ML19347F303

Inservice Insp Rept on 810223-0323.Describes Exam Results of Pressure Retaining Components & Supports of Reactor Coolant, Reactor Pressure Vessel & Bolting of Seismic Supports. Integrity of Sys Has Been Maintained

ML19347F303
Person / Time
Site:	Prairie Island
Issue date:	04/27/1981
From:	Dahlman L, Hansen D, Krumpos P NORTHERN STATES POWER CO.
To:
Shared Package
ML19347F302	List: ML19347F301 ML19347F303
References
NUDOCS 8105180306
Download: ML19347F303 (200)

Text

O NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT II

. INSERVICE INSPECTION - EXAMINATION

SUMMARY

RRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT II February 23 to March 23, 1981 REFUELING OUTAGE No. 5 INSPECTION PERIOD 2

]

Report Date:

Prepared by: L C Dahlman, a

April 27, 1981 M&SP Specialist D B Hansen Assoc M&SP Engineer Commercial Service Reviewed by:

M '[/T' Date: December 21, l'/74 PJKrpmds/)

Superintendent Mh,ecerials and Special Processes l

i j

lm

/

Approved by:

A

/hv ze Jf W Ariddrson I

/ eneral Superintendent Production Plant Maintenance I

l

%nos/Koss

INSERVICE INSPECTION - EXAMINATION

SUMMARY

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2

- INDEX -

1.0 Introduction 2.0 Summary of Results 3.0 ASME Class 1 and 2 Components 3.1 Examination Plan 3.2 Examination Methods 3.3 Examination Pcocedures 3.4 Equipment and Materials 3.5 Personnel 3.6 Evaluation 3.7 Examination Reports and Documentation 4.0 Examination of Reactor Pressure Vessel and Outlet Nozzles 5.0 Seismic Bolting Appendix A - ASME Class 1 Examination Inservice Inspection - Examination Summary Tables:

Table Sl.1

- Reactor Vessels Table S1.2

- Pressurizer Table Sl.3.1

- Steam Generators Table Sl.3.2

- Regenerative Heat Exchanger Table S1.3.3

- Excess Letdown Heat Exchanger Table Sl.4

- Piping Pressure Boundary Table St.5

- Reactor Coolant Pumps Table Sl.6

- Valve Pressure Boundary Table II - Baseline Comparison Summary Table III - Isometric Summary Appendix B - ASME Class 2 Examins*; ion Inservice Inspection - Examination Summary Tables:

Table S2.1

- Pressure Vessels - Steam Generators Table S2.2.1

- Piping-Circumferential Butt Welds Table S2.2.2

- Longitudinal Weld Joints in Fittings Table S2.2.3

- Branch Pipe to Pipe Weld Joints Table S2.2.4

- Piping - Pressure Retaining Bolting Table S2.2.5

- Piping - Integrally Welded Supports Table S2.2.6

- Piping - Nonwelded Supports Table S2.3

- Pumps Table S2.4

- Valves Table II - Baseline Comparison Summary Table III - Isometric Summary Page 1 of 2

Appendix C - FSAR Augmented hamination

- No examinations scheduled this outage Appendix D - Seismic Bolting Ex==4 nation Inservice Inrpection - Examination Susumary Table:

Table SB - Seismic Bolting Table II - Baseline Comparison Summary Table III - Isometric Susunary Appendix E Table I

- Personnel Listing Table II - Ultrasonic Calibration Blocks Table III - Procedure Listing Table IV - Equipment and Materials Appendix F Form NIS-1, Owners' Data Report for Inservice Inspections 9

e a

9 Page 2 of 2

INSERVICE INSPECTION - EXAMINATION

SUMMARY

PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 February 23 to March 23, 1981

1.0 INTRODUCTION

This report is a summary of the examinations performed during the fifth inservice inspection at the Prairie Island Nuclear Generating Plant -

Unit 2.

This was the last inservice inspection conducted for inspec-tion period two.

The examinations were performed during the plant's fif th refueling outage from February 23 to March 23, 1981. Prairie Island - Unit 2 began commercial operation on December 21, 1974.

This report identifies the components examined, the examination met:iods used, the examination number; and, summarizes the examination results of each of the following areas:

1.

Pressure retaining components and supports of the reactor coolant and associated systems cicssified as ASME Class 1 and ASME Class 2.

2.

Reactor pressure vessel examinations; including examination of nozzle bores for underclad cracking.

3.

Bolting of seismic supports classified as ASME Class 1.

2.0

SUMMARY

OF RESULTS The evaluation of all the results from the inservice examinations indicated that the integrity of these systems has been maintained. ine following is a list of all anomalies detected:

System Item ID Exam Method Type & Number of Indications PER Safety A W-1 PT 2 linear W-1A S.E.

PT 2 linear & several rounded PER Safety B W-1 PT 1 linear W-1B S.E.

PT 6 linear PER Spray W-22B PT 3 linear FW Loop A W-177 MT 4 linear A, Hanger MT 1 linear FW coop B W-133 MT 22 linears PT 23 linears l

l MS Loop A G, Hanger VT Loose bolt H. Hanger MT 2 linears MS Loop B 0, Hanger VT Nut not flush with base RCC Loop A RCC-A-6 PT 14 linears 1

RVSI B, Hanger PT 6 linear Page 1 of e

System Item ID

_, Exam Method Tvpe & Number of Indications RTD Loop A B1, Hanger VT Hanger tilted S/G 21&22 Primary MT 1 bolt - 1 linear, 1 bolt-Manway Bolts dented threads S/G 21&22 Secondary VT 6 bolts - dented threadr Manway Bolts 21 bolts gouged S/G 21 Upper Ring VT 2 loose bolts Grinder Connec-ting Bolts S/G 22 Top Column VT 2 loose nuts Connecting Bolts RCP 21 Tie Back Bolts VT 1 loose nut RDV Loop A Outlet Nozzle UT 22 indications Bore Region RPV Loop B Outlet Nozzle UT 83 indicatiorm Bore Region All anomalies, with the exception of the rounded PT indications on Pressurizer Safety Line A and the indications on the Reactor Pressure Vessel Outlet Nozzle Bore Region, were corrected. The loose nuts and bolts were tightened, and the tilted hanger was straightened. The linear MT and PT indications were removed by light hand grinding and blending the surface smooth. The bolts with major steam gouges and linear indication were replaced. All indications were correctad and reexamined with the same method that located them.

The several rounded indications on Pressurizer Safety Line A were accepted as is, based on Westinghouse's evaluation conducted in the January 1980 outage. The indications on the Reactor Pressure Vessel outlet Nozzle Bore Region was also accepted as is, See section 4 for acceptance analysis, i

3.0 ASME CLASS 1 AND 2 COMPONENTS 1

l 3.1 Examination Plan l

The examination plan focused on the pressure-retaining components i

and their suppor s of tha reactor coolant and associated auxiliary systems classified as A5!P Class 1 and Class 2.

t l -

The examination plan was based on the examination requirements of the ASME Boiler and Pressure Vessel Code Section XI, 1974 l

Edition through and including the Summer 1975 Addenda, and com-l plied with Prairie Island's Technical Specification, Section TS 4.2.

l The examination is in accordance with the program submitted to the l

United States Nuclear Regulatory Commission on February 1, 1978 I

entitled, "ASME Code Section XI Inservice inspection and Testing l

Program and Information Required for NRC Review of Requests for l

Relief from ASME Code Section XI Requirements."

l l

l Page 2 of 8

3.2 Examination Methods Ultrasonic examination methods and techniques were 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 height (amplitude) and the second channel was calibrated to indicate metal path (range) to the 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 examinations were performed using color contrast-solvent removable materials. Magnetic particle examinations were performed using e: ther a yote with dry powder or an A-C L-10 coil with fluorescent prepared batn.

All v_sual examinations were aided when necessary with artificial light 1ng and verified for adequacy with an 18% neutral grey card with a 1/32 inch black line.

3.3 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 other examination proce-dures complied with the requirements of the 1974 Edition through ard including 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.

3.4 Equipment and Materials All equipment and expendable materials used in the examinations are listed by either serial number or type along with their respective calibration date or batch number in Table IV of Appendix E.

l The ultrasonic calibration standards used in the examination are l

listed in Table II of Appendix E.

These standards are owned and l

maintained by NSP at the plant cite.

3.5 Personnel Northern States Power Company contracted Lambert, MacGill, Thomas, Inc. to perform the examinations. Hartford Steam Boiler Inspec-tion and Insurance Company, representing ANI, provided the a

Authorized Inspection.

l All personnel involved in the performance or evaluation of exami-nations are listed along with their title, organization, and ASNT l

Level cf certification in Table I of Appendix E.

Certifications for examination personnel are maintained on file by Northern States Power Company.

Page 3 of 8

3.6 Evaluation Any indications disc 1ceed in the examinations were evaluated by the examiner at the time, in accordance with the rules of the procedure and ASME Section XI.

The ultrasonic examiner was aided in his evaluation by a calibra-tion performed on a standard reference before each day's examina-tion, checked before and after each individual examination, and at intervals net exceeding four (4) hours.

In addition, the ultrasonic data was recorded on strip charts which were made a part of the inspection report, and permitted further evaluation.

3.7 Examination Reports and Docurggiation All examination reports and docamentation are maintained on file by Northern States Power Compeny. Table I of Appendices A, B and D identifies the examinat. ion report number (s) for each item examined. Many of the iteus identify more than one examination report because of the different types of examinations performed on the item.

Table I of Appendix A, B, and D summarizes 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 examina-tion requirements. For retrieval purposes, the prefix of the inspection report number corresponds with the year that the insp-ection was performed. The examination report numbers for this outage are prefixed with "81 ".

Table II of Appendix A, B, and D compares the baseline examination results with *.he results obtained during this examination. Table III of Appendix A, B, and D identifies the isometric drawings that were used for the examinations. The personnel, ultrasonic cali-bration blocks, procedures, equipment and materials that were used for the inspection are identified in the tables of Appendix E.

Appendix F contains the Form NIS-1, entitled " Owners" Data Report for Inservice Inspections".

4.0 EXAMINATION OF THE REACTOR PRESSURE VESSEL AND OUTLET N0ZZLES Westinghnuse was contracted to perform the remote ultrasonic and visual examinations of the reactor pressure vessel. The visual examina-tion program consisted of two reactor vessel shell clad patches each bein3 36 square inches. The rer.otely operated ultrasonic device was utilized to perform examinations on the shell-to-flange weld, vessel flange ligaments, outlet nozzle-to-weld, and for investigating for the presence of underclad cracking in the reactor vessel outlet nozzle bore region, ihe examinations were performed in accordance with the applicable requirements of Prairie Island's Technical Specification, Section TS 4.2, and the 1974 Edition of ASME Section XI through and including the Summer 1975 Addenda. There was no reportable indications revealed during all the examinations with the exception of the outlet nozzle underclad cracking examinations.

These examinations disclosed 22 discrete reflectors in the cylindrical section of the Loop A nozzle bore and 83 discrete reflectors in the Loop B nozzle bore. There was no Pace 4 of 8

reportable indications detected in the taper regions of either loop A or B nozzles.

The following is a summary of the underciad examination results and bases for evaluation. This information was received by letter from Mr. J.A. Vano, Manager Inspection Services, Westinghouse Electric Corp.

Examinations were conducted from the inside diameter of the nozzle using dual element, transmit-receive, 2.25 MHz, focused immersion search units inclined to generate lonaitudinal waves at a refrac.ed' angle of 55 to 60. Test sensitivit.y was established on the flat bottom of a 2mm diameter hole drilled just below the clad / base metal interface in a representative calibration block. Secnning was conducted on 3/16 inch increments in both circumferential directions. Any indications equal to or exceeding the primary reference response was recorded. Reflector lengths were measured via a 12 dB drop method. This procedure provides a sensitivity 14 - 16 dB greater than current ASME XI requirements and has been demonstrated capable of resolving reflectors as small as 1 to 2mm deep and 3 to 4tr long.

The fact that reflectors are' confined to areas in the nozzles clad with two layers suggests they may indicate the presence of underclad cold cracking. However, the reflector. are located at depths which indicate they may be confined to the cladding, and further, only half of the reflectors are detectable in both scanning directions. Laboratory studies have consistantly shown that sub-clad cracking is detectable from both directions. Since a definite conclusion regarding the nature of the ultrasonic reflectors is not available, all will be conservatively assumed to be planar surface defects just beneath the cladding for analysis purposes.

An ASME XI evaluatibn of these reflectors requires a measurement of their through-wall extent. Current NDE technology does not permit a direct, accurate, measurement of this dimension thus a reliable method of estimating these depths is necessary.

Assuming the worst case, that of underclad cold cracking, exhaustive l

destructive analysis of nozzle strip clad with multiple layers have demonstrated these cracks are always confined to the depth of the heat affected zone of the second layer of cladding, 0.295 inches (7.5mm) maximum. The Prairie Island Unit II nozzles were clad using a process j

with a lower heat input, dual-wire / submerged-arc. Thus an essumption that all reflectors are 0.295 inches deep is conservative for ASME XI l

inservice evaluation purposes.

l -

The criteria of I;'A-3330 for multiple planar flaws have been applied where necessary and all reflectors or groups of multiple reflectors have been characterized as surface flaws, IWA-3310, with depths equal to O.295".

l The thickness of the bore region of the Prairie Island Unit II nozzles i

is 10 inches. This thickness is determined per Table IWB ~n12, note 2, where t=tni + cn2 Dimension ent' and tn2 were btained from nozzle 2

l fabricacion drawings.

i Page 5 of 8

Th3 long3st ultrestnically meccur:d rafisctor obsarv:d in tho outist nozzle bore regions was 1.0".

These reflectors have been evaluated per IWB-3512, ASME XI, 1977 Edition. Assuming a depth of 0.295", the allowable a/t value is 3.5% while the actual a/t value for this case is 2.95%.

Reflectors in the vicinity of the safe end welds have been evaluated per IWB-3514.4 (a), which refers to Table IWB-3514.2. The longest reflector detected in these areas was 0.86".

Assuming a depth of 0.295", the allowable a/t value is 14.2%, while the actual a/t value for this case is 12.3%.

Thus, based on the conservative assumption that reflector depths are 0.295" (7.5mm), it is concluded that all ultrasonic reflectors detected in the Prairie Island loop A and B outlet nozzle bores meet the inservice acceptance criteria of IWB-3500, ASME XI, 1977 Edition.

Structural Materials Engineering (W. Bamford) perfocmed a fractute evaluation on the locations where the indications were detected, even though it was not required by the rules of Section XI of the code because the indications were small. In the nozzle bore region the critical flaw depth was found to be equal to the wall thickness for normal and upset transients, and to be equal to 2.53 inches for the governing accident condition, the larger LOCA. The crack growth of indications beneath the cladding is negligible, so the following results obtain:

ai = 2.55 a

= 12.15 (wall thickness) c ag = 0.295 Therefore the evaluation criteria of IWB 3600 are met:

ag < 0.5 at ag < 0.1 a

~

e In the nozzle safe end region, the critical flaw size for both normal upset and faulted conditions is equal to the wall thickness, because the stresses are very low.

The fatigue crack growth is also negligible in this case, so the fellowing results are obtained:

ag = 0.295 a

= 2.53 c

ai = 2.53 Page 6 of 8

I The criteria used here are based on the calculated stress intensity factors for the observed indication for faulted conditions Kg (a=.295) = 33.0 kai 9in for normal upset conditions Kt (a=.295) = 36.0 kai E K

=Kyc = 200 kai Nin at the governing time for both normal y3 and faulted conditions.

Therefore the criteria for integrity are met:

410 Kr (nomal-upset) = 36 Q 10 114 < 200

=

7K (f..lted) 33 Q 2 46.7 < 200.

=

=

In conclusion, the reflectors meet the acceptance standards of ASME Section XI 1977 Edition. This conclusion was verified by a detailed fracture mechanics analysis perfomed by Westinghouse for Northern States Power Company. Copies of the procedures, inspection programs, inspection data and evaluation, and personnel certificatio a are con-tained under a separate report prepared by Westinghouse. This report will be maintained on file by Northern States Power Company.

5.0 EXAMINATION OF SEISMIC BOLTING The entire seismic bolting program, partially due to the problems that have bear occuring with high strength bolting materials, was scheduled for examination.

This program includes the bolting, anchors, nuts, and pins on tne steam generator, reactor coolant pumps, accumulators, and pressurizer support structures. All items were examined visually, and where feasible, by ultrasonic examination techniques.

la addition, a program for replacing each of the 48 helicoil bolts was scheduled for implementation during this outage. The helicoil bolts (so named because of the helicoil insert utilized in the base metal) form the connection between the steam generator channel head casting and the support structure it rests on.

This replacement was scheduled due to the problems encountered during the detensioning program on Unit I's bolts during the September 1980 cutage.

When the problem on Unit I's helicoil boles was identified (September 1980 outage), Unit 11 was shut down and the helicoil bolts on both steam generators were ultrasonically examined. The examinations revealed 1 bolt without a back reflection, that subsequently sheared off during detensioning, and 2 bolts with a reduced back reflection. These two

~

bolts were removed and a fluorescent magnetic particle examination was perfomed on them revealing a linear indication in the thread relief area adjacent to the bolt head on each bolt. Two of the other 45 bolts were removed and a magnetic particle examination was perfomed on them with no apparent indications. These two bolts were used to replace the two with indications (beca use all three of the bolts with indications were on the same support leg). The remaining bolts were detensioned and reexamined ultrasonically with no further indications.

Page 7 of 8 l

\\

These bolts were all removed during this outage and fluorescent magnetic particle and an ultrasonic examination was performed on each bolt. The ultrasonic examinations revealed one bolt with a reduced back reflection from the head end.

The magnetic particle examinations revealed linear indications in the thread relief area adjacent to the bolt head on 36 of the 45 bolts. The majority of these indications were very small and inter-mittent. All the helicoil bolts were replaced with bolts of an approved design.

All other indications disclosed during the examinations were resolved prior to plant heat up.

The loose nuts and bolts were tightened. All indications were corrected and the areas were reexamined with the same method that located them.

i Page 8 of 8

APPENDIX A ASME CLASS 1 - EXAMLNATION Page 1 of 1

-er-r---,,---w.v,-,-----,,-

-,r_,_,_-,-.,-,,,n----,_.-,,_,,____,-..-~.,________._._-w,-.---_.--_.---+~,,,-ve,,

- -, -... -,..,. ~. -, - - __

i!

S T

T T.

NO.

R R

ON IN O

O F

O I

P TT E

E CR R

R EO V

P P W

W 1

S E N

u IR R

R 1

1 S

tc W_

W_

A

/

1 E

E T

8 LEI BG AA 5

TP 3

64 0

N 1

O I

O I

9 T

2 5

M A

3 E

MC T

EI 245 E

F I

TI I2 IT OOO O2 2

R N

O E

NNN H

1 0

J D

E EEDDD D1 O

A I

O NNLLL U

I' NNEEE I2 M

t

- - % W%

S1 9

.M TMA 3

0 -

X A

3 3

E D.

Q' T.

M E A 0

555 3

06 R

5 3

33 E

E E

PR E

E E

S E R

R E

OR N

IP H

N WH IH I I

- - T C

~

Y RA S

S M

M D ME D

D L

I R

I W O S

E S

A A D

S E

S M

E N

U S

D N

- N A T B

W D

D S

YqI R C D

l T S N

I E

M I

I I

A B I

L M E A O

EDL A

E G

A C N E

L E H D A 0 l

A W I' Y I

I 1

E WI A W

N N

X I

l E

I D

R R P P E S EI E

A O

m E N O R O LD P G

L I

S L

T N L O

I E

E B U N A

N N E A F

T B

A D A

N A A G

1 E R

S I

NLE A G I

1 A

EO I

N E

I O E N D C

I AR I

N T 0

N DT L E I

R L

T 1

T F

I I

N DNE F A N 1.

A W D

E A N 0 A t

M N

U F h E

(

I E

O C A M C A B UCF I

O M

E IL T

M I

R S

H TI M O F R

LN G D m R

GIC D P SD T

C T

Y IDU T

E E

A I

D A I

U D E L F

)

R X

U I G

C U F L O C R I

E A R O RR L

1 M

SI N N N

R I

M E I

T T

D EC f

I I'

EE I

ES D W VW E2 E

I H E B C E G W S S M D N N W

G E

I I

C G

I O

N N R G N R O O O A A I

1 S A R

CIIAMSH(OA I

N N E E E E I

E E

I PTO I

I C

VHC I

F R T.

I I SNT E U C T

E ADP ME.YA TNS C

A B

C N

SAI G

L B

B B

N SE RI C 1

EEI HI V A-T HR BM 1

2 3

. 9 UE l

P RA E ST S

I l

l l

B B

B P

OR N NPI j

a iiJ 1

i

NORTilERN STATES POWER CO.

TABLE SI I PRAIRIE ISLAND UNIT 2

PAGE 2

op 5

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

REACIOR VESSEL

^

YS M p

SUB INSP.

R EQ*D.

AfAT.

ITEM INSPECTtDN TE-D E I IO ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED 1

Bl.3 B-C (00tfr'D)

SIUD HOLE:

HEAD 'IO FIANGE WE 33%

33%

1'IEIU 16 77-W RPV REPORT &

EID NO. 6 77-74,73,75 TO 33%

33%

16 'IHRU 34 B1-141,143,144

'IMREE 33%

I Bl.4 B-D PRIMARY N ZZIE 'IO-VESSEL WEIDS A10 NOZFLE,7NSIDE RADIUSED SECTIONS j

REACIOR CNE COOUNf N0ZZIES CUTIET FOZZIES OE 1

1 BCC-A-1 77-W RPV REEORT

'IWO 1

1 BCC-B-1 81 _W RPV REPORT INIEP N0ZZIES

'IHREE 2

SAFETY IMJECTION

'DIREE 1

FOZZIES TIREE 1

l B1.5 B-E VESSEL PENEffRATINS, INCIDDING OCNIiOL HOD DRIVE Ato INSPIUMENTATIN PFNETTRATIWS GWrROL ROD PErd.'IY@.TIQE GE 3%

• 3

• EACH ITEM IIEPECMD

'IWO 3%

• 3 BY PUNP PERS0tMEL

'IMREE 4%

DURItG EAOi REACIOR VESSEL IEAKAGE

'IEST i

l rosses a7-247e e/7s Fosses poo. ese-sees PP9-A-2

NORTHERN STATES POWER CO.

TABLE S101 PRAIRIE ISLAND UNIT 2

PAGE 3

OF 5

INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

IEACIW VESSEL SUS INSP.

REQ D.

AMT.

BTEM

$NSPECTION N DE TION ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED I.

B1.5 B-E (CONP'D) mSTRUMENPATIN PENE1BATIW S OE 3%

• 3

• EACH ITEM INSPECPED

'INO 3%

• 3 BY PUNP PERSCIAEL

'1HREE 3%

mRING EAG REACIOR VESSEL EAIOGE *1TET REACIOR VESSEL LEAD VENP 1

• 1 1-21C-36 'IO 2-RC-8-5 Bl.6 B-F N0ZZLE TO SAFE END WEIDS REACIOR CWE COGANT 20ZZES OtrPLET N0ZZES OE 1

1 ICC-A-1 S.E.

77-W R W REPORT &

77420,112

'IWO 1

1 BCC-B-1 S.E.

81-W RW REPORT &

81-21 INLET N0ZZES

'IHREE 2

REACIOR VESSEL SAEETY INJECTIN N0ZZES lOZZ E A S.E.

OE 1

1

10. 1 77-W RW REPORT &

77423,113 IOZZE B S.E.

'IHREE 1

Bl.8 B-G-1 CIDSURE STUDS AND NLfrS QE 16 16 il 'IERU 616 77-W RW REPORP &

77-106 il '1HHU 616

' 78-84,99 (Mr WIX)

'IWO 16 16 617 'INRU #32 81-162,163,165,166 1HREE 16 i

FORD 4 4 7-245 S S/78 FOftta 960. 8S8-4 948 PP9-A-3

NORTHERN STATES POWER CO.

Tall.E S1.1 PRAIRIE ISLAND UNIT.

2 PAGE 4

OF 5

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

REAC'IOR VESSEL M

N YS D,E INSP.

R Eb'D.

AMT.

ITEM INSPECTION SUB E.

N

• Al TIOq ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED SIUD HOIES:

Bl.9 B-C-1 LIGAMENTS BEDEEN OE 16 16 12-22 & 29-35 77-H RW REPORT HIREADED SIUD fl0LES

'INO 14 14 9-11 & 36-46 81-W RW REPORT DIREE 18 B1.10 B-G-1 CIOSURE WASHERS AN_D_

Bl!SHINGS WPSHERS WE 16 16 PAIRS,1 'HIRU 16 77-W RW RdKRT

'INO 16 16 PAIRS,17 TIRU 32 81-164 MIREE 16 BUSHINGS

-NCtE-B1.11 B-G-2 PRESSURE RETAINING BOLTING NE 3

9 ALL 9 BOLTS 77-W RW REPORT

'IWO 3

9 ALL 9 BOLTS 81-T70 MIREE 3

Bl.12 B-H INTEGRALLY WELDED VESSEL SUPPORTS MIREE 2

31.13 B-I-1 CIDSURE HEAD CLADDING CE 2

2 HCP-1 & HCP-2 77-W RW REPORT

'INO 2

3 liCP-1,HCP-3 & HCP-4 81-T55 TIREE 2

Bl.14 B-I-1 VESSEL CIADDING CNE 2

2 VCP-1 & VCP-2 76-W INTERNALS RPF

'IWO 2

2 VCP-3 (2 PA'ICHES) 81-W RW REPORT MIREE 2

i roa = i1-. eve sire con

. isi-i...

PP9-A-4

2 NOllTHERN STATES POWER CO.

TA!LE S1 1 PRAIRIE ISLAND UNIT 2

PAGE 5

op,,. 5 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

REACIOR VESSEL N

SUS-INSP.

R EO'D.

AMT.

ITEM INSPECTION E.

N DE I TION ITEM PER.

AMT.

EXAM IGENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED i

1 4

Bl.15 B-N-1 VESSEL INTERIOR UPPER IN1ERHAIS AND OiE 76-W INIEINAIS RPr IDWER INTERNAIS

'IWO

~

i 91REE 80-W INIERIAIS RPf

~

, REPPESENTATIVE REGICNS CF '11M INPERIOR SWFACES i

Ato INTERNAIS MADC NYTRSIBW BY THE j

REMOVAