERIOR VT
- W NONE NONE NONE W= WESTINGHOUSE
- REPRESENTATIVE INTERNALS RPT REGIONS OF THOSE 1980-UNIT 2 INTERIOR SURFACES AND INTERNALS B2.4 N0ZZLE TO SAFE END WELDS PRESSURIZER SAFETY LINE A 30 UT W-1A S.E.80-188 76-53 NONE S-1; N0ZZLE CONFIG.
S-2; LIMITED TO 1" CONFIG.
PT 80-192 76-26 ROUGH SURFACE WELD SPLAT-TER @l2,3
& 7:30 PT 80-192R 3-3/16" LINEAR NOTE: EXAM IN CON-2-5/16" LINEAR JUNCTION WITH SAFE
- SEVERAL ROUNDED END TO PIP WELD.
INDICATIONS .
! PT 80-192Ra -
SEVERAL ROUNDED INDICATIONS f SAFETY LINE B 30 UT W-1A S.E.80-189 76-52 NONE NONE S-1; N0ZZLE S-2: LIMITED TO 1" CONFIG.
PT 80-191 76-61 ROUGH SURFACE NONE UNDERCUT @
6:00 80-191R NONE NONE i________._____._______________.________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
__ _ _ . _ . _ _ _ _ _ _ _ JZWm fah T@H-1003
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT ? PAGE 2 0F 10 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENr. NO. INDICATIONS INDICATIONS LIMITATIONS RELIEF LINE 27 UT W-1A S.E. 80-87 NONE NONE S-1; N0ZZLE UT 80-170 NONE S-2,ID GEO, 50% S-1; N0ZZLE PT 80-58 NONE NONE NONE SPRAY LINE 7 UT W-22A S.E. 80-85 NONE NONE S-2; N0ZZLF,80-168 NONE . S-1, OD GEO, 63% S-2; N0ZZLE PT 80-57 NONE NONE NONE B4.1 SAFE END TO PIPING AND SAFE END IN BRANCH PIPING WELDS PRESSURIZER 30 UT W-1 80-187 76-53 NONE NONE NO S-1; SAFE END SAFETY LINE A CONFIG.
PT W-1 80-192 UNkRbT ROUGH SURFACE 80-192R : 3-3/16" LINEAR NOTE: EXAM IN CON-2-5/16" LINEAR JUNCTION WITH SEVERAL ROUNDED N0ZZLE TO SAFE END INDICATIONS WELD i 80-192Ra NONE 30 UT W-1 80-190 76-52 UONE NONE NO S-1; SAFE END SAFETY LINE B CONFIG, PT 80-191 76-61 NONE ROUGH SURFACE 80-191R NONE NONE FORM NO. ISI-1003
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 3 0F 10 BASELINE COMPARISON
SUMMARY
I NSP NDE W BASELINE REPORT ISI EXAMINATION COMPONENT /SYSTDi ISO METHOD _ IDENT. NO. IBASELINE 1DICATIONS INDICATIONS LIMITATIONS RELIEF LINE 27 UT W-1B 80-83 NONE NONE S-2; REDUCER 80-169 NONE S-1, OD GEO, 100% S-2; PIDUCER PT W-1B 80-58 NONE NONE NONE SPRAY LINE 7 UT W-22B 80-86 NONE NONE S-1; REDUCER 80-167 NONE NONE S-1; PIDUCER PT W-22B 80-56 NONE 3/16" LINEAR NONE 80-56R NONE NONE NONE B4.5 CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS SEAL INJECTION B 12B UT W-29 80-91 NONE NONE S-2: 8:00 TO 2:00 ELBOW I.R.
W-33 80-90 NONE NONE S-2; 4:00 TO 8:00 ELBOW I.R.
W-34 80-89 NONE NONE S-1; 4:00 TO 8:00 ELBOW I.R.
' NO S-2 W-36 80-92 NONE NONE S-1; 2:00 TO 10:00 ELBOW I.R.
W-37 80-93 NONE NONE S-2; 4:00 TO 8:00 ELBOW I.R.
13B UT W-37 80-96 NONE NONE S-1; 1:00 TO 5:00 CHARGING LINE ELBOW I.R.
FORM NO. ISI-1003
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 4 0F 10 BASELINE CmfPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYS m ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS CHARGING LINE 13B UT W-38 80-97 NONE NONE S-2; 1:00 TO 5:00 ELBOR I.R.
W-39 80-98 NONE S-1, OD GEO, 50% S-1; 4:00 TO 8:00 ELBOW I.R.
LETDOWN AND DRAIN 16 UT W-6 80-94 NONE NONE S-2; 4:00 TO 8:00 ELBOW I.R.
W-7 80-95 NONE NONE S-1; 10:00 TO 2:00 ELBOW I.R.
RTD COLD LEG A 3 UT W-6 80-177 1/16" @ 1/2* NONE NO S-1; 6:00 TO 100% 2:00 RESTRAINT 1/16" @ 2" S-2; 2:00 TO 8:00 100% ELBOW I.R.
RTD COLD LEG B 14 UT W-8 80-116 1 7/16" LONG S-1, ID GEO, 70% S-1; 4:00 TO 8:00 9 2. T 100% S-2, ID GEO, 75% ELBOW I.R.
+ 2. dB S-2; 9:00 to 11:00 ELBOW I.R.
NO SCANS 7:00 TO 9:00 HANGER W-9 80-117 NONE NONE NO S-1 S-2,3&4; 8:00 TO 4:00 HANGER RTD HOT LEG A 4 UT W-29 80-178 2" IANG @ NONE S-1; 4:00 70 8:00 2.8T 100% ELBOW I.R.
+2dB
- - - - _ _____ _ . _ _ _ _ _ _ . . _ _ _ . - - - - - - - - - - - _ -- __ __ _ _ _ _ _ FORM NO. ISI-1003
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 0F 5 10 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD _ IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS RTD HOT LEG B 15 UT W-23 80-104 NONE NONE S-1; 7:00 TO 11:00 ELBOW I.R.
SPRAY TO PRESSURIZER 7B UT W-20 80-121 NONE NONE S-2; 1:00 TO 5:00 BRANCH ELBOW I.R.
W-24 80-120 NONE NONE S-2; 10:00 TO 2:00 ELBOW I.R.
W-25 80-119 NONE S-1, OD GEO, 50% S-2: 4:00 TO 8:00 ELBOW I.R.
SPRAY TO PRESSURIZER 7D UT W-3 80-18 NONE NONE S-1; 4:00 TO 8:00 BRANCH B ' ELBOW I.R.
W-4 80-122 NONE NONE NO S-1; 2:00 TO 7:00 RESTRAINT S-2; 1:00 TO 5:00 ELBOW I.R.
W-5 80-103 NONE NONE S-1; 7:00 TO 11:00 ELBOW I.R.
1 PRESSURIZER RELIEF 27 UT W-9 80-99 NONE NONE S-1; 11:00 TO 1:00 LINE B HANGER S-2: 1:00 TO 5:00 ELBOW I.K.
REACTOR SAFETY INJECTION A 29 UT W-6 80-100 NONE -NONE NO S-2; VALVE 30 UT W-8 80-102 NONE NONE NO S-2; FLANGE PRESSURIZER SAFETY LINE A -
S-1,3&4; 3:00 TO 6:00 HANGER FORM NO. ISI-1003
l ) : ,lllllll ll 3
0 0 0 1 OTOT O . .
1 NS E TNTN TT G G -
ON L I I N I I I IO Z 0A0A 0I F F S I F TI Z 0R0R EE 0A E NEE NEE I I 0 AT 0 : T: T NN : R N ONN ONN NA N 2S2S OO 5T O COO COO .
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1 3 3 33 1 1 1 1 1 7 114 OO - - - - - - - - - - - - - -
PN 0 0 0 00 0 0 0 000 000 E 8 8 8 88 8 8 8 888 888 R
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N A Y A P R B M A D O M E E E C 2 M G G D R U M R R L E R S E A A E Z E T H H S N W I R B WTN S C C D I U
OIO Y S S L A Y PNS S B I I E R L S N UI / D D W D A L S O S R T P B A E I EDA N O R R T D G R R T '
TNP E O O O E N E G G P C AAM N L T T K A L E E E .
TLO O A A C L T S OA J SSC P P L L O N T T N T T N I M A U U S W O O I R H I N E O C M M O H H O YC REN C - U U 8 D 9 P AN L EII O C C T D D P RA A HRL L C C 4 E T T 4 U PR E TIE P A A B L R R B S SB S RAS ORA "
NPB
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 10 PAGE 7 0F BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE '
COMPONENT / SYSTEM ISI EXAMINATION ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS B4.10 SUPPORT COMPONENTS S2AL INJECTION A. IA VT A 80-148 NONE NONE . NONE B 80-148 NONE NONE NONE C 80-147 NONE NONE NONE RTD COLD LEG A 3 VT B1 80-144 -
NUT NOT FLUSH NONE 80-144R NONE NONE RTD HO LEG A 4 VT G 80-146 -
NONE NONE H 80-146 --
NONE NONE SAFETY INJECTION HIGH A 5 -VT D 80-132 -
NONE NONE SPRAY TO PRESSURIZER 7C VT V 80-135 NONE NONE . . NONE BRANCH A SPRAY TO PRESSURIZER 7D VT D 80-129 SPRING NONE NONE BRANCH B READING LOCKED IN PLACE E 80-130 NONE NONE NONE F1 80-131 NONE NONE NONE RHR TAKE OFF A 10A VT C 80-23 NONE NONE NONE E 80-54 SPRING NONE NONE READING LOCKED IN PLACE ACCUMULATOR DISCH, A 11 VT D 80-25 NONE NONE NONE E 80-50 NONE NONE NONE G 80-51 NONE NONE NONE FORM NO. ISI-1003
... c. ..
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 8 0F 10 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYS*'EM ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS SEAL INJECTION B 12B VT D 80-53 SPRING NONE NONE READING LOCKED IN PLACE E 80-52 NONE NONE NONE 12A VT L 80-47 NONE NONE NONE M 80-46 NONE NONE NONE CHARGING LINE 13B VT 0 80-80 NONE NONE NONE 13C VT Q 80-127 NONE NONE NONE T 80-126 NONE NONE NONE V 80-125 NONE NONE NONE RTD COLD LEG B 14 VT C 80-145 NONE NONE NONE RTD HOT LEG B 15 VT A1 80-73 -
LOOSE NUTS NONE A1 80-73R NONE NONE A 80-72 NONE NONE NONE LETDOWN AND DRAIN 16 VT A 80-71 NONE NONE NONE B 80-78 NONE NONE NONE RHR TAKE OFF B 20A VT C 80-65 INCOMPLETE NONE NONE ON WELD 7 D 80-64 NONE NONE 20B VT K 80-133 145# 1-1/2" NONE NONE DEFLECTION ACCUMULATOR DISCH B 22 VT -A 80-48 NONE NONE NONE
' REACTOR VESSEL SAFETY 26 VT' A- 80-134- -
NONE NONE INJECTION B FORM No. ISI-1003
NORTHERN STATES POWER COMPANY TABLE TT PRAIRIE ISLAND UNIT 2 PACE 9 0F 10 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENT, NO. INDICATIONS INDICATIONS LIMITATIONS REACTOR VESSEL SAFETY 29 VT A 80-75 NONE NONE NONE INJECTION A PRESSURIZER SAFETY B 30 VT A2 80-128 NONE NONE NONE PRESSURIZER SURGE 31 VT C 80-70 WELDS INCOMP NONE NONE D 80-71 WELDS INCOMP NONE NONE B4.12 PRESSURE-RETAINING BOLTING PRESSURIZER SAFETY A 30 VT 12 BOLTS / 80-135 NONE NONE NONE NUTS @
RV2-8010A SEAL INJECTION B 12 VI 4 BOLTS80-172 NONE NONE NONE NUTS @ W-2 REACTOR COOLANT PUMPS PUMP 21 FLYWHEEL 45 UT KEYWAY 80-143 NONE NONE NONE CORNER FLYWHEEL 80-142 NONE NONE NONE BODY PERIPHERY 80-141 NONE NONE NONE PUMP 22 FLYWHEEL 45 UT KEYWAY 80-140 NONE NONE NONE CORNER FLYWHEEL 80-139 NONE NONE NONE
. _ . . BODY PERIPHERY 80-124 NONE NONE NONE FisTT3_Prokj W(gj R@
NDRTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 10 0F 10 BASELINE C(BfPARISON
SUMMARY
I NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYS'IM ISO METHOD _ IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS B6.9 PRESSURE RETAINING BOLTING ACCUMULATOR DISCH. B 22 VT 2-8841B 80-82 NONE NONE NONE SAFETY INJECTION HIGH A 8 VT 2-8842A 80-166 NONE NONE NONE RTD COLD LEG A 3 VT 2-RC-1-7 80-152 NONE NONE NONE RTD COLD LEG B 14 VT 2-RC-1-15 80-131 NONE NONE NONE 2-RC-1-16 80-165 NONE NONE NONE RTD HOT LEC A 4 VT 2-RC-1-9 80-150 NONE NONE NONE 2-RC-1-10 80-151 NONE NONE NONE RTD HOT LEG B 15 VT 2-RC-1-13 B0-136 NONE NONE NONE PRESSURIZER RELIEF B 27 VT 2-PCV-430 B0-149 NONE NONE NONE REACTOR VESSEL SAFETY 29 VT 2-8844A BO-171 NONE NONE NONE INJECTION LOW A LETDOWN LINE 16 VT 2-RC-1-5 B0-81 NONE NONE NONE
$ h
-- - _ _ _ _ _ _ _ . _ _ __ FORM NO. ISI-1003 .- . .
<e. =. .. a.
Table III PAE 1 0F 4
'NORMERN STATES P0hT.R CO.
PRAIRIE ISIAND UNIT 2 ISGETRIC SLM1ARY CLASS 1 REVISIQ4 00MPONDir OR SYSTEM ILOP h BR AkR t
2-ISI-l 0 SEAL INJECTION (GENERAL VIEW) A lh"62" - -
A 1" 1 -2VC-21A 1 2-ISI-1A 0 3 A 2" 2-2VC-21A 2-ISI-1B 0 3 A 2" 2-2VC-21A 2-ISI-1C 0 A 2" 2-2RC-10A 3 2-ISI-2 0 CROSSOVER DRAIN 2-2RC-llA 3 A 2" 2-2RC-8A 3 2-151-3 0 RTD TAKEOFF COLD LEC 2" 2-2RC-7A 3 A
2-131-4 0 RTD TAKEOFF HOT LEG 2" 2-2SI-35A 3 A
2-ISI-5 0 SAFETY INJECTION HIGH HEAD 3-2RC-6A 4 A 3" 2-ISI-6 0 RTD RETURN A&B 3" -
2-lSI-7 0 SPRAY TO PRESSURIZER (GENERAL VIEW) A 3" 3-2RC-5 4 0 4 2-ISI-7A A 3" 3-2RC-5 0 4 2-ISI-7B A 3" 3-2RC-5 0 3-2RC-5 4 2-ISI-7C B 3" 2-ISI-7D 0 6" 6-2RC-13B 6 A
2-ISI-8 0 SAFETY INJECTION HIGH HEAD 6-2RC-13A 6 A 6" 2-ISI-9 0 PLO-CAP A 8" -
0 RHR TAKE OFF (GENERAL VIEW) 8" 8-2RC-15A 8 2-ISI-10 8 2-ISI-10A 0 8" 8-2RH-1A 0 8-2RH-1A 8 2-ISI-10B 8" 2-ISI-10C 0 12" 12-2RC-16A 11 A
0 ACCUMULATOR DISCHARGE 12-2SI-27A 11 2-ISI-11 O
Table III '
NRIHERNSTATESPNERCD. PAGE 2 op 4 PRAIRIE IStAND WIT 2 ISOMETRIC SG NARY i
REVISIN COMP m ENT OR SYSIB! LOOP ER 2-ISI-12 0 SEAL INJECTION (GENERAL VIEW) B lb"62" - -
2-ISI-12A 0 B 2" 2-2VC-21B 3 2-ISI-128 0 B 2" 2-2VC-21B 3 2-ISI-12C 0 B 1\" 1 -2VC-21B 1 2-ISI-13 0 CHARGING LINE (CENERAL VIEW) B 2" - -
2-ISI-13A 0 B 2" 2-2RC-17 3 2-151-135 0 B 2" 2-2VC-5 3 2-ISI-13C 0 B 2" 2-2VC-6 3 2-ISI-13D 0 B 2" 2-2VC-6 3 2-ISI-14 0 RTD TAKEOFF COLD LEC B 2" 2-2RC-8B 3 2-151-15 0 RTD TAKEOFF HOT LEG B 2" 2-2RC-7B 3 2-ISI-16 0 CROSSOVER DRAIN AND LETDOWN B 2" 2-2RC-10B 3 2-2RC-11B 3 2-2RC-12 3 2-ISI-17 0 RTD RETURN B 3" 3-2RC-6B 4 2-ISI-18 0 SAFETY INJECTION HIG". HEAD E 6" 6-2RC-13D 6 2-ISI-19 0 PLO-CAP B 6" 6-2RC-13C 6 2-ISI-20 0 RHR TAKEOFF (GENERAL VIEW) B 8" - -
2-ISI-20A 0 B 8" 8-2RC-155 8 2-ISI-208 0 B 8" 8-2RH-1B 8 2-ISI-20C 0 B 8" 8-2RH-1B 8 2-1S1-21 0 RHR RETURN B 10" 10-2SI-26 10 2-ISI-22 0 ACCUMULATOR DISCHARGE B 12" 12-2RC-168 11 12-251-27B 11
- . . , _ , . . - ~ _ - - _ . . ._ . - - _ _ , - . . _ . . . - . _ _ _ . - - _ - _ . . . _ _ _ , - _ - - --
... .. .. n Table III M)R1HERN STATES POWER CO. PA 3 OF 4 PRAIRIE ISIAND LNIT 2 ISOMETRIC SL*SMRY ,
REVISIm COMPONENT OR SYSIDI IDOP h R ST.
2-ISI-23 0 SAFETY INJECTION HIGH HEAD B 2" 2-2SI-35B 3
- 2" 2-2RC-19 3 2-ISI-24 0 AUXILIARY SPRAY 2-2VC-4 3 2-ISI-25 0 REACTOR VESSEL SAFETY INJECTION A 2" 2-2SI-24A 3 2-ISI-26 0 REACTOR VESSEL SAFETY INJECTION B 2" 2-2SI-24B 3 A&B 3" 3-2RC-21 4 2-ISI-27 0 PRESSURIZER RELIEF 2-ISI-28 0 REACTOR VESSEL SAFETY INJECTION B 4" 4-2RC-14B 5 B 6" 6-2RC-14B 6 B 6" 6-2SI-25B 6 2-ISI-29 0 REACTOR VESSEL SAFETY INJECTION A 4" 4-2RC-14A 5 A 6" 6-2RC-14A 6 A 6" 6-2SI-25A 6 2-ISI-30 0 PRESSURIZER SAFETY A 6" 6-2RC-20A 6 B 6" 6-2RC-20B 6 PRESSURIZER SURGE B 10" 10-2RC-4 10 2-ISI-31 0 A 29" 29-2RC-1A 15 2-ISI-32 0 REACTOR COOLANT A 31" 31-2RC-2A 15 A 27 " 27 -2RC-3A 15 B 29" 29-2RC-1B 15 -
2-ISI-33 0 REACTOR COOLANT B 31" 31-2RC-2B 15 B 27 " 27 -2RC-3B 15
- - - 6 2-ISI-34 0 REGENERATIVE HEAT EXCHANGER 2-ISI-35 -
0 PRESSURIZER SAFETY AND RELIEF N0ZZLES ,
... = ,, .
Table III NORIHERN STATES P W ER Q. PAT 4 OF 4 PRAIRIE ISLAND INIT 2 ISCME.TRIC SGNARY LINE LINE UT - CAL, NSP ISO COMP WENT OR SYSTD1 IAOP REVISICN SIZE NtNBER STANDARD NtNBER 2-ISI-36 0 PRESSURIZER - - -
25A/16 0 STEAM GENERATORS A&B - - 25A 2-ISI-37 2-1S1-38 0 REACTOR VESSEL CONOSEAL BOLTING 0 REACTOR VESSEL STUDS, NUTS & WASHERS - - - STUDS-17 2-ISI-39 2-ISI-40 0 REACTOR VESSEL N0ZZLES -
0 REACTOR VESSEL HEAD WELD - - -
25A 2-ISI-41
"' REACTOR VESSEL SHELL WELDS 2-ISI-42 0 2-ISI-43 0 RC PUMP SEAL HOUSING BOLTING A&B - -
2-ISI-44 0 RC PUMP FLANCE BOLTING A&B - -
2-ISI-45 0 RC PUMP FLYWHEEL A&B - -
- - 6 2-ISI-46 0 EXCESS LETDOWN HEAT CL-1 EXCHANGER j 2-ISI-47 0 REACTOR VESSEL CLOSURE CL-1 HEAD CLAD PATCHES 2-ISI-48 0 REACTOR VESSEL CLAD -
CL-1 PATCH IDENTIFICATION e
4
_ _ - - ,y. - -, . ., .--- +. - - - , , - ,, _ ~. r .,. -. - ,- - - - - ,., - - _. -v__---- , >-- -e - - _ - - - - - - _ _ - - - - - - - - _ _ - - - - - - _ _
' - - - - - - - .2
+
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APPENDIX B ASME CLASS 2 -
EXAMINATIONS t
I I
i I
l l
l 9
e i
NORTHERN STATES POWER CO. TABLE S2.2.1 PRAIRIE ISLAND UNIT 2 PAGE 1 OF 5 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: prpT?rarncrwwwrTAr. nimP kHDS E. N DE I TION O INSP. R E Q'O. AMT. ITEM INSPECTION ITEM PER. AMT. GXAM BDENTIFICATION GORY ITEM TO 8E EXAMINED REPORT NO.
C2.1 C4 CIRCUMrERENTIAL BUIT hMDS MAIN SITAM A 32-2MS-1 - - -
MAIN STEAM B 32-2MS-2 - - -
MAIN SIEAM A 'IWO I -
30-2MS-1 'DIREE 1 -
MAIN SIEAM B - - -
30-2MS-2 MAIN STEAM A CNE 1 1 Mi-17 77-101,31 31-2MS-1 'IWD 1 -
MAIN STEAM B 31-2MS-2 - - -
MAIN STEAM A CNE 1 1 MS-188 77-99,15 RELIEF HDR., 30-2MS-1 MAIN STEAM B RELIEP HDR., 30-2MS-2 - - -
MAIN STEAM A 6-2MS-1 - - -
MAIN STEAM B 6-2MS-2 CNE 1 1 MS-113 77-96,37 FEEDWATER A 16-2FW-13 CNE 1 1 IW-161 77-45,55 16-2PW-12 'IWD -
3 IW-161 80-20,27,83,185 16-2FW-11 - - -
IW-174 80-18,31,84,160 FW-177 80-19,29,40,162 FEEDWATER B 16-2FW-16 'IMD -
1 Fw-133 80,21,38,41,161 16-2PW-15 GiB 1 1 FN-116 77-97,3
=== n n ene m..
PP9-B-11
NORTHERN STATES POWER CO. TABLE S2.2.1 PRAIRIE ISLAND UNIT ? PAGE ? OF S INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPIM3-CIRCUMFERFNPIAL BUTT WELDS
^M MPONE OR S M SUS hTE. D Dp INSP. R EQ'D. AMT. ITEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION R EPORT NO.
ITEM TO BE EXAMINED C2.1 C-G (CONP'D)
FEEDWATER A (8 in) 3-2AF-11 - - -
FEEDWATER B (8 in) 3-2AF-12 - - -
REFUELING NATER SIORAGE TANK DISCHARGE 14-2SI-1 'IWD 1 1 W-58 (Pt only) 79-41 12-2SI-3A 'IWO 1 1 W-60 79-83 12-2SI-3B - - -
12-2S-11 - - -
12-2S1-4 'IHREE 1 -
10-2S1-8 'IWO 1 1 W-68W 79-84 STREAM 1 'IHREE 1 -
srREAM 2 'IWO 2 2 W-88,289 79-77, 76 CONTAINMENT SUMP B DISCHARGE LINES 14-2SI-33A - - -
14-2SI-33B - - -
12-2SI-34A- 'IWO 1 1 W-17 79-25 12-2SI-34B 'IWD 1 1 W-5 79-26 12-2RH-6A - - -
12-2RH-6B - - -
renen n.sen ene venen no. eoe-s ees PP!HF-12 Q y - - -.w-- - , -
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NORTHERN STATES POWER CO. TABLE S221 PRAIRIE ISLAND UNIT 2 PAGE a OF s INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: PTPTW,-CTRff MFFRFNPT AT. Rf 7PP 1mTlIE N
SUS INSP. R EQ'O. AMT. ITEM INSPECTION ITEM E- N DE IPTl N GORY ITEM TO BE EXAMINED PER. M. EXAM IDEN M8 W ION RENT NO.
C2.1 C-G (CONr'D)
ACCUPULATOR DISGARGE LINES .
12-2SI-28A - - -
12-2SI-288 - - -
12-2SI-29A - - -
12-2SI-29B OE 1 1 SI-316 77-49 C2.1 C-F RESIDUAL HEAT RDOVAL DISGARGE 10-2RH-11 ole 1 1 E-294 77-33
'IWO 1 1 W-176 79-30
'DIREE 1 -
6-2RH-12 'IWO 1 -
6-2S1-10B '!HREE 1 -
RESIDUAL IFAT RDOVAL SUCTIN 12-2RH-5A TWO 1 1 W-105 79-27 12-2M-5B TWO 1 1 W-142 79-47,50 8-2RH-4A 7WD 1 1 W-100 79-68 B-2M-4B 'DIREE 1 -
10-2M-3 CNE 2 2 m-255,RH-256 77-50,51 TWO 2 2 W-225,226 79-28,29
'IHREE 2 -
8-2RH-5A 7WO 1 1 W-104 79-69 8-22-5B TND 1 1 W-138 79-64 n e4n ene ro = = . ..-i .
PP9-B-14
l ., .. .. .
- _ NORTHERN STATES POWER CO. TABLE S2.2.1 PRAIRIE ISLAND UNIT ') PAGE 5 OF 5 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPIM'rCIROMFERINEAL BUIT WEIIS SUB 8 E. N E i Tl N0 INSP. REO D. AMT. ITEM INSPECTION ITEM PER. AMT. EXAM IDENTIFICATION REPORT NO.
GORY ITEM TO BE EXAMINED C2.1 C-F (CONT'D)
IEACIOR VESSEL SAEEtY INJECTION 6-2S1-25A OiE 1 1 SI-332 77-52
'IWO l' -
DIREE 1 -
6-2SI-258 OiE 1 1 SI-26 77-46A e
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NORTHERN STATES POWER CO. TABLE S2.2.5 PRAIRIE ISLAND UNIT 2 3 PAGE 1 OF INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPDG-INIEGRALLY WEILED SUP10RIS SU8 ^ "
" hTE- N 0E BPTl N O INSP. R EQ~D. AMT. ITEM INSPECTION GORY ITEM TO BE EXAMINED R. MT. EXM IDE WIFICATION R EN NO.
C2.5 C-E-1 INITERAILY hEDED SUPPORIS MAIN SIEAM A 'D O 2 -
30-2MS-1 'IEREE 2 -
MAIN STEAM B OIE 1 1 I 77-147 30-2MS-2 'IWO 2 -
'IHREE 2 -
MAIN SPEAM A GiE 3 3 J,K,M 77-154,140 31-2MS-1 'IWO I -
MAIN STEAM B 31-2MS-2 'IHREE 2 -
MAIN STEAM A 30-2MS-1 (R-IER) 'IHREE 1 -
MAINSTEAM B 30-2MS-2 (R-HDR) - - -
MAIN SIEAM A 6-2MS-1 - - -
79LIN STEAM B 6-2MS-2 QE 1 1 P 77-103 PEEDNMER A 16-2FW-13 OIE 1 1 K 77-105 16-2FW-12 'IWO 10 10 A 80-5,5R,32 16-2PW-11 B,C 80-2,33,6,62 E,P 80-1,28,68,63 H,I 80-67,61,66,59 J 80-77,60 K 80-3,3R,44 L 80-8,26
'IEREE 3 -
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PP9-o-19 O
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NORTHERN STATES POWER CO. TABLE S2.2.5 PRAIRIE ISLAND UNIT 2 PAGE 2 op 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING-INIEGRALLY WEIDED SUPIORIS
- SUS INSP. R EQ'O. AMT. ITEM 1NSPECTION ITEM TE. N DE RI Tl NO GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION R EPORT NO.
C2.5 C-E-1 (00Nr'D)
FEEDWATER B 16-2FW-16 WE 2 2 G,H 77-104,148 16-2EW-15 'IWO 8 8 A 80-16,16R B,C,D,E,F 80-9,10,42,74 G 80-11,11R H 80-12
'DIREE 1 -
REFUELING WATER SIORAGE TANK DISCHARGE 12-2SI-4 'IWO 1 1 C 79-42,34 00NEAIMIENr SUMP B DISCHARGE LINES 12-2SI-33A - - -
12-2SI-33B - - -
SAFErY IRTECTION REP NO. 21 SUCTION BRANCH 1 p 6-2RH-10A CNE 1 1 B 77-119 BRAN 01 2 6-2RH-10A QE 1 1 G 77-119 SAFETY IR7BCTION RMP NO. 22 SUCTICN BRANCH I 6-2RH-10B 'INO 1 1 D 79-35,38,38R BRANQi 2 6-2RH-10B 'IHREE 1 -
RESIDUAL HEAT REMOVAL SUCTION PUMP A 8-2RH-4A 'INO 1 1 A 79-19,44 co.u n. n ene ro = . ... .
PP9-B-20
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SUMMARY
MAJOR ITEM: pTpTm-ww wrrsn c:noposrrs
^ "
SUS ITEM $T- N DE le i N O
INSP.
PER.
R EU'D.
AMT.
AMT.
EXAM ITEM IDENTIFICATION INSPECTION GORY ITEM TO BE EXAMINED REPORT NO.
C2.6 C-E-2 SUPPORT COMPONENIS P9LIN SPEAM A 31-2MS-1 'INO I -
MAIN SPEAM B 31-2MS-2 'IHREE 1 -
MAIN STEAM A 30-2MS-1 'IWO I -
MAIN STEAM B 30-2MS-2 'IHREE 1 -
MAIN SPEAM A RELIEF HDR., 30-2MS-1 CNE 1 1 O 77- 140 MAIN SPEAM B RELIEF HDR., 30-2MS-2 'IND 1 -
EEEDIOGER A 16-2EW-13 'INO 2 2 D,G 80-4,69
'1HREE 1 -
REPUELING )@GER SIORAGE 'IRNK DISCHARCE 12-2S1-4 'IMO 1 1 B 79-45 roness7-a47s e/7e rones peo.ess-seen PP9-B-22
.. .. .. a NORTHERN STATES POWER CO. TABLE S2.2.6 PRAIRIE ISLAND UNIT 2 PAGE 2 op 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: PIPING-NW WEIDED SUPPORTS SUB N 8 E- DE R1 T N INSP. REOTL AMT. ITEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION REPORT NO.
ITEM TO BE EXAMINED C2.6 C-E-2 (00Nf'D) 10-2SI-8 BRANCH 1 DIREE 1 -
BRANCH 2 - - -
SAFEIT INJECTION PUMP NO. 21 SUCTICN BRANCH I ,
6-2RH-10A - - -
-tDE-ERANCH 2 6-2RH-10A 'IND 1 1 E 79-46
'IHREE 1 -
SAEEfY INJECTION RMP NO. 22 SUCTION BRANCH 1 6-2RH-10B - - -
-10NE-BRANCH 2 6-2RH-10B 'INO 1 1 A 79-33,33R HIREE 1 -
RESIDUAL HEAT RIMNAL DISCHARGE PUMP A 6-2BH-12 CNE 1 1 M 77-136 R]MP B 6-2SI-10B - - -
RESIDUAL HEAT REMOVAL SUCfION PLMP B 10-2Rft-3 CNE 2 2 A,B 77-155
'IMD 1 1 F 79-9
'IHREE 2 -
RMP A B-2RH-4A TWO 1 1 B 79-18 RIG B 8-2RH-4B TIREE 1 -
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MRt1IERN STATES POWER COMPANY TABLE II PRAIRIE ISTAND UNIT 2 PAGE 1 0F 4 4
BASELINE C(DIPARISON
SUMMARY
COMPONENT / SYSTEM NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION ISO METHOD _ IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS C2.1 CIRCUMFERENTIAL BUTT WELDS FEEDWATER A 48A UT W-161 80-83 77-45,55 3-1, ROOT GEO,75% NONE 16-2W-13 NONE S-1, TAPER GEO,75% NONE UT 80-20 N/A NONE NONE MT 80-27 N/A NONE NONE RT 80-185 NONE NONE NONE 48A UT W-174 80-84 N/A S-2, OD GEO, 75% NONE
, 80-18 N/A NONE NONE MT 80-31 N/A NONE NONE RT 80-160 NONE NONE NONE 48A UT W-177 80-40 N/A S-1, ID GEO, 50%
- S-1, OD GEO, 60%
S-2, OD GEO, 50%
UT 80-19 N/A NONE NONE MT 80-29 N/A NONE NONE RT 80-162 NONE NONE NONE 48A UT W-175 TO 80-153 N/A 5-1. ID GEO,W177 ALL SCANS LIMITED W-177 S-2, VENT ID, 50% BY SWEEP-O-LET, UT BASE 80-24 N/A NONE GAMMA PLUG & VENT METAL 48A MT W-175 TO 80-30 N/A NONE LIMITED BY GAMMA W-177 PLUG, VENT & SWEEP-BASE METAL O-LET.
RT 80-163 N/A NONE LIMITED BY CAmfA PLUG, VENT & SWEEP-0-LET FEEDWATER B 49A UT W-133 80-41 N/A NONE NONE
+
UT 80-21 N/A NONE NONE Mr 80-38 N/A 9 LINEAR NONE P0sM NO. ISI-1003
3 D T T 0 E ,N N 0 4 T E E T 1 NS ITV V N -
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I AM N CE E - M E - NN N. NN NN NN NN 2 XI SWATPM TPA M EL SMIEA I EM R L MMEG MEM O E LYAIW IWA F LE ABGLS& LSG BG AA TP S S N % N S O 0 O N I 5 I
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M RTEERN STATES POWER COMPANT TABLE II PRAIRIE ISLAND UNIT 2 PAGE 3 0F 4
,i BASELINE COMPARISON
SUMMARY
l l NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD _ IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS C2.5 CONT'D FEEDWATER A 48A VT WH-71 80-67 N/A NONE NONE MT H 80-61 N/A NONE NONE VT WH-75 80-66 N/A NONE NONE MT I 80-59 N/A NONE NONE VT FWH-60 80-77 N/A NONE NONE MT J 80-60 N/A NONE NONE VT FWH-58 80-3 77-105 NONE MISSING NUT NONE K 80-3R NONE-NUT REPLACED MT 80-44 77-105 NONE NONE NONE VT WH-53 80-8 N/A NONE NONE MT L 80-26 N/A NONE NONE FEEDWATER B 49A VT WH-67 80-16 N/A LOOSE NUTS ALL SUPPORTS WERE i A 80-16R NONEiNUTS EXAMINED TO EXTENT TIGHTENED POSSIBLE, DUE TO VT WH-65,B 80-9 N/A NONE ENCAPSULATION VT FWH-64,C 80-10 N/A NONE -
VT WH-69,D 80-42 N/A NONE VT WH-63,E 80-42 N/A NONE VT WH-62,F 80-74 N/A NONE VT FWH-59,G 80-11 77-104 NONE NUT NOT FLUSH 80-11R 90NE* NUTS -
TIGHTENED -
VT WH-54,H 80-12 77-148 NONE NONE 1
C2.6 SUPPORT COMPONENTS FEEDWATER A 48A VT WH-72,D 80-4 N/A NONE NONE VT WH-74,G 80-69 N/A NONE NONE FOUM NO. ISI-1003
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- Table III l ERIHERN STATES PCWER CO. PAGE 1 0F 3 l PRAIRIE ISLAND INIT 2
! ISOGTRIC SLSNARY - CLASS 2 NSP ISO LINE LINE LTT - CAL' REVISICN COMPONENT OR SYSTEM IDOP NLNBER SIZE NLFBER STANDARD 2-ISI-37 0 STEAM GENERATORS A6B - -
NO26 2-ISI-46 0 MAIN STEAM (CENERAL VIEW) A - - -
2-ISI-46A 0 A 32" 32-2MS-1 NO.
2-ISI-46B 0 A 31" 31-2MS-1 24 30" 30-2MS-1 23 6" 6-2MS-1 7 2-ISI-47 0 MAIN STEAM (GENERAL VIEW) B - - -
2-ISI-47A 0 B 32" 32-2MS-2 NO.
2-ISI-47B 0 B 31" 31-2MS-2 24 30" 30-2MS-2 23 6" 6-2MS-2 7 2-ISI-48 0 FEEDWATER (CENERAL VIEW) A - - -
2-ISI-48A 0 A 16" 16-2W-13 13f 36 2-ISI-48B 0 A 16" 16-2 W-12 13 16" 16-2W-11 13 8" 3-2AF-11 NO.
2-ISI-49 0 FEEDWATER (CENERAL VIEW) B - - -
2-ISI-49A 0 B 16" 16-2W-16 13/36 2-ISI-49B 0 B 16" 16-2W-15 13 8" 3-2AF-12 NO.
2-ISI-50 0 RHR PUMP B SUCTION (WELDS) B 10" 10-2RH-3 22 2-ISI-51 0 RHR PUMP B SUCTION (HANGERS) B 8" 8-2RH-4B NO .2H_.
B 8" 8-2RH-5B NO .2H__
B 12" 12-2RH-5B No .32__
10" 10-2SI-9B B NO .22__
2-ISI-52 0 RHR PUMP A SUCTION (WELDS) A 8" 8-2RH-4A NO.fo 2-ISI-53 0 RRR ? UMP A SUCTION (HANGERS) A 8" 8-2RH-5A NO .gg__
A 12" 12-2RH-5A NO. o A 10" 10-2SI-9A - NO.22__
. _ - . _ _ . . _ _, _._ _ . _ . - _ . ~, _ __ _ _ _ . _ _ .. _ _ _ _ _ __ , . _ _ . _ .__
NRIHERN STATES POWER CD. p{* 1*d2 PRAIRIE ISIAND UNIT 2 0F 3 ISOETRIC S3 NARY - CLASS 2 REVISICN CXNPONENT OR SYSTD1 IDOP h IB R Ah 2-ISI-54 0 RHR PUMP B DISCHARGE (WELDS) B 8" 8-2RH-7B NO.29 2-ISI-55 0 RHR PUMP B DISCHARGE (HANGERS) B 8" 8-2RH-9B NO.T B 6" 6-2SI-10B NO.2/
2-ISI-56
~
0 RHR PUMP A DISCHARGE (WELDS) A 8" 8-2RH-7A NO.29 2-ISI-57 0 RHR PUMP A DISCHARGE (HANGERS) A 8" 8-2RH-9A NO.T "
A 10" 10-2RH-ll 22 A 6" 6-2RH-12 NO.27 2-ISI-58 0 CONTAINMENT SUMP B DISCHARGE (WELDS) B 12" 12-2RH-6B NO.32 2-13I-59 0 CONTAINMENT SUMP B DISCHARGE (HANGERS) B 14" 14-2SI-33B NO.
B 12" 12-2SI-34B NO.
2-ISI-60 0 CONTAINMENT SUMP B DISCHARGE (WELDS) A 12" 12-2RH-6A NO.32 2-ISI-61 0 CONTAINMENT SUMP B DISCHARGE (HANGERS) A 14" 14-2SI-33A NO.
A 12" 12-2SI-34A NO.
2-ISI 0 SAFETY INJECTION PUMP 22 SUCTION (WELDS) B 6" 6-2RH-10B NO.27 2-ISI-63 0 SAFETY INJECTION PUMP 22 SUCTION (HANGERS) 2-15I-64 0 SAFETY INJECTION PUMP 21 SUCTION (WELDS) A 6" 6-2RH-10A NO.27 2-ISI 0 SAFETY INJECTION PUMP 21 SUCTION (HANGERS) 2-ISI-66 0 REFUELING WATER STORAGE (WELDS) -
14" 14-2SI-1 NO.
TANK DISCHARGE 12" 12-2SI-3A NO.JJ 2-ISI-67 0 REFUELING WATER STORAGE (HANGERS) 12" 12-2SI-3B NO.T TANK DISCHARGE 12" 12-2SI-4 NO.33 10" 10-2SI-8 NO.31 12" 12-2SI-11 NO.33 2-ISI-68 0 BORIC ACID SUPPLY TO (WELDS) - 6" 6-2SI-13A NO.28 SAFETY INJECTION 6" 6-2SI-13B NO.28 2-ISI-69 0 BORIC ACID SUPPLY TO (HANGERS) 8" 8-2SI-17 NO.30 SAFETY INJECTION 8" 8-2SI-18 NO.30
.m.-
Table III -
M STATES POWER 00. PAE 3 0F 3 PRAIRIE ISLAND INIT 2 ISCNETRIC SibMARY - CLASS 2 REVISI(N COMPONENT OR SYSTD1 If0P h R AND 2-ISI-70 0 REACTOR VESSEL SAFETY INJECTION (WELDS) B 6" 6-2SI-25B 6 2-ISI 0 REACTOR VESSEL SAFETY INJECTION (HANGERS) 2-ISI-72 0 REACTOR VESSEL SAFETY INJECTION (WELDS) A 6" 6-2SI-25A 6 2-ISI-73 0 REACTOR VESSEL SAFETY INJECTION (HANGERS) 2-ISI-74 0 BORIC ACID SUPPLY (WELDS) -
8" 8-2SI-18 NO.30
- 2-ISI-75 0 ACCUMULATOR DISCHARGE (WELDS) A 12" 12-2SI-28A 11 4
2-ISI-76 0 ACCUMULATOR DISCHARGE (HANGERS) 12" 12-2SI-29A 11 B 12" 12-2SI-28B 11 l 12" 12-2SI-29B 11
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SEISMIC BOLTING EXAMINATION i l
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NORTHERN STATES POWER CO. TABLE SB PRAIRIE ISLAND UNIT 2 PAGE l OF D INSERVICE INSPECTION-EXAMINATION
SUMMARY
M AJOR ITEM: MASMIC BOLnNU M M SUB ITEM $^E. N DE Tl N INSP.
PER.
R EQ'D.
AMT.
AMT.
EXAM ITEM IDENTIFICATION INSPECTION GORY ITEM TO BE EXAMINED REPORT NO.
WA WA STEAM GENERA'IORS STEAM GENERA'IOR 10. 21 UPPER RING GIRDER CNE 2 2 SNUEER 1 77-72 (SNUBBER PINS) 'INO 2' 2 SNUBBER 2 80-180
'mREE 4 -
UPPER RI E GIRDER CNE 5 5 'IOP ROW 77-143 (SNUBBER WALL BOLTS) 'INO 5 5 CENTER ION 80-1 M
'mREE 5 -
~
UPPER RING GIRDER CNE 8 8 'IOP ROW ON GIRDER 77-143 (SNUBBER BOLTS) 'IW 8 8 'IDP ROW ON WALL 80-176
'mREE 16 -
UPPER RING GIRDER CNE 10 10 RING CON. 2 77-159 (RING CONNECT BOLTS) 'IWO 10 10 RING CON. 1 80-110
'IHREE 20 -
UPPER RING GIRDER CNE 10 10 10 EXAMINED 77-159 (RING WPLL BOLTS) 'INO 10 10 10 EUMINED 80-110
'mREE 10 -
(REPEAT INSP.)
COI M PINS CNE 2 2 Bar CDL 1/IOP COL 4 77-69,70
'IWO 2 2 BOT & 'IOP CDL 2 80-182
'mREE 4 -
BASE ANCHOR BOLTS CNE 8 8 BASE OP 00CM 1 77-143
'INO 8 8 BASE CP CIXM 2 80-106
'mRES 16 -
TOP CDIM CNE 4 4 'IOPOP00tm 1 77-165 CINiECTING BOLTS 'IWO 4 4 'IOP OF 00[Ulti 2 80-173 THREE 8 -
con = n. n ene ro== no... -ie.
M .. . . . . . _ _ _ _ _ _ _ - - _ _ _ - - _ _ - . _ _ - _ _ _ _
SB TA!LE -
NORTHERN STATES UNIT POW {R CO. #
PRAIRIE ISLAND INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM:
PAGE " " g " "'
SUB
" " E M E. N DESCRI T1 N INSP. R EQ*D. AMT. BTEM INSPECTION ITEM GORY PER. AMT. EXAM IDENTIFICATION R EPORT NO.
ITEM TO BE EXAMINED N/A N/A (S.G. NO. 21 CDNT'D)
SUPPORT PAD CNE 6 6 00 m 1 77-62 IELI-COIL SCREWS 'IWO 6 6 CDN 2 80-183
'IHREE 12 -
STEAM GENERA'IOR NO. 22 UPPER RING GIRDER CNE 2 2 SNUBBER 1 77-71 (SNUBBER PINS) 'INO 2 2 SNUBBER 2 80-180
'IEREE 4 -
UPPER RING GIRDER CNE 5 5 '10P ROW 77-142 (SNUBBER WALL BOLTS) 'IWO 5 5 CENIER EDW 80-111
'IHREE 5 -
UPPER RING GIRDER OE 8 8 '10P ICW ON GIRDER 77-142 (SNUBBER BOLTS) 'IWO 8 8 '10P ROW ON WALL 80-112
'IHREE 16 -
UPPER RING GIRDER CNE 10 10 RING CON. 4 77-160 (RING CONNECP BOLTS) 'INO 10 10 RING O N. I 80-111 EREE 20 -
UPPER RING GIRDER CNE 10 10 10 EXAMINED 77-160 (RING WALL BOLTS) 'IND 10 10 10 EXAMINED 80-111 EREE 10 -
(REPEAT INSP.)
CDIIMN PI!E GE 2 2 CON 1 77-65
'1WD 2 2 CDws 2 80-182
'IHREE 4 -
BASE ANCHOR BOLTS CNE 8 8 BASE OF CDwm 1 77-160
'IWD 8 8 BASE OP 00 m 2 80-106
'IHREE 16 -
romu p-seys etre romm wo. ese-seet
NORTHERN STATES POWER CO. TABLE SB PRAIRIE ISLAND UNIT 2 PAGE 3 OF 3 INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM: seasMIC BounrKi SUS 88 AMT.
E- N DE I T10 INSP. R EQ'D. ITEM INSPECTION I
GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
WA WA (S.G. NO. 22 CDNT'D) 20P 00N CNE 4 4 TOP OF CO[ Dei 1 77-165 OCNECTING BOLTS TWO 4 4 'IOP OF CIXUm 2 80-113
'IHREE 8 -
SUPPORP PAD . CNE 6 6 00tD M 1 77-61 HELI-CDIL SCRENS IWO 6 6 00HM4 2 80-184
'ElREE 12 -
PRESSURIZER BASE ANCHOR BOLTS CNE 8 8 1-8 BOLTS77-146 TWO 8 8 9-16 BOLTS80-114
'IHREE 8 -
ACOLMEATOR A
- BASE ANCHOR BOLTS GE 8 8 1-6 BOLTS77-141
'IND 8 8 9-16 BOLTS 8 & 115
'IHREE 8 -
ACC(MHATOR B BASE ANCHOR BOLTS CRE 8 8 1-8 BOLTS77-141 TWO 8 8 9-16 BOLTS80-115
'IHREE 8 -
WA -
WA REAC10R 000EJWP PLMPS PLMP NO. 21 CDU M4 PIl6 CNE 2 2 000tMi 1 77-67 TWO 2 2 00Emei 2 80-181
'IHREE 2 -
comm n-u n ene room . isi-see
.______m. __ . . . . _ _ _ _ _ . . . . . _ . . . . . _ _ . . _ _ . _ - _ - . - _ _ . - .. .. . . . .
NORTHERN STATES POWER CO. TA2LE SB 2 4 PRAIRIE ISLAND UNIT INSERVICE INSPECTION-EXAMINATION
SUMMARY
MAJOR ITEM:
PAGE **C gM*D M N E SU8 INSP. R EQ'D. AMT. ITEM INS *ECTION ITEM E. DE RI Tl N GORY ITEM TO BE EXAMINED PER. AMT. EXAM IDENTIFICATION REPORT NO.
N/A. N/A (PUMP 10. 21. CONT'D)
BASE AN W OR BOLTS OE 8 8 BASE W (YYIBei 1 77-158 TWO 8 8 BASE T 00witi 2 80-107 THREE 8 -
CDIIRE C0ttiECTING QE 6 6 TOP OP 00 WIN 1 77-163 BOLTS '50 6 6 TOP OF 00mpel 2 80-174 THREE 6 -
TIE BACK BOLTS 04E 1 1 PAD 1 77-77 7WO 1 1 PAD 2 80-179 UHREE 1 TIE BACK PINS CNE 1 1 PAD 1 77-68 UNO 1 1 PAD 2 80-186
'IHREE 1 -
THROUGH ANWOR CNE 2 2 PAD 1, SOUIH 2 77-161 BOLTS Tv0 2 2 PAD 1, CENTER 2 80-175
'!HREE 2 -
IATERAL SUPPORT AND CNE 4 4 PAD 2 77-158 l WALL BOLTS TWO 3 3 PAD 3, TOP BOW 80-175 I THREE 3 -
PUMP NO. 22 (YYIBei PINS OiB 2 2 00WIM 1 77-64 TWO 2 2 CDwpH 2 80-181
'IHREE 2 -
BASE ANCHOR BOLTS OtE 8 8 BASE T 00WDM 1 77-161 TWD 8 8 BASE & CDwpW 2 80-107
'IHREE 8 -
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A P S BL TT O I AS OB E A P S S R T N CC B P BT T HS R EDA N I R UA G W E R WS T E R WS NW EE L TNP E E 0T S NN L N 2O 2N 2E N E 0T AAM N L N M #R E B RL O E B RL N NN L #B #I C G B O TLO O B G B O WO OO A U T RB SSC P U RB O CC W L NR NC NS U I M E RS O MO ME M M N E N E C M N UN UL A S TL O I A S TL T GG G C UH E NL REN C M E NL PL NN N LC LN LI EA EII S T 2 EA OO II I 2 ON OO OO T 2 HRL I S # CW TB RR R # CA CC CC S # CW TIE E RAS S 0RA 0 PB 1
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NORTHERN STATES POWER COMPANT TABLE II PRAIRIE ISLAND UNIT 2 PAGE 2 0F 4 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE EXAMINATION COMPONENT / SYSTEM ISO METHOD _ IDENT. NO. INDICATIONS INDICN/ W ., T. IMITATIONS TOP ROW SNUBBER 86 VT 8-BOLTS80-112 NONE NONE NONE BOLTS ON WALL RING CONNECTING BOLTS 85 VT 10-BOLTS80-111 NONE NONE NONE RING CONNECTION #1 RING WALL BOLTS 85 VT 10-BOLTS80-111 NONE NONE NONE
- 2 COLUMN PINS 77 UT BOT-PIN 80-182 NONE NONE NONE 78 UT TOP-PIN 80-182 NONE NONE NONE COLUMN #2 BASE 77 VT 8-BCLTS 80-1.06 NONE NONE NONE ANCHOR BOLTS COLUMN #2 TOP 87 VT 4-BOLTS80-113 NONE NONE NONE l
COMNECTING BOLTS COLUMN #2 HELI 87 UT 6-SCREWS80-184 NONE NONE NONE COIL SCREWS PRESSURIZER BASE ANCHOR BOLTS 88 VT 8-BOLTS80-114 NONE NONE NONE ACCUMULATOR A BASE ANCHOR BOLTS 89 VT 8-BOLTS80-115 NONE NONE NONE ACCUMULATOR B BASE ANCHOR BOLTS 89 VT 8-BOLTS80-115 NONE NONE NONE REACTOR COOIANT PUMP #21 79 UT BOT-PIN 80-181 NONE NONE NONE
_ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ J N TJEIL_T08 l M 31
i NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 3 0F 4 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS COLUMN #2 BASE 79 VT 8-BOLTS80-107 NONE NONE NONE ANCl10R BOLTS COLUMN #2 CONNECTING 80 VT 6-BOLTS80-174 NONE NONE NONE BOLTS COLUMN #2 TIE 84 UT 1-BOLTS80-179 NONE NONE NONE BACK BOLTS COLUMN #2 TIE 84 UT 1-PIN 80-186 NONE NONE NONE BACK PINS PAD #1 CENTER PAIR 84 VT 2-BOLTS80-175 NONE NONE NONE THROUGH ANCHOR BOLTS PAD #3 TOP ROW 84 VT 3-BOLTS80-175 NONE NONE NONE LAT'L SUPPORT AND WALL BOLTS REACTOR COOLANT PUMP #22
- 2 COLUMN PINS 79 UT BOT-PIN 80-181 NONE NONE NONE 80 UT TOP-PIN 80-181 NONE NONE NONE COLUMN #2 BASE 79 VT 8-BOLTS80-107 NONE NONE NONE ANCHOR BOLTS 80 VT 6-BOLTS80-108 NONE NONE NONE COLUMN #2 CONNECTING BOLTS 81 UT 1-BOLT 80-179 NONE NONE NONE COLUMN #2 TIE BACK BOLTS 81 UT 1-PIN 80-196 NONE NONE NONE COLUMN #2 TIE BACK PINS FaVCU3bkRK-BMIM
- n. l- .. .
NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT 2 PAGE 4 0F 4 BASELINE COMPARISON
SUMMARY
NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENT. NO. INDICATIONS INDICATIONS LIMITATIONS PAD #1 CENTER PAIR 81 VT 2-BOLTS80-109 NONE 3 NUTS NOT FLUSH NONE THROUGH ANCHOR BOLTS 80-109P NONE NUTS TIGHTENED NONE PAD #3 TOP R0W 81 VT 3-BOLTS80-109 2 MISSING NONE NONE LAT'L SUPPORTS AND 1 LOOSE WALL BOLTS l
l
_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ . -_ _ _ XGZ1 GEL E9E-lE03 _ _ _ _
,. *= .. .
Table III N STATES N 00. PAE I 0F I PRAIRIE ISIAND LNIT 2 ISO 4ETRIC SLM4ARY - SEISMIC BOLTING AUCMENTED NSP ISO LINE LINE LTT - CAL.
REVISICN COMPONENT OR SYSTB1 100P NtNBER SIZE NLNBER STANDARD 2-1S1-77 0 STEAM CENERATOR SUPPORT BASE A&B -
4/CENERATOR -
2-ISI-78 0 STEAM GENERATOR SUPPORT TOP A&B -
4/CENERATOR -
, 2-ISI-79 0 REACTOR COOLANT PUMP SUPPORT BASE A&B -
3/ PUMP -
2-ISI-80 0 REACTOR COOLANT PUMP SUPPORT TOP A&B -
3/ PUMP -
2-ISI-81 0 R.C. PUMP #22 LOh'ER LATERAL SUPPORT B - - -
2-ISI-84 0 R.C. PUMP #21 LOWER LATERAL SUPPORT A - - -
2-ISI-85 0 STEAM CENERATOR UPPER SUPPORT A&B - - -
2-ISI-86 0 STEAM GENERATOR UPPER SUPPORT SNUBBERS A&B - - -
2-ISI-87 0 STEAM CENERATOR SUPPORT PAD A&B -
4/CENERATOR -
2-ISI-88 0 PRESSURIZER BASE - - - -
2-ISI-89 0 ACCUMULATOR BASE A&B - - -
e
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APPENDIX E 1 TABLE I -
PERSONNEL LISTING TABLE II -
ULTRASONIC CALIBRATION BLOCKS TABLE III -
PROCEDURE LISTING TABLE IV -
EQUIPMENT AND MATERIALS
.\
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NORTilERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND - UNIT 2 TABLE I PERSONNEL LISTING PAGE 1 of 2 EXAMINER TITLE ORGANIZATION ASNT LEVEL UT PT MT VT ET RT l M E GUSTELY TECHNICIAN LMT(3) -- -
II -- - -
D A IIALL TECIINICIAN LMT .I -- -- -- -- -
R A KELLERHALL TECHNICIAN LMT II II II II(2b)-- --
'. R W PECHACEK TECHNICIAN LMT II II -
II(2b)-- --
E L THOMAS SUPERVISOR I11T III III III III I --
(2a,b)
. W M TIGHE TECHNICIAN LMT I -- -- -- -- -
C L BROWN TECHNICIAN PTS (4) - -- -- -- -- II !
R GROSS TECllNICIAN PTS -- -- - - --
(1)
L HARSTON TECHNICIAN PTS - -- - - -
II K MARTINSON TECHNICIAN PTS -- -- - -- -- II V A OLSON TECHNICIAN PTS -- -- -- - - I i
S J BEEHNER TECHNICIAN W(5) __ __ __ _ y _
l P E BUKES TECHNICIAN W -- - - IIA - -
J J DUCAR TECHNICIAN W - - -- -
II --
J ESTEL TECHNICIAN W -- - - --
II -
G J FERENCHAK TECHNICIAN W - -- - - II -
R P HAZEN TECHNICIAN W - -- - -
II --
R H INGRAHAM SUPERVISOR W - - - -- III -
L W LUNDEN TECHNICIAN W - -- -- --
I -
J E MILLS TECHNICIAN W - - - -
I -
R A VOLLMER TECHNICIAN W -- -- - --
I -
T J WESTCOAT TECHNICIAN W - - -- --
I --
r E O MC KEE EVALUATOR ZETEC( ) -- -- -- --
IIA -
6 i
NORTHERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND - UNIT 2 TABLE T PERSONNEL LISTING __PAGE 2 of 2 CONTINUED EXAMINER TITLE ORGANIZATION ASNT LEVEI,,
UT PT MT - VT ET RT L C DAHLMAN M&SP SPECIALIST NSP D B HANSEN ASST M&SP NSP III II II II(2a,b)
ENGINEER
- P J KRUMPOS SUPT M&SP NSP
'. J WILLIAMS ANII HARTFORD STEAM BOILER INSIECTION
& INSURANCE CO FOOTNOTES:
(1) LEVEL I TRAINEE (2a) CERTIFIED BY NORTHERN STATES POWER COMPANY TO PERFORM VISUAL DETER-MINATION OF STRUCURAL INTEGRITY FOR HANGER ASSEMBLIES IN ACCORDANCE WITH PROCEDURE NSP-VT-2.
(2b) INSPECTION EXPERIENCE AND NDE QUALIFICATIONS WERE JUDGED TO BE ADEQUATE TO PERFORM VISUAL EXAMINATIONS IN ACCORDANCE WITH NSP-VT-1.
(3) ORGANIZATION: LAMBERT, MAC GILL, THOMAS, INC. (LMT).
771 BROKAW ROAD SAN JOSE, CA 95112 (4) ORGANIZATION: PEABODY TESTING SERVICE (PTS) 1920 OAKCREST SUITE 5 ROSEVILLE, MN 55113 (5) ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION (W)
NUCLEAR SERVICES DIVISION P.O. BOX 2728 PITTSBURGH, PA 15230 1
(6) ORGANIZATION: ZETEC
, P.O. BOX 140 e ISSAQUAH, WA 98027
__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___o
1 ,
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o A - 4 898 17 18 44 45 5511 D 781 - - - - - -
- - - - - - - - - - - - 1111 -
111 111 11 11 11 11 -
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APPENDIX E NORTHERN STATES POWER COMPANY PRAIRIE ISLAND - UNIT TABLE III PTSCEDURE LISTING PAGE 1 of 2 PROCEDURE NUMBER FIELD PROCEDURE TITLE PLANT APPROVAL FIELD CHANGE CHANGE DESCRIPTION AND REVISION CHANGE DATE REMARKS NSP-VT-1, REV. 1 NONE VISUAL EXAMINATION 4-4-79 NONE NSF-VT-2, REV. 2 NONE VISUAL EXAMINATION OF 4-4-79 NONE ASSEMBLED HANGER ASSEMBLIES NSP-PT-1, REV. 1 NONE LIQUID PENETRANT 4-4-79 NONE EXAMINATION NSP-MT-1. REV 1 NONE MAGNETIC PARTICLE EXAMINA- 4-4-79 NONE TION, YOKE METHOD NSP-UT-1, REV. O NONE ULTRASONIC EXAMINATION OF 4-4-79 NONE PIPE WELDS NSP-UT-2, REV. O NONE AUTOMATIC. DATA RECORDING 4-4-79 NONE NSP-UT-4, REV. 0 ' NONE ULTRASONIC EXAMINATION OF 4-4-79 NONE STUDS AND BOLTS NSP-UT-12, REV. O NONE ULTRASONIC EXAMINATION OF 4-4-79 NONE REACTOR COOLANT PUMP FLYWHEELS PEABODY TESTING 3.20.A.1-3, REV. 0 1 RADIOGRAPHIC EXAMINATION 12-31-79 NONE FIELD CHANGE INCLUDED TO OF WELDS COMPLY WITH 2T PENETRAMETER SENSITIVITY REQUIREMENTS OF IE BULLETIN NO. 79-13 &
CLARIFY PERSONNEL REQUIRE-MENTS.
- -- v -- - - - w. -v -w-- _,,v--- - -
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EORTHERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND - UNIT TABLE III PROCEDURE LISTING PAGE 2 of 2 PROCEDURE NUMBER FIELD PROCEDURE TITLE PLANT APPROVAL FIELD CHANGE CHANGE DESCRIPTION AND REVISION CHANGE DATE REMARKS WESTINGHOUSE ISI-88, REV. 1 NONE REMOTE VISUAL EXAMINATION 12-31-79 NONE OF REACTOR VESSEL INTER-NALS INSPECTION PROGRAM NONE INSPECTION PROGRAM PLAN 12-31-79 NONE PLAN REV. 1 2-27-79 WMF-95050-P-001, NONE INSTRUCTIONS FOR VIDEO 12-31-79 NONE REV. 1 TAPE DUBBING IWMF-95050-P-003 NONE UNDERWATER TELEVISION 12-31-79 NONE REV. 1 SYSTEM SET UP AND OPERATING INSTRUCIIONS FOR CUSTOMER SITE WMF-95050-P-004, NONE INSTRUCTIONS FOR WESTING- 12-31-79 NONE REV O HOUSE UNDERWATER MINIATURE CCTV SYSTEM, MODEL ETV 1250 MKS 2.4.2 GEN-23 NONE MULTI-FREQUENCY EDDY 12-31-79 NONE REV. 1 CURRENT INSPECTION OF STEAM CENERATOR TUBING -
PRESERVICE AND INSERVICE MRS 2.4.2 GEN-19 NONE INSTALLATION AND REMOVAL 12-31-79 NONE REV. 0 0F EDDY CURRENT POSITION - -
ING DEVICES
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ - _ - ,-_w.6
NORTilERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND - UNIT 2 TABLE IV EQUIPMENT AND MATERIALS PAGE 1 0F 4 MATERIAL OR TYPE OR CALIBRATION DATE REMARKS EQUIPMENT SERIAL NUMBER OR BATCll NUMBER ULTRASONIC:
NORTEC 131 D S/N 129 CAL: 11-28-79 NORTEC 131 D S/N 111 CAL: 12-19-79 SONIC FISMKI S/N 755111 CAL: 10-31-79 RECORDERS:
COULD 222 S/N 00647 CAL: 9-18-79 COULD 220 S/N 14596 CAL: 12-03-79 COULD 220 S/N 14012 CAL: 12-0749 TEMPERATURE GAUCES:
i PTC SURFACE tiler- S/N 192 CAL: 9-20-79 CERTIFIED BY MANUFAC-M0 METERS S/N 215 CAL: 11-14-79 TURER :
S/N 211 CAL: 10-22-79 '
S/N 216 CAL: 11-14-79 MAGNETIC PARTICLE:
MAGNAFLUX YOKE S/N LMT-100 CAL: 1-03-80 ON SITE QUALIFICATION MAGNAFLUX YOKE S/N GTL-001 CAL: 1-14-80 ON SITE QUALIFICATION ROMPAS BLOCKS:
4140 C.S. S/N 013
- CERT 9-08-77
- BY ORLAS MACHINE SHOP 304 S.S. S/N 14
- CERT 5-17-78 304 S.S S/N 024 ** CERT 9-13-79 ** CERTIFIED BY LMT IIW2 S/N 01 *** CERT 5-16-73 *** BY COOD STEEL SERVICE ;
CALIPER:
DIAL S/N 104 CAL: 11-29-79 CERTIFIED BY MANUFAC-TURER MATERIALS:
e
- LMT-GEL BATQI NO.
ULTRASONIC COUPLANT l LMT 111778 CEL 3000 BATQI NO. 1378 l ULTRACEL II BATG1 NO. 1377 PENETRANT MAGNAFLUX PENETRANT BATCH NO. 7A004 TYPE: SKL-HF/S SPOTCilECK DEVELOPER BATQI NO.78LO50 TYPE: SKD-NF <
CLEANER BATOI NO.786035 TYPE: SKC-NF DEVELOPER BATQ! NO. 6K069 TYPE: SKD-NF 1 i
I l
l
NORTilERN STATES POWER COMPNJY APPENDIX E PRAIRIE ISLAND - UNIT 2 TABLE IV PAGE 2 0F 4 EQUIPMENT AND MATERIALS MATERIAL OR TYPE OR CALIBRATION DATE REM /RKS EQUIPMENT SERIAL NUMBER OR BATCil NUMBER ULTRASONIC TRANSDUCERS: SIZE FREQUENCY llARIS0NICS R30103 .375" x .375" 3.5 MilZ IIARISONICS Q1265 .5" x .25" DUAL 1.5 MilZ
!!ARIS0NICS Q1032 .5" x .5" DUAL 1.5 MHZ llARIS0NICS R1150 .25"x .25" 2.25 MllZ
.375" x .375" 3.5 MIIZ llARIS0NICS R169 llARISONICS R10020 .25" DIA 5 MllZ llARISONICS Q11123 .5" DIA 2.25 MllZ llARISONICS R12200 .25" x .25" 2.25 Mllz llARISONICS P362 1" DIA 2.25 MllZ llARIS0NICS P8120 .5" x .5" 2.25 MilZ PANAMETRICS 5290 .750" DIA 2.25 MllZ liARIS0NICS P360V .5" DIA 2.25 MHZ llARIS0NICS N979 .5" x .5" 2.25 MilZ llARIS0NICS R7166 .5" x .5" 2.25 Mitz PEABODY TESTING EQUIPMENT:
DENSITY STRIP S/N 12831 CAL: 10-01-79 X-RITE CO.
l l
WESTINC110USE !
EQUIPMENT:
-DATA STATION #1- l TEAC FM 2300s NDS/SS# 0036 11-01-79 i BRUS11 MK-220 0530 9-12-79 ,
- BRUSil MK-220 0533 9-12-79 l
, l 8-CllANNEL RECORDER !
MAIN FRAME PLUG IN'S , !
it.P. 3968AZ 0535 9-19-79 MIZ 12 0557 10-03-79 MIZ 42 0558 10-03-79 MIZ 12 0559 10-03-79 MIZ 12 0560 10-03-79 I
MIZ 12 0561 10-03-79 T
NORTilERN STATES POWER COMPANY APPENDIX E PRAIRIE ISIE D - UNIT 2 TABLE IV PAGE 3 0F 4 EQUIPMENT AND MATERIALS MATERIAL OR TYPE OR 1ALIBRATION DATE REMARKS EQUIPMENT SERIAL NUMBER OR BATCll NUMBER MIXER PLUG IN'S MIZ 12 0562 STICKER MIZ 12 0543 IDENTIFIES CAL NOT REQUIRED DISPLAY MODULE STORACE SCOPE MIZ 12 0583 10-03-79 TEK 5111 0564 10-03-79
-DATA STATION #2-TEAC FM 2300S NSD/SS# 0272 11-01-79 BRUSH MK-220 0156 CAL ON STICKER 1-03-80 CAL ON CERT 1-02-80 THIS RECORDER JAS TAGGED OUT AND WILL NOT BE LISED.
BRUSil MK-220 0276 11-02-79 8 CHANNEL RECORDER MAIN FRAME PLUG IN'S 3968AZ ll.P. 0534 9-19-79 '
MIZ 12 0538 9-19-79 -
MIZ 12 0539 9-19-79 l MIZ 12 0584 10-03-79 l MIZ 12 0540 9-19-79 l MIZ 12 0541 9-19-79 HP 3968AZ 0546 10-03-79 MIZ 12 0570 11-19-79 MIZ 12 0565 11-19-79 '
MIZ 12 0566 11-19-79
'I MIZ 12 0567 11-19-79 MIZ 12 0568 11-19-79 e
MIXER PLUG IN'S 0569 STICKER MIZ 12 0571 IDENTIFIES CAL MIZ 12 NOT REQUIRED DISPLAY MODULE STORAGE SCOPE MIZ 12 0537 9-19-79 TEK Sill 0536 9-19-79
\
l l
NORTl!ERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND - UNIT 2 TABLE IV EQUIPMENT AND MATERIALS PAGE 4 0F 4 MATERIAL OR TYPE OR CALIBRATION DATE REMARKS EQUIPMENT SERIAL NUMBER OR BATCll NUMBER EDDY CURRENT STD ,
ZETEC INC S/N 133W DBil 1-06-80 '
INCONNEL 600 LCD 1-05-80 EDDY CURRENT STD INLINE STD ,
. SB-166 INCONNEL S/N IS IIEAT # DBH 1-06-80 TUBING FOR ABS NX-7735 ;
MIXER PLUG IN'S MIZ 12 0542 STICKER 0543 IDENTIFIES CAL NOT REQUIRED DISPLAY MODULE ,
MIZ 12 0556 NO. CAL. STICKER RAS TAGGED OUT <
AND WILL NOT BE USED STORAGE SCOPE TEK 5111 0555 8-23-79 r
-DATA STATION #3-TEAC FM 2300S NSD/SS# 0208 11-01-79 '
BRUSil MK-220 0024 11-20-79 BRUSH MK-220 0532 9-12-79 ZETEC INC S/N I-30-W STANDARD CERT INCONNEL 600 INLINE STD WAS REVIEWED STD WAS NOT UNBOXED
,t ZETEC EQUIPMENT l
, VECTOR ANALYZER
. DISPLAY MODULE STORAGE SCOPE MODEL III S/N 001 11-21-79 MIZ 12 S/N 002 9-19-79 TEK 5111 S/N B120356 11-30-79 f I
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i t
1
(
l APPENDIX F I i
STEAM GENERATOR NO. 21 l
Eddy Current Results and Tube Sheet Maps l r
I i
i l
l
- l O
I i
1
I EDDY CURRENT 1:XAMINATION RESULTS PRAIRIE ISLAND - UNIT II . APPENDIX p STEAM CENERATOR NO. 21 PAGE 1 of 5 llot Leg DATE Mnrch 15- 1980 EXAMINATION FREQUENCY MULTI JAN., 1980 ilASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION i INDICATIONS YR ISI 1 1 66% 0.D. 17"above T.S. None N/A 14 3 DTSS #7 TSP ll.L. None N/A l 12 4 DTSS #7 TSP ll.L. None None !
39 22 DTSS None N/A ,
10 28 DTSS None N/A i 15 28 DTSS None N/A ,
10 34 DTSS None N/A 15 34 DTSS None N/A 20 34 DTSS None N/A '
1 36 P.V. 36"above#4 TSP None 11/76 10"\/#5 TSP 45 36 DTSS None N/A i 15 40 DTSS None N/A ;
20 40 DTSS None N/A ,
N/A t
15 46 DTSS None 45 48 P.V. 2h" above T.S. None N/A 2" above roll None N/A 15 52 DTSS None N/A 26 52 P.V. 23" above #5 TSP 22" above #5 TSP N/A l 26 58 P.V. T.S. to #3 TSP Full Length N/A 43 63 P.V. Around #2 TSP None None 25" above #5 TSP ,
15 64 DTSS None N/A 26 64 DTSS P.V.6"above#1 TSP N/A 42 66 P.V. 8"above #5 TSP 15"above #5 TSP N/A 41 67 P.V. scattered T.S. to #1 TSP to 25"above N/A
26 70 P.V. 29"above#4 TSP 30"above#4 TSP N/A 30 70 DTSS None N/A :
32 76 DTSS #1 TSP P.V.17"above#3 TSP N/A 32 77 P.V. 25"above#2 TSP between#1 TSP N/A 35 77 P.V. f.E. to #2 TSP T.E. to #2 TSP N/A '
.t 31 80 P.V. 40"above#3 TSP 42"above#3 TSP 11/76-10"\/#4 TSP 29 83 P.V. aetween #16#3 TSP around #2 TSP N/A
35" above T.S. 36" above T.S.
P.V.=Permabi lity Variation DTSS = Distc rted Tube Sheet Sitnal 0.D.=0utside diam ( ter
. T.E.= Tube End T.S.= tube sheet T.S.P= tube
!I.L. = Hot Leg
\/ = Below
EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT II APPENDIX F STM1 GENERATOR NO. 21 PAGE 2 of 5 !
Cold Leg DATE March 15. 1980 EXAMINATION FREQUENCY: MULTI JAN'.', 1980 BASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION INDICATIONS YR ISI
. 13 3 P.V. 8"above#1 TSP PV 8"/N#1 TSP N/A 19 7 P.V. between#16#3 TSP PV between#16#2 TSP N/A 1 9 P.V. 12" above T.S. PV 14" above T.S. N/A
. 27 11 P.V. TE to#3 TSP Plus PV full length N/A 30 13 (20% 0.D. Ctr #1 TSP None N/A 31 14 (20% 0.D. Ctr #1 TSP None N/A 33 17 P.V. between#1 TSP PV between #16#2& 11/76 PV 6"5/#4 TSP 45" above #3 TSP PV 10"/\#1 TSP 35 17 (20% 0.D. Ctr #1 TSP None N/A 34 18 P.V. between#16#2 TSP PV from 24" above
- 1 to #2 TSP N/A 36 19 (20% 0.D. Ctr #1 TSP None N/A 37 20 P.V. 5"&l7"above#1 TSP PV 7"&l5" /\ #1 TSP N/A ,
39 25 31% 0.D. Ctr #1 TSP None N/A 15 28 DTSS None None 42 28 (20% 0.D. Ctr #2 TSP None N/A !
43 32 P.V. 35" above #4 TSP & PV 30" above #4 TSP 11/76-PV6"/\ #2 TSP l around #2 TSP around #2 TSP 43 33 ( 20% 0.D. Ctr #2 TSP None N/A ,
10 34 DTSS None N/A 15 34 DTSS None None 20 34 DTSS None N/A !
44 34 P.V. 7"above#4 TSP & PV 12"above#4 TSP 11/76-PV6"/\ #4 TSP I between#16#3 TSP PV around #2 TSP 11/76-PV from #1 to #2 TSP .
43 36 P.V. f.E. to #3 TSP plus PV from TE to N/A
- 3 TSP ,
44 36 P.V. around #1 TSP PV around #1 TSP 11/76-PV 15"\/#1 TSP 43 37 P.V. TS to #3 TSP PV from TE to N/A
- & 23" above TS 45 37 (20% 0.D. Ctr #2 TSP None N/A
, 41 38 P.V. Between #1 & #2 PV between #1 & N/A
. TSP #2 TSP 43 38 P.V. TE to #3 TSP plus PV from TE to N/A t
- 4 TSP 44 39 P.V. 5",7"642"/\ #1 TSP PV around #1 & #2 N/A 45 39 (,20% 0.D. Ctr #1 TSP None N/A 10 40 DTSS None N/A 15 40 DTSS None None 20 40 DTSS None d/A
EDDY CURRENT EXAMINATION RESULTS i
PRAIRIE ISLAND - UNIT II APPENDIX F STEAM CENERATOR NO. 21 PAGE 3 of 5 Cold Leg DATE March 15.1980 ;
i EXAMINATION FREQUENCYsMULTI l
JAN., 1980 BASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION INDICATIONS YR ISI 40 40 P.V. TE to #3 TSP PV from TE to #3 N/A TSP
. 45 40 (20% 0.D. Ctr #2 TSP None N/A
~
43 41 P.V. TE to #3 TSP PV from TE to #4 N/A TSP 44 42 P.V. TS to #3 TSP PV 22" A TS & bet- N/A ween #1 & #2 TSP 43 43 P.V. TS to #3 TSP PV from TE to #3 N/A TSP 44 43 P.V. Between #2 & #3 PV 12" A #2 TSP N/A TSP !
43 44 P.V. TE to #3 TSP None N/A ,
10 46 DTSS ,
None N/A 15 46 DTSS None N/A 20 46 DTSS None N/A 40 46 P.V. TS to #3 TSP PV from TE to 30" N/A ,
& above #2 TSP 44 46 (20% 0.D. Ctr #1 TSP PV 14" A #2 TSP N/A 45 46 (20% 0.D. Ctr #1 TSP PV 40" A #1 TSP N/A ;
43 47 P.V. TE to#3 TSP PLUS PV from TE to #5 N/A TSP 44 48 22% 0.D. Ctr #1 & #2 None N/A TSP 1 50 DTSS None N/A ,
1 51 DTSS None N/A 43 51 P.V. TS to #1 TSP PV from TE to #3 N/A TSP 1 52 DTSS None N/A ,
10 52 DTSS PV 45" above #3 N/A 15 52 DTSS None N/A 20 52 DTSS None N/A i
40 52 P.V. TS to #1 TSP PV between #1 & N/A
- 2 TSP
. 43 52 P.V. Between #2 & #3 PV between #1 & N/A
- TSP #2 TSP 45 52 37% 0.D. Ctr #1 TSP None N/A 46 52 32% 0.D. Ctr #1 TSP None N/A 1 53 DTSS None N/A 42 53 P.V. #1 to #3 TSP & PV from TS to #3 N/A 3" above TS TSP 44 53 <20% 0.D. Ctr #1 TSP None. N/A 46 53 (20% 0.D. Ctr #1 TSP None N/A 1 54 DTSS None N/A 44 54 29% 0.D. Ctr #1 TSP None N/A 1 55 DTSS None N/A l
l
EDDY CULRENT ULV!INATION RESULTS PRAIRIE ISLAND - UNIT II APPENDIX F STEAM GENERATOR NO. 21 PAGE 4 of s Cold Le8 DATE March Iq. 1980 EXAMINATION FREQUENCY: MULTI I
JAN., 1980 BASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION -
INDICATIONS YR ISI 45 56 P.V. TS to #1 TSP PV from TS to #1 N/A
- TSP 44 57 P.V. Around #1 TSP PV 40" A #4 TSP & N/A ,
around #1 TSP 10 58 DTSS None None 15 58 DTSS None N/A 20 58 DTSS None None ,
40 58 P.V. Between #1 & #3 PV around #2 TSP N/A l TSP 41 58 P.V. TS to #3 TSP Plus PV fron TS to 25" N/A l abo"c #3 TSP 42 58 P.V. TS to #3 TSP PV from TS to #3 N/A ;
TSP j 45 58 P.V. TS to #3 TSP PV from TS to #3 N/A l i
TSP 41 59 P.V. TS to #3 TSP Plus PV from TS to #3 N/A I l
TSP 43 59 <20% 0.D. Ctr #1 TSP None M/A l 43 62 <20% 0.D. Ctr #1 TSP None N/A {
10 64 DTSS None N/A i 15 64 DTSS None N/A 40 66 <20% 0.D. Ctr #2 TSP None N/A 41 67 39% 0.D. Ctr #1 TSP None N/A
- 40 69 (20% 0.D. Ctr #1 TSP None N/A 39 72 <20% 0.D. Ctr #1 TSP None N/A 38 74 (20% 0.D. Ctr #1 TSP None N/A 34 76 <20% 0.D. Ctr #2 TSP None N/A 37 76 <20% 0.D. Ctr #1 TSP None N/A 35 78 72% 0.D. Upper half None N/A
,s #1 TSP 1 79 33% 1" above TS & None N/A 35% 8" above TS None N/A 31 79 <20% 0.D. Ctr #1 TSP None N/A
/ 32 79 35% 0.D. Ctr #1 TSP None N/A i 31 81 P.V. #4 to #5 TSP PV between #4 & N/A
- 6 TSP 30 83 (20% 0.D. Ctr #1 TSP None N/A 23 86 (20% 0.D. Ctr #1 TSP None N/A 20 87 (20% 0.D. Ctr #1 TSP None N/A 18 89 <20% 0.D. Ctr #1 TSP None N/A l
l 7 91 <20% 0.D. Ctr #1 TSP None N/A 9 91 <20% 0.D. Ctr #1 TSP None N/A
l I
I 1:1)l>Y CUltRENT :WI[ NATION ItESULTS l
Al' lit.:Nulx p !
i l'ItA 1RI E ISt.ANI) - 1: nit II STEA}l CENEftAT0lt NO. , 21 l'Ar:E s of 5 Cold Leg l) ATE _liarch 15,_1980
[
l'XA>11 NATION 1'liEQUENCY: flUI.Tl l
/
.l AN. , l ')HO D AS El. I!!E l'l:EV1011S itik' Ct)l.21. I ND Ii AT IO*4S I,0fIA'l i OM I NI)I CAT I1)!!N Vit iST 10 91 20% 0.D. CTR #1 TSP NONE N/A 4 94 28% 0.D. CTR #1 TSP NONE N/A l
l l
- NOTE: PV = PERMABILITY VARIATION l DTSS = DISTORTED TUBE SHEET SICNAL !
CTR = CENTER 0.D. = OUTSIDE DIAETER TE = TUBE END TS = TUBE SUPPORT TSP = TUBE SUPPORT PLATE l A = AB0VE l V = BELOW t
3 1
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@ tubes plugged to d.te e
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SERIES 51 93 9189 67 % B3 681917 75 73 78 69 671,51,5 bl 59 57 55 E3 5149 47 45 43 4/ 39 373533 3129 27 25 23 21 1917 IS 13 ll 9753/
I COLUMNS 9e 92 90 86 8684 82 So 78 76 74 72 70 68 66 IA 62 l#58 ' /,54 52 50 4e 46 44 42 40 53 54 34 32 30 Zo 24 24 22 to so 16 I4 12 to S I, 4 Z l
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Prair:1e Island Nuclear Generating Plant Unit II
- +MANWAY E!Of4*H
- IS.H.1""
E tubes inspected through 7th support NOZZLE +
Eor A tubes inspected through 3rd support tubes inspected through U-Bends h- tubes plugged to Date
-v.-_
SERIES 51 93 9189 6765 83 ol 19 71 TS 1318 69 67 LS 45 bl $9 57 55 E3 5149 4145 43 4139 313535 3/ 2127 25 23 21 19171513 ll 9753/
I COLUMNS 94 92 90 88 86 84 82 60 75 75 74 7Z 70 68f.6 IA 62 14SS *454 52 So 4e 46 44 42 40 58 54 34 32 30 to 21 24 22 20 to 16 I4 IZ lo S le 4 Z
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Pro steam Generator No. 21 Inlet - 400 EHI
+M ANWAY uctrie Island1.ti Weclear e Tot.tGeneratingor w. I..,ected Plant to -noteUnit<=II 1,11) NOZZLE--*
S Tubes Inspected Through U Bende 3 Tubes Inspected to Top (7th) Support t
g . _.4 -_ ._ _____ - _ . _ . _ _ _
a e * .e s
~
SERIES 51 93 9/ 89 5785 83 83 79 77 75 73 78 69 47 45 45 4159 57 55 f3 5149 47 45 43 4/ 39 373533 3/ 29 27 25 25 2/ #917 /513 // 9 7 5 3 /
COLUMNS 98 ft 90 88 86 84 82 60 75 76 74 72 10 6866 (A 62 (#58 *4 54 52 50 4e 46 44 42 40 58 56 54 32 30 Z8 26 24 22 20 18 le I4 IZ fo 8 6 1 Z KXxxxxxxx ~'
- 44 45
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_ _ _; - u__ m __ __ __ _ _ _; u__ _ __;
2ra Steam Generator No. 21 Outlet - 400 KRa p +M ANWAY am.trie Istand.i.ti Nuclear rot. Generating or row. I..,e.te Floatto- Unit .... (No. II tem NOZZLE--*
p a row . 1..,e.te, to 1., <1tn> s.,, ort b
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-_ _ m ______ .
i i
I I
APPENDIX G
! STEAM CENERATOR NO. 22 l
Eddy Current Results and Tube Sheet Maps r
t I
I e
l l
l
= l s l l
1- l l
I l
- l l
l l
l 1
1 l
EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT II APPENDIX c STEAM CENEl% TOR NO. 99 PAGE 1 of a Hot Leg DATE unr 1s. 1oRO EXAMINATION FREQUENCY:MULT1 o
J AN. , 1980 BASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION . INDICATIONS YR ISI 12 3 DENT #7 TSP NONE N/A !
13 3 DENT #7 TSP NONE N/A 14 3 DENT #7 TSP NONE N/A 12 4 DENT #7 TSP NONE 01 Same .
NONE N/A !
11 4 DENT #7 TSP
- 7 TSP NONE NONE !
9 4 DENT '
8 4 DENT #7 TSP NONE N/A 7 5 DENT #7 TSP NONE N/A 8 5 DENT #7 TSP NONE N/A 9 5 DENT #7 TSP NOME N/A 43 30 DTSS Dent @ #1 anti- 01 Same vibration Bar 44 33 DENT #7 TSP C.L. NONE N/A 26 34 DTSS NONE N/A 20 34 DTSS NONE N/A 15 34 DTSS NONE N/A 10 34 DTSS NONE N/A !
45 40 DTSS NONE N/A l 26 40 DTSS NONE N/A
- 20 40 DTSS NONE N/A 15 40 DTSS NONE N/A 10 40 DTSS NONE N/A 45 41 DTSS #7 TSP NONE N/A ,
46 41 DTSS #7 TSP $ NONE N/A DTSS #1 TSP NONE N/A 45 42 DTSS #7 TSP NONE N/A 30 46 DTSS NONE N/A 26 46 DTSS NONE N/A 20 46 DTSS NONE N/A 15 46 DTSS NONE N/A
. 10 46 DTSS NONE N/A t 16 46 DTSS NONE N/A i 17 46 DTSS NONE N/A 18 46 DTSS NONE N/A ,
8 47 DTSS NONE NONE l 9 47 DTSS NONE N/A 10 47 DTSS NONE N/A i 11 47 DTSS NONE NONE
. 12 47 DTSS NONE NONE 13 47 DTSS NONE N/A 14 47 DTSS NONE N/A l 15 47 DTSS NONE. NONE l' 16 47 DTSS NONE N/A 18 47 DTSS NONE NONE i 19 47 DTSS NONE N/A ,
l
EDDY CURRENT EXAMINATION RESULTS I
PRAIRIE ISLAND - UNIT II APPE}'DlX G l STEAM CENERATOR NO. 22 PACE 2 of 8 Hot Leg DATE u.
~~
ie
~~' -~~0 io .
EXAMINATION FREQUENCY: MULTI l l
JAN., 1980 BASELINE PREVIOUS l ROW COLM. INDICATIONS 1.0 CAT 10N INDICATIONS YR IST 20 47 DTSS NONE N/A 21 47 DTSS NONE NONE
'; 22 47 DTSS NONE N/A 23 47 DTSS NONE N/A 24 47 DTSS NONE NONE '
25 47 DTSS NONE N/A ,
26 47 DTSS NONE NONE 27 47 DTSS NONE N/A 28 47 DTSS NONE N/A 29 47 DTSS NONE NONE ,
30 47 DTSS NONE N/A 31 47 DTSS NONE NONE 32 47 DTSS NONE N/A 31 48 DTSS NONE N/A 30 48 DTSS NONE N/A i 29 48 DTSS NONE N/A l 28 48 DTSS NONE N/A 27 48 DTSS NONE N/A 26 48 DTSS NONE N/A 25 48 DTSS NONE N/A 24 48 DTSS NONE 01-76 PV @ U-Bend 23 48 DTSS NONE N/A 22 48 DTSS NONE N/A 21 48 DTSS NONE N/A N/A 20 48 DTSS NONE 19 48 DTSS NONE N/A 18 48 DTSS NONE N/A 17 48 DTSS NONE N/A 16 48 DTSS NONE N/A 15 48 DTSS NONE N/A 14 48 DTSS NONE N/A 8
13 48 DTSS NONE J/A 12 48 DTSS Dent 33" A #4 TSP NONE
- 11 48 DTSS NONE N/A t 10 48 DTSS NONE N/A 9 48 DTSS NONE N/A
. 8 48 DTSS NOME N/A 7 48 DTSS NONE N/A l 30 52 DTSS NONE N/A l 26 52 DTSS NONE N/A
( 20 52 DTSS NONE N/A 20 52 PV Around #5 TSP & PV around #5 TSP & N/A Between #2&3 TSP between #263 TSP 15 52 DTSS NONE N/A 10 52 DTSS NONE N/A I
EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT II APPENDIX C ;
STEAM CENERATOR NO. 22 PAGE 3 of a Hot Leg DATE mr 1s; iogn EXAMINATION FREQUENCY: MULTI i
JAN., 1980 BASELINE PREVIOUS R0W COLM. INDICATIONS LOCATION - INDICATIONS YR ISI o 20 58 DTSS NONE N/A 20 58 PV 29" A#2 TSP & PV 30"A #2 TSP & N/A >
! 15 58 DTSS NONE N/A 26 64 DTSS NONE , N/A 26 70 DTSS NONE N/A 20 70 PV Around #3 TSP & NONE N/A around #7 TSP C.L.
15 91 PV Between #3 & #1 PV Between #1 & N/A TSP #3 TSP 1
I NOTE: PV = PERMAB ELITY VARIATION DTSS = DIST)RTED TUBE SHEET SIGNAL DENT = <2.5 MILS TSP = TUBE 3UPPORT PLATE C.L. = COLD LEG ,
, A = AB0V s t
A k,
r EDDY CURRENT EXAMINATION RESULTS PRAIRIE ISLAND - UNIT II APPENDIX n STEAM CENERATOR NO. 22 PACE ti of n Cold Leg DATE u n ,. p;- loan EXAMINAT10N FREQUENCY: MULTI JAN'., 1980 BASELINE PREVIOUS ROW COLM. INDICATIONS LOCATION . INDICATIONS YR ISI 12 2 DENT #7 TSP ll.L. NONE N/A 8 2 SMALL DENT 19" A #5 TSP Dent 18" A #5 TSP N/A 2 3 SMALL DENT 19" A #1 TSP NONE N/A l I 12 3 (20% 0.D. #2 TSP CTR NONE NONE 16 4 PV Between #36#4 TSP NONE N/A 16 5 PV Around #3 TSP NONE N/A 16 6 PV 21" A #3 TSr PV 22"A #3 TSP N/A 18 6 PV 3" A TS PV 0 TS N/A 19 7 PV TS to #3 TSP + NONE N/A .
22 8 PV Around #3 TSP PV Between #4 & N/A
- 5 TSP 19 8 PV Between #1 & #3 NONE N/A TSP 28 10 SMALL DENT 15" A #5 TSP NONE N/A 15 10 PY 10" A #2 TSP PV 12"A #2 TSP N/A 19 10 PV TS to #3 TSP PV from TS to N/A
26 11 33% 0.D. CTR #1 TSP NONE N/A 30 13 22% 0.D. CTR #1 TSP N0'1E N/A 28 15 <20% 0.D. #1 TSP 1A N/A 33 16 <20% 0.D. CTR #1 TSP V N/A 31 16 (20% 0.D. CTR #1 TSP NONE N/A 30 16 (20% 0.D. CTR #1 TSP NONE N/A 32 17 39% 0.D. CTR #1 TSP NONE N/A 33 17 <20% 0.D. CTR #1 TSP NONE NONE 36 18 33% 0.D. CTR #1 TSP NONE N/A 35 18 (20% 0.D. CTR #1 TSP NONE 1. /A 34 18 48% 0.D. CTR #1 TSP PV 44" above TS N/A 35 19 <20% 0.D. CTR #1 TSP NONE NONE 34 20 (20% 0.D. CTR #1 TSP NONE N/A 36 20 (20% 0.D. CTR #1 TSP NONE N/A 37 21 41% 0.D. CTR #2 TSP NONE N/A 38 22 24% 0.D. CTR #2 TSP NONE N/A
' 15 22 DTSS NONE NONE 39 23 (20% 0.D. CTR #2 TSP NONE N/A 40 24 23% 0.D. CTR #2 TSP NONE N/A 40 25 (20% 0.D. CTR #2 TSP NONE N/A 39 25 21% 0.D. CTR #2 TSP NONE N/A 41 28 38% 0.D. CTR #1 TSP NONE N/A 20 28 PV Between #2 TSP NONE NONE 15 28 DTSS NONE NONE
! 42 32 (20% 0.D. CTR #2 TSP NONE NONE j 42 33 28% 0.D. CTR #2 TSP NONE N/A l '
l '
l
EliinY CultitE;ri WlINATION llESULTS l'llAllllE ISt.ANI) - 11Nt's il Ag.g.y;;n g x g STI:N! GENERAT0lt t:0. 22 i.Ar:n q iff T Ih\ II AflON FREQtlENCY ttill.Tl i
.l AN . , 1980 !; ASEl. l N E PRI'.V iollS 80U C01.21. I N1)1 CAT I ONS 1.0PATION 1NHICATIONS Yle iSI e
- 20 34 DTSS NONE NONE 15 34 DTSS 0.D. CTR #2 TSP NONE N/A 44 35 21%
0.D. # 2 TSP NONE N/A 43 36 24%
0.D. # 2 TSP NONE N/A 43 37 47%
47% 0.D. #2 TSP NONE N/A ,
44 37 0.D. #2 TSP NONE N/A i 45 37 51%
0.D. #2 TSP NONE N/A 45 39 < 20%
NONE N/A ,
20 40 DTSS NONE NONE 15 40 DTSS 0.D. #2 TSP NONE N/A 44 40 < 20%
0.D. #1 TSP NONE N/A 46 41 < 20%
49% 0.D. #2 TSP NONE N/A 44 41 0.D. #2 TSP NONE N/A :
46 42 <20% N/A 43 41% 0.D. #1 TSP NONE 46 0.D. #2 TSP NONE N/A 45 44 (20% N/A 0.D. #1 TSP NONE 46 45 (20% N/A 47 DTSS NONE 7
NONE N/A -
8 47 DTSS DTSS NONE N/A 9 47 NONE N/A 10 47 DTSS 47 DTSS NONE N/A 11 47 DTSS NONE N/A 12 DTSS NONE N/A 13 47 47 DTSS NONE N/A 14 DTSS NONE N/A 15 47 DTSS NONE N/A 16 47 47 DTSS NONE N/A 21
' NONE N/A 22 47 DTSS NONE N/A 23 47 DTSS 47 DTSS NONE N/A' 24 DTSS NONE N/A
< 25 47 NONE N/A 1 30 47 DTSS 0.D. #2 TSP NONE N/A 46 48 48%
NONE N/A
- 31 48 DTSS NONE NONE 30 48 DTSS NONE NONE 28 48 DTSS NONE N/A 27 48 DTSS NONE N/A 26 48 DTSS NONE NONE 25 48 DTSS I NONE N/A 23 48 DTSS NONE N/A 22 48 DTSS NONE NONE 21 48 DTSS l
1:1)DY CURREN'i ' WilNATION ltESULTS PitAIRil'. ISt AND - !!?;lT 11 apt'ENul x a STEAfl CENEPATOR No. 22 PAGE DATl;
(
_- of _b Mnr 15.~ 1980 COLD LEG EXA'llNATION l't:EOUENCY: ttill.T l I; ASCI,1 NC PREV [011S
.l AS. , 1980 I ND lCXi lON!i 1. ORATION INul t:AT IONS YR IST 140U C01.:1.
e NONE 20 48 DTSS NONE 48 DTSS NONE N/A 19 i 48 DTSS NONE N/A
- 18 48 DTSS NONE N/A ;
17 !
16 48 DTSS PV 12" above TS N/A 15 48 DTSS NONE 01-76 Dent 14" l' above T.S.
NONE NONE 14 48 DTSS 13 48 DTSS NONE N/A 12 48 DTSS NONE N/A i 11 48 DTSS NONE N/A l i
NONE NONE 10 48 DTSS 48 DTSS NONE N/A 9 !
NONE NONE 8 48 DTSS 7 48 DTSS NONE N/A 46 49 (20% 0.D. #1 TSP NONE N/A 1 51 DTSS NONE N/A 52 DTSS NONE N/A 15 10 52 DTSS NONE N/A 1 52 DTSS NONE N/A 1 53 DTSS NONE N/A 43 53 29% 0.D. #2 TSP NONE N/A 46 54 29% 0.D. #1 TSP NONE N/A 1 54 DTSS NONE N/A 44 54 44% 0.D. #2 TSP NONE N/A 1 55 DTSS NONE N/A 45 55 DTSS NONE N/A 44 55 (20% 0.D. @#1 TSP NONE N/A 43 55 (20% 0.D. #2 TSP NONE N/A 42 55 23% 0.D. #1 TSP NONE N/A 1 56 DTSS NONE N/A
- 0.D. #1 TSP NONE N/A 44 56 (20%
40 56 29% 0.D. #1 TSP NONE N/A 1 57 DTSS NONE N/A 0.D. #2 TSP NONE N/A 44 57 (20%
44 58 (20% 0.D. #1 TSP NONE N/A 15 58 DTSS NONE N/A 0.D. #2 TSP NONE N/A 42 59 (20%
43 59 <20% 0.D. #2 TSP NONE N/A 44 59 36% 0.D. #2 TSP NONE N/A 0.D. #1 TSP NOME N/A 44 60 (20%
41 61 (20% 0.D. #2 TSP NONE N/A 43 62 25% 0.D. #2 TSP- NONE N/A (20% 0.D. #1 TSP NONE N/A 1 62 DTTS NONE N/A
I:DI)Y Cl!!(ItENT .OrlINATION IU. SUI.TS l'l:A III l'. ISt.AND - li::I 'l i! Al*1'E!;D i X _L , _
S~l1:A.'l Cl:N1;l:ATOI: NO. 22 l'ACI:_ 2_ of _ A Cold Leg DATE Mar _15 1980 EXAMl;;AT10N !<1:EytI6'. ;CY: ?1111.T l IAN., l ')HO il ASl;l.1 N E l'iti: VIOL!S 401l COI.l1. I ND i t'A l I ONS l.orATIO: I N u t CA'l I ON S Yli ISI 1 63 DTSS NONE N/A 39 64 <20% 0.D. #2 TSP NONE N/A 42 65 <20% 0.D. #2 TSP PV 15" A #3 TSP N/A
. 43 65 (20% 0.D. #2 TSP None N/A 41 66 25% 0.D. #2 TSP NONE N/A 41 67 27% 0.D. #2 TSP NONE N/A .
41 68 < 20% 0.D. #2 TSP NONE N/A 10 70 DTSS NONE N/A ;
1 71 DTSS NONE N/A 40 71 <20% 0.D. #2 TSP NONE N/A 39 72 <20% 0.D. #2 TSP NONE N/A 1 72 DTSS NONE N/A 38 72 31% 0.D. #2 TSP NONE N/A 38 73 (20% 0.D. #1 TSP NONE N/A 37 73 <?0% 0.D. #2 TSP NONE N/A ,
38 74 49% 0.D. #2 TSP NONE N/A ,
37 74 (20% 0.D. #2 TSP NONE N/A I 37 75 27% 0.D. #1 TSP NONE N/A 37 76 (20% 0.D. #2 TSP NONE N/A 36 76 <20% 0.D. #1 TSP t:0NR N/A 34 76 56% 0.D. #1 TSP NONE N/A 34 77 22% 0.D. #1 TSP NONE N/A 36 77 (20% 0.D. #1 TSP NONE N/A (20% 0.D. #2 TSP NONE N/A 35 78 46% 0.D. 12"A TS (2 NONE N/A indications) 33 78 30% 0.D. #2 TSP NCNE N/A 70% 0.D. #1 TSP NONE N/A 31 78 36% 0.D. #1 TSP NONE N/A 31 79 35% 0.D. #2 TSP NONE N/A 32 79 <20% 0.D. #2 TSP NONE N/A .
33% 0.D. #1 TSP NONE N/A a 33 79 46% 0.D. #1 TSP NONE N/A 34 79 43%. O.D. #2 TSP ? PULLED N/A 30 79 (20% 0.D. #2 TSP NONE N/A 31 80 <20% 0.D. #1 TSP NONE N/A 31 81 32% 0.D. #1 TSP NONE N/A
. 30 81 (20% 0.D. #1 TSP NONE N/A 29 82 <20% 0.D. #2 TSP NONE ^
N/A 29 83 (20% 0.D. #2 TSP NONE N/A 28 85 <20% 0.D. #1 TSP NONE N/A
EiniY ct:H R FN'l \AfilNATION ItElilflifS l'l!A l i' l l: I SI ANi> - l*?. I'l i1 API'! N:11X __ & _
STI:A': GENI:f:.Y; ot: t.o . 22 pat:t.__8_ "I ._8 Cold Leg IWiE gn,. 3,,ggg, EXAh!INATloN i !:Etjtfi:NCY: Mt11.Tl
.l AN. , I980 1; A!;f.t. l M E l'Rl:V i OliS 1 :.: lit'A'l it P ti IM'ATlii!: I NIH ('A r t hMS Yl; ISI I:OW COI .' t .
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25 85 < 20% 0.D. #1 TSP NOME N/A 23 85 < 20% 0.D. #2 TSP NONE N/A 22 86 <20% 0.D. #2 TSP NONE N/A 18 90 <20% 0.D. #1 TSP NONE N/A 2 91 PV 17" above TS NONE N/A 17 91 <20% 0.D. #2 TSP NONE N/A 1 93 <20% 0.D. #1 TSP NONE N/A 7 93 PV 10" A #1 TSP PV 40"A #5 TSP & N/A 8" A #1 TSP l
Note: PV = PERMABlLITY VARIATION 4TSS = DISTOR"ED TUBE SilEET SIGNAL t.
DENT = <2.5 MILS II.L. = Il0T LEG TS = TUBE SHEET !
TSP = TUBE SUPPORT PLAT E CTR = CENTER 0.D. = OUTSIDE DIA 1ETER i A = ABOVE I
~ . . . . . -
SERIES 51 93 9189 S7 % 83 6179 7715 73 70 @ !,7 45 65 tol $9 5155 E3 5I 49 47 45 43 4/ 39 313535 3) 29 27 25 23 21 19 97151311 9 7 5 3 l 94 92 90 83 84 84 82lSo74 COLUMNS 78 74 72 70 68 e6 L4 62 M 58 % 54 52 50 4e 46 44 42 40 58 54 54 32 30 28 24 24 22 to to it,14 f, to 8 I, 4 2 l
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_- Prairie Island Nuclear Generating Plant L; nit 11 b +MANWAY XHM.fPe 5 s;.'Cl25" tubes inspected through 7th Support NOZZLE
- Ecr or tubes inspected through U-Bend tubes inspected through 1st Support tubes plugged to date g incompAet.e InsPectiOR
-w: v. 3 swQ~-~'
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__ SERIES 51 93 ?i d 67 % e: 86191175 73 76 .d si L5 65 41 $9 5T 55 E3 5149 47 45 43 4139 373533 3/ 29 27 25 23 21 1917151311 9 7 5 3 l i COLUMNS
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Prairie Is1.nJ Nuclear Cencrating Plar.t L' nit II
__J-k ___ - : - -
ROWS S'"""'"""'~
b *-MANWAY Multi-frequency Examinations: g Tubes Inspected through 7th Support NOZZLE-*
Q or A Tubes Inspected through 3rd support O Tubes Inspected through let Support O Tubes Plugged to Date
- r Incomplete Inspection P Pulled
. r ~ ...w-
c SERIES 51 73 9/ 89 $7 85 83 83 77 77 75 75 71 M &7 45 43 &I 57 57 55 f3 5149 47 45 43 4/ 37 373533 3129 27 25 25 21 171715131/ 9 7 5 3 /
COLUMNS 94 72 90 S8l.8&l64l82l60 75 7G 74 72 70 68la /,4 L2 /,9 58 % 54 52 50 de 46 44 42 40 55 54 34 52 30 ZS 24 24 22 20 #816 I4 /Z 10 8 la 4 Z l l'
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- Prairie Island Nuclear Generating plant - Unit II Steam Generator No. 22 Inlet - 400 KNI
+ M M WM ^* * """ ' ' '* *' ' " ' '" '*
- G* Tubes ** * *Inspected " (""'Through ') -
WUWe b- E Tubes Inspected to Top (7th) Support U. Send O Tubes Inspected to piret support g Restricted Tubes O plugged Tubes
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SERIES 51 93 9189 67 85 83 68 TJ 77 T5 73 70 i,9 47 65 45 bl 59 57 55 E3 5149 47 45 43 4139 373533 3/ 29 27 25 23 21 IP 17151311 9 7 5 3 /
COLUMNS 94 PF 90 86 86 84 82 80 78 75 74 72 70 4l66 /A f,2 /,0 58 % 54 52 50 4e 46 44 42 40 58 54 34 32 30 28 24 24 22 to to te I412 to 8 la 4 Z
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s ROWS Prairie Island leoclear Generating Plant - Unit II stema Generator Isa. 22 Outlet - 400 KHB g Accumulative Total of Tubes Inspected to Date (1 tov,1977) g] 4 i e Tubes Inspected Through U-Bende E Tubes Inspected to Top (7th) Support
-an: ,
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l APPENDIX H FORM NIS-1 Owners' Data Report for Inservice Inspection O
e 9
0
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTICNS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY g,) g9 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA Address PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 ,
2.) Flant e Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorisation)' ---
5.) Consnercial Service Date 12-21-74 6.) National Board Number for Unit----
7.) Components Inspected Manu facturer Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
Bl.0 REACTOR VESSEL CREUSOT-LOIRE 687 MINN 200-51 ----
Bl.15 VESSEL INTERIOR .
VISUALLY ----
ACCESSIBLE WESTINGHOUSE SURFACES CREUSOT-LOIRE l
B2.0 l'RESSURIZER WESTINGHOUSE 1191 ---- 68-57 B2.4 N0ZZEL TO SAFE END WELDS PZR SAFETY LINE A NAVC0 6-2RC-20A 6" W-1 S.E.
PZR SAFETY LINE B NAVC0 .
J 6-2RC-20B 6" W-1 S.E. ;
- PZR RELIEF LINE NAVC0 l
. 3-2RC-21 J
3" W-1 A S.E. -
PZR SPRAY LINE NAVC0 l 3-2RC-5 l
3" W-22A S.E.
B3.11 STEAM GENERATOR TUBING !
1 STEAM GENERATOR 1181 --- 68-39 NO. 21 WESTINGHOUSE {
Form No. 3-3048-1 Page y of 22 1
l l
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS 1
(As Required by the Provisions of the ASME Code Rules) l 1.) Owner NORTHERN STATES POWER COMPANY l
Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA l 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (certificate of Authorization)
I 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit --
7.) components Inspected Manu facturer Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
B3.11 CONT'D INLET INSP INSP TUBE AMT TYPE EXTENT 315 MULTI-FREQ AROUND U BEND 63 MULTI-FREQ -AROUND TIGHT RADIUS U BEND 119 MULTI-FREQ PAST SEVENTH SUPPORT OUTLET INSP INSP TUBE AMT_ TYPE EXTENT 429 MULTI-FREQ PAST THIRD SUPPORT 266 MULTI-FREQ PAST SEVENTH SUPPORT 27 MULTI-FREQ AROUND TIGHT RADIUS U BEND 4
STEAM GENERATOR WESTINGHOUSE 1182 -
68-40 -
NO. 22 1 INLET INSP INSP TUBE AMT TYPE EXTENT 80 MULTI-FREQ PAST FIRST SUPPORT 105 MULTI-FREQ PAST SEVENT SUPPORT 318 MULTI-FREQ AROUND U BEND 89 MULTI-FREQ AROUND TIGHT RADIUS U BEND
.Page 2 of 22 Form No. 3-3048-1
i l
l l
l FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONC (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTIIERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant
- Address WELCll, MINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorization) --
S.) Commercial Service Date 12-21-74 6.) National Board Number for Unic" 7.) Components Inspected Manu fa cturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
OUTLET INSP INSP TUBE AMT TYPE EXTENT 3 MULTI-FREQ PAST FIRST SUPPORT 928 MULTI-FREQ- PAST THIRD SUPPCRT 212 MULTI-FREQ PAST SEVENTH SUPPORT B4.0 PIPING PRESSURE BOUNDARY B4.1 SAFE END TO PIPING AND SAFE END IN BRANCH PIPING WELDS PZR SAFETY LINE A ----
6-2RC-20A NA)CO 6" W-1 PZR SAFETY LINE B 6-2RC-20B NAVC0 e - - - -----
6" W-1 --
- PZR RELIEF LINE- NAVC0 2RC-21 3" W-B w-f g PZR SPRAY LINE NAVC0 3-2RC-5 3" W22B Page .3 of 22 Form No. 3-3048-1
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 3
Address , 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR CENERATING PLANT, UNIT 2 ,
Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorization) ---
~
5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit---
7.) Components Inspected Manu facturer Component or Manu facturer or Installer State or National ,
Apportenance or Installer Serial No. Province No. Board No.
B4.5 CIRCUMFERENTIAL BUTT WELDS SEAL INJECTION B NAVC0 ----
2-2VC-21B 2" W-29, 33, 34, 36, 37 ;
CHARGING LINE NAVC0 ---
2-2VC-5 2" W-37, 38, 39 LETDOWN AND DRAIN NAVC0 !
2-2RC-10B 2" W-6,7 RTD COLD LEG A NAVC0 2-2RC-8A 2" W-6 RTD COLD LEG B NAVC0 2-2RC-8B 2" W-8, 9
- RTD HOT LEG A NAVC0 ----
2-2RC-7A 2" W-29 RTD HOT LEC B NAVC0 - - - -
2-2RC-7B ,
2" W-23 l l
SPRAY TO PZR NAVC0 - - - - -
BR-A j 3-2RC-5 l 3" W-20, 24, 25 l Page 4 of 22 Form No. 3-3048-1 0'
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTHERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA ,
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant Address WELCH, MINNESOTA 3.) Plant Unit 2 4.)
Owner (Certificate of Authorisation)
I 5.) Comercial Service Date 12-21-74 6.) National Board Number for Unit --
7.) Components Inspected Manu fa cturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
B4.5 CONT'D SPRAY TO PZR NAVC0 ---
l -
BR-8 3-2RC-5 3" W-3, 4, 5 PZR RELIEF LINE B NAVC0 -
3-2RC-21 3".W-9 REACTOR VESSEL SAFETY INJECTION A NAVC0 ---
6-2SI-25A 6" W-6 PZR SAFETY LINE A NAVC0 -- - - -
6-2RC-20A 6" W-8 PLO-CAP LOOP B NAVC0 -----
6-2RC-13C ~
6" W-1 ACCUMULATOR NAVC0 ----
DISCHARGE A 12-251-27A i 12" W-7 .
ACCUMULATOR NAVC0 -
DISCHARGE B
! 12-2SI-27B l 12" W-13
.Page 5 of 22 Form No. 3-3048-1 l
l
< +
l FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTilERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2
, Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorization) --
5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit ---
7.) Components Inspected Manu fa c turer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
B4.8 SOCKET WELDS LETDOWN AND DRAIN NAVC0 - - - - -- ----
2-2RC-10B 2" SW-10 RTD HOT LEG A NAVC0 -- - --- ----
2-2RC-7A 2" SW-31 RTD HOT LEG B NAVC0 -- - - ---
2-2RC-7B ,
2" SW-29 ,
B4.9 INTEGRALLY WELDED SUPPORTS SPRAY TO PZR NAVC0 ----- ---- -----
BRANCH A 3-2RC-5 L, RCRH-14
' t SEAL INJECTION B NAVC0 ----- - --
2-2VC-21B A. RCVCH-1575 B4.10 SUPPORT COMPONENTS SEAL INJECTION A NAVC0 ---- --- --
- 2-2VC-21A A, PRCVCH - 1526 B, PRCVCH - 1526 l C, PRCVCH - 1525 l
Form No. 3-3048-1 Page 6 0f' 22
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner ORMM SNES MER COMM 414.NICOLLET MALL, MINNEAPOLIS, MINNESOTA Address PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant 1 WELCH, MINNESOTA
, Address 2
3.) Plant Unit 4.) Owner (Certificate of Authorization) -- i 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit ---
7.) Components Inspected Manu facturer '
Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No. Province No. -Board No. :
B4.10 CONT'D RTD COLD LEG A NAVC0 2-2RC-8A l B1, PRRCH - 281 RTD HOT LEG A NAVC0 - - - -
2-2RC-7A G, PRRC11 - 279 H. PRRCH - 279 SAFETY INJECTION NAVC0 ----
IIIGH A 2-2SI-35A D, PRSIH-240 SPRAY TO PZR NAVC0 -
BRANCH A 3-2RC-5 V, RCRH-5 4
SPRAY TO PZR NAVC0
, . BRANCil B
. 3-2RC-5 D, RCPJi-1 E, 111-2RC-2B F1, 111-2RC-3 l RilR TAKE OFF A NAVC0 -
8-2RC-15A 8-2RH-1A
- C, 9-2RHR-7 l E. RHRRH-1 l
l Page 7 of 22 Form No. 3-3048-1 l
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 Address WELCH, HINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorization) --
5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit 7.) Components Inspected Manu facturer Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No. ,
l B4.10 CONT'D ACCUMULATOR NAVC0 DISCHARGE A 12-2SI-27A D, SIRH-4 E, 101-2 SIS-2 G, 101-2 SIS-3A SEAL INJECTION B NAVC0 ---
2-2VC-21B D, PRCVQl-1382 ,
E, PRCVCH-1381 '
L, PRCVQl-1375 M, PRCVCH-1374 CHARGING LINE NAVC0 ----
2-2VC-5
, 2-2VC-6 ,
0, PRCVCH-1395 4 Q, PRCVOI-1393 i l
T, PRCVQl-1390
. V, PRCVO!-1389
. i RTD COLD LEG B NAVC0 2-2RC-8B '
C, 137-2RTD-3 RTD HOT LEG B NAVC0 ---
2-2RC-7B A1, 137-2RTD-6 A, 137-2RTD-5 l Page 8 of 22 Fonn No. 3-3048-1
FORM NIS-1 OWNERS' DATA FEPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
~
1.) Owner NORTHERN STATES POWER COMPANY 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA Address PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant Address WELCH, MINNESOTA e
3.) Plant Unit 2 4.) Owner (Certificate of Authorization)
' 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit -----
7.) Components Inspected Manu facturer Component or Manufac turer or Installer State or National Appur tenance or Installer Serial No. Province No. Board No.
B4.10 CONT'D ;
LETDOWN AND DRAIN NAVC0 ---
2-2RC-12 A, 107-2CVCS-2 B, PRRCll-250 RHR TAKE OFF B NAVC0 8-2RC-15B 8-2Ril-1B C, 9-2RHR-15A D, 9-2RilR-15 K, 9-2RHR-14B ACCUMULATOR NAVC0 - - - -
DISQlARGE E l 1
12-2SI-27B A. RHRRIl-23 REACTOR VESSEL NAVC0 -
, SAFETY INJECTION B 2-2SI-24B j A, PRSIll-345 I REACTOR VESSEL NAVC0 --- ---
SAFETY INJECTION A 4-2RC-14A l A. RHRRH-33 l 1
- -- l PZR SAFETY B NAVC0 6-2RC-20B A2, 112-2RC-7 )
i I
Page 9 of- 22 Fona No.. 3-3048-1 e
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (certificate of Authorization) 5.) Conrnercial Service Date 12-21-74 6.) National Board Number for Unit -----
7.) Components Inspected Manu fa cturer Component or Manufac turer or Installer State or. National Appurtenance or Installer Serial No. Province No. Board No.
B4.10 CONT'D PZR SURGE NAVC0 1-2RC-4 C, 134-2SL-3 D, 134-2SL-4 B4.12 PRESSURE - RETAINING BOLTING PZR SAFETY A NAVC0 -----
6-2RC-20A 12 FLANGE BOLTS ,
@ RV2-8010A SEAL INJECTION B NAVC0 FLANGE BOLTS
- 1 thru #4 F
@ W-2 B5.0 PUMP PRESSURE BOUNDARY ,
e REACTOR COOLANT PUMP FLYWHEELS R.C. PUMP 21 WESTING- W510 ---
- HOUSE FLYWHEEL BODY t
PERIPHERY KEYWAY CORNER R.C. PUMP 22 WESTING- W515 ----
FLYWHEEL BODY HOUSE PERIPHERY KEYWAY CORNER l
Page 10 of 22 Form No. 3-3048-1
+ - . .
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS f
(As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 Address WELCH, MINNESOTA a
3.) Plant Unit 2 4.) Owner (Certificate of Authorization)-----
5.) Comercial Service Date 12-21-74 6.) National Board Number for Unit -
7.) Components Inspected Manu facturer Component or Manu fac turer or Installer State or Nacional Appurtenance or Installer Serial No. Province No. Board No.
B6.9 PRESSURE RETAINING BOLTING ACCUMULATOR NAVC0 --- ---- ---
DISOIARGE B 12-2SI-27B 2-8841B SAFETY INJECTION NAVC0 --- - - - - ----
IIIGH A 6-2RC-13B 2-8842A RTD COLD LEG A NAVC0 - - - - --- - - - -
2-2RC-8A 2-RC-1-7 RTD COLD LEG B NAVC0 ---- ----- ----
2-2RC-8B 2RC-1-15 2RC-1-16 ;
e RTD HOT LEG A NAVC0 - - - - -
2-2RC-7A
{ 2RC-1-9
. 2RC-1-10 RTD HOT LEG B NAVC0 - - - - - - - - ----
2-RC-7B 2RC-1-13 PZR RELIEF B NAVC0 ---- --- ---
3-2RC-21 2-PCV-430 Page 11 of ~ 22 Form No. 3-3048-1
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERr2ING PLANT, UNIT 2 Address kTLCH, MINNESOTA w
3.) Plant Unit 2 4.) Owner (Certificate of Authorization)
- 5.) Comercial Service Date 12-21-74 6.) National Board Number for Unit ----
7.) Components Inspected Manu facturer Component or Manu fac turer or Installer State or National Appur tenance or Installer Serial No. Province No. Board No.
B6.9 CONT'D REACTOR VESSEL NAVC0 ---- ---
SAFETY INJECTION LOW A 6-2RC-14A 2-8844A LETDOWN LINE NAVC0 --- - - - - ----
2-2RC-12 2-RC-1-5 ,
1 l
l l
- l e
l l
l l
Page 12 of '22 Form No. 3-3048-1 i
.I
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTHERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLTS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 ,
g Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) Owner (Certificate of Authorization) 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit----
7.) Components Inspected Manu facturer Component or Manu fac turer or Installer State or National Appur tenance or Installer Serial No. Province No. Board No.
ASME CLASS 2 C2.0 PIPING C2.1 CIRCUMFERENTIAL BUTT WELDS FEEDWATER A NAVC0 16" W-161 W-174 W-177 BASEMETAL W 175 TO W 177 ,
FEEDWATER B NAVC0 16" W-133 BASEMETAL W 132B TO W 133
, C2.5 INTEGRALLY WELDED SUPPORTS a FEEDWATER A NAVC0 SUPPORT A o Wil-66
- SUPPORT B FWH-68 ,
SUPPORT C WH-61 l
SUPPORT E t Wii- 73 l
l Page 13 o f 22 l
Form No. 3-3048-1
a FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS i
(As Required by the Provisions of the ASME Code Rules)
NORIllERN STATES POWER COMPANY 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 Address WELCH, MINNESOTA 6
3.) Plant Unit 2 - 4. ) Owner '(Certificate of Authorisation) -----
'. 5.) Comerc '.at Service Date 12-21-74 6.) National Board Number for Unit ---- ;
I 7.) Components Inspected Manu fa c turer ;
Component or Manufacturer or Installer State or National I Appurtenance or Installer Serial No. Province No. Board No. ;
C2.5 CONT'D SUPPORT F - - - -
Wil-70 i SUPPORT H -- - -----
Wil-71 SUPPORT I ---- - - - - --- !
WH-75 \
l SUPPORT J --- ,
Wit-60 SUPPORT K ---- ----
Wil-58 SUPPORT L _____ _____ _____
Wil-53 t -
FEEDWATER B NAVC0 - - - - ---
SUPPORT A
- Wil-67 SUPPORT B -
Wil-65 -
SUPPORT C ---- -
FWit-64 SUPPORT D ---- ---
WH-69 Page 14 of 22 Forn No. 3-3048-1
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Requaed by the Provisions of the ASME Code Rules) 1.) Owner NORTilERN STATES POWER COMPANY Addrese, 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE-ISLAND NUCLFAR GENERATING PLANT Address WELCH, MINNESOTA y
3.) Plant Unit 2 4.) Owner (Certificate of Authorization) o 5.) Consnercial Service Date 12-21-74 6.) National Board Number for Unit -~~~~
7.) Components Inspected Manu facturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
SUPPORT E -- -
Wil-63 ,
SUPPORT F ----
Wit-62 SUPPORT G -- ---
Wil-59 SUPPORT H ----
Wll-54 C2.6 SUPPORT COMPONENTS FEEDWATER A NAVC0 --- - - -
g ---
SUPPORT D Wit-72 %
SUPPORT G ---
,- Wil-74 FEEDWATER B NAVC0 ---- ----
o GUARD PIPE o 8 SUPPORTS Page 15 of 22 Form No. 3-3048-1 e
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner OREM SMES NR NM Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT Address WELCH, MINNESOTA
, v 3.) Plant Unit 2 4.) Owner (Certificate of Authorisation) ---
5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit -
7.) Components Inspected Manu fa cturer Component or Manu fac turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
SEISMIC BOLTING COMPONENTS STEAM CENERATOR NUMBER 21 WESTINGHOUSE 1181 ----
68-39 SNUBBER #2 - - - - ---- ----
2 PINS SNUBBER WALL BOLTS -- --- - - - -
5 BOLTS SNULBER BOLTS -- -- ---- - - - - l 8 BOLTS RING CONNECT BOLTS #1 --- - - - - --
I 10 BOLTS RING WALL BOLTS --- ----- - - - -
10 BOLTS COLUMN #2 ---- ---
2 PINS l 1
- COLUMN #2 --- 1 P BASE ANCHOR BOLTS '
8 BOLTS COLUMN #2 ---- ---
COLUMN CONNECT BOLTS l
4 BOLTS l
COLUMN #2 ---- ----- ---
HELI-COIL SCREWS l 6 SCREWS l 1
l Form No. 3-3048-1 Page 16 of 22
h FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)
NORTHERN STATES POWER COMPANY 1.) Owner 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA l Address PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 2.) Plant WELCH, MINNESOTA v
Address -
3.) Plant Unit 2 4.) Owner (certificate of Authorisation) 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit ----
7.) Components Inspected i
Manu facturer component or Manu facturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No. ,
o STEAM GENERATOR NUMBER 22 WESTINGHOUSE 1182 ----- 68-40 i SNUBBER #2 - - - -
2 PINS SNUBBER WALL BOLTS 5 BOLTS SNUBBER BOLTS 8 BOLTS RING CCNNECT BOLTS #1 10 BOLTS t
RING WALL BOLTS 10 BOLTS COLUMN #2 2 PINS
^. ----- -- -
COLUMN #2 BASE ANCHOR BOLTS
- 8 BOLTS COLUMN #2 COLUMN CONNECT BOLTS 4 BOLTS COLUMN #2 l HELI-COIL SCREWS 6 SCREWS l
Page 17 o f 22 Form No, ~-3048-1 3
l
FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NORTHERN STATES POWER COMPANY Address 414 NICOLLET MATT. MTNNFAPOf.TR_ MTMNFROTA 2.) Plant PR ATRTF TRT.AND Nffff.P AR CFNFRATTMC PT. ANT. IINIT 2 Address WELCH. MINNESOTA w
3.) 2 4.) ~~-
Plant Unit Owner (certificate of Authorization) 1 5.) Commercial Service Date 12-21-74 6.) National Board Nuinber for Unit -
7.) Components Inspected '
Manu fa cturer Component or Manu fac turer or Installer State or National l Appurtenance or Installer Serial No. Province No. Board No.
PRESSURIZER WESTINGHOUSE 1191 ---- 6857 BASE ANCHOR BOLTS -- -----
8 BOLTS ACCUMULATOR A DELTA SOUTHERN ----- -----
BASE ANCHOR BOLTS 8 BOLTS ACCUMULATOR B DELTA SOUTHERN ----- - - - -
BASE ANCHOR BOLTS !
8 BOLTS l
REACTOR COOLANT I PUMP NO. 21 WESTINGHOUSE W510 -- ----
COLUMN #2 ----- ---- - - - -
2 PINS l COLUMN #2 ----- - - - - --
BASE ANCHOR BOLTS
- 8 BOLTS COLUMN #2 --- ---- -
COLUMN CONNECT BOLTS 1 6 BOLTS '
l COLUMN #2 ----- ---- ----- I TIE BACK 30LT COLUMN #2 - --- - --
TIE BACK PIN l
Forin No. 3-3048 1 Page 18.of 22
'I
J FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) 1.) Owner NOREEM STATES NR CMM Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 .
tr Address WELCH, MINNESOTA 3.) Plant Unit 2 4.) owner (certificate of Authorisation)----
5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit----
7.) Components Inspected ,
?
Manu facturer
- Component or Manufac turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
REACTOR COOLANT PUMP 21 CONT'D PAD #1 THROUGH ANCHOR' BOLTS 2 BOLTS PAD #3 LAT'L SUPPORT WALL BOLTS 3 BOLTS r
REACTOR COOLANT WESTINGHOUSE W515 ---
PUMP NO. 22 COLUMN #2 2 PINS COLUMN #2
. BASE ANCHOR BOLTS 8 BOLTS COLUMN #2 l A COLUMN CONNECT BOLTS
^ 6 BOLTS a
COLUMN #2 TIE BACK BOLT COLUMN #2 TIE BACK PIN Page 19 of 22 Form No. 3-3048-1
FORM NIS-1 OWNERS' DATA REPORT FOR INSEP.VICE INSPECTIONS (As Required by the Provisions of.the ASME Code Rules)
NORTHEPN STATES POWER COMPA!W 1.) Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.) Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 Address WELCH, MINNESOTA y
~~
3.) Plant Unit 2 4.) Owner (Certificate of Authorization) t 5.) Commercial Service Date 12-21-74 6.) National Board Number for Unit ----- -
7.) Components Inspected Manu fa cturer Component or Manu fac turer or Installer State or National ,
Appurtenance or Installer Serial No. Province No. Board No.
REACTOR COOLANT PUMP NO. 22 CONT'D PAD # 1 THROUGH ANCHOR BOLTS ,
2 BOLTS PAD #3 LAT'L SUPPORT WALL BOLTS ,
3 BOLTS s
s.
7 Page 20 of 22 Form No. 3-3048-1
FORM NIS-1 (back) 8.) Examination Dates 1-2-80 to 2-4-80 9.) h.spection Interval 12-21-74 to 12-21-84 10.) Abstract of Examinations.
This was the second inservice inspect 1.a in the Second Period of the First Ten Year Inspection Interval. The examinations completed approximately 30% of the required pressure retaining components and their supports of the reactor coolant I and associated auxillary systems classified as ASME Class I. In addition, 100%
of the feedwater piping welds and base metal required by IE Bulletin No. 79-13, 100% of the required Seismic Bolting Program, 100% of the reactor coolant pump d flywheels, and 100% of the required visual examinations of the reactor vessel internals was performed. Eddy Current examination requirements for steam gen-erator tubes during this outage was also completed in accordance with Prairie
! Island Technical Specifications, Section T.S. 4.12.
11.) Abstract of Conditions Noted.
Other than steam generator (S.G.) tubes, there were no other signs of degradation to systems scheduled for examination.
The eddy current inspection revealed for the first time tube deteriation. This deteriation was determined to be tutu wastage (corrosion) and confined to the cold Icg (outlet) side at the outer periphcry of the tube bundle for both S.C.'s.
There were a total cf 10 and 43 tubes for S.C. No. 21 and No. 22, respectively, that were found exhibiting wastage;t20% of tube wall. One tube in S.G. No. 21 l was found to have been damaged by a loose flow lane blocking device.
The only anomalies detected were: one nut not flush in RTD Cold Leg A, Hanger "B1"; two loose nuts on RTD Hot Leg B, Hanger "Al"; three nuts not flush on Reactor Coolant Pump 22 Through Anchor Bolts; a missing nut on Feedwater Loop A, Hanger "K"; two loose nuts on Feedwater Loop A, Hanger "A"; two loose nuts on Feedwater Loop B, Hanger "A"; one nut not flush on Feedwater Loop B, Hanger G; one linear PT indication on Pressurizer Spray Weld 22B; five linear ai.d several rounded PT indications on Pressurizer Safety Line A Welds 1 and 1A S.E., and several linear MT indications on Feedwater Loop B Weld FW 133.
12.) Abstract of Corrective Measures Recommended and Taken.
All degradated S.C. tubes with wall thinning or damage > 43% were explosively plugged. The locating and locking mechanism for the flow lane blocking device was improved, and as a preventive measure the tubes that are directly in line with the tube lane blocking devices (Row 1 Column 1 and Row 1 Column 94) were
. plugged. An augumented water chemistry sampling and testing program for the Plant's secondary water system has been established to determine the cause and y source of the wastage (corrosion); so that preventive action in the future can.
be taken.
i All anomalies, with the exception of the rounded PT indications on Pressurizer Safety Line A, were corrected. The locse nuts on the Hangers and on the Through '
Anel Bolts were all tightened. The missing nut on Hanger "K" was replaced.
The : linear PT indication on Weld 22B, the five linear PT indications on Welds 1 anu 1A S.E. and several MT on Feedwater Loop B Weld FW 133 were all buffed off j the surface. The several rounded indications on Pressurizer Safety line A were i accepted as is, based on the PT examination results, radiographs, visual exam-inations with 10% magnification, and ASME Section XI acceptance criteria. The above hangers that had indications requiring corrective action will be reexam-ined during the next scheduled outage. l (Continued on next page)
L Page 21 of 22
We certify that. he statements n.ade in this report are correct a . :'
- ie exarninations and coricctive measures taken conform to the rules of the ASt1E Code, S: Lion XI, Date . iw,/ / 19 70 Signed /' k S88 P = 0.By #
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- Ouner f %) ~ l if Certificatc of Authorization No. (if applicable) .,h Expiration Date //
CEH r!FI(ATE OF IiWI.RVICC IllSpECTION I, the undersigned, holding a valid cc.mmission issued by the !!ational 11oard of Boiler and Pressure Vessel Inspectors and/or the Stace or Province of /U,hyen,/q. and employed by. A , , F b > f % /n h L *T w 6 of /LMA>d C6u, have inspected the com-to 2-9eFC P"""nts lescribed i n t h i s Dwne r ' s Da t a it epo r t 'du r i ng the period /-2 fd 1
and state that to t he 'ies t of my knowledge an.1 helief, the Owner has performed examinations and takra corrective reasures described in this owners' Data Report in accordance with the requirements of the ASME (. ode,Section XI.
Ily signing .his certificate ne it he r the luspector nor his employer makes any warranty, expressed or inpland, concerning t he examina t ions and correct ive n. asures described in this Nno r . ' liara Peport. l'o r t h e rmo re , neither the inspect.or nor his employer shall be liable in any manner for any personal . . , or property damage or loss of any kind ar i sins; f rom or connec t ed with t his inspection, l>a t a kpdrl ] _, 14 SO
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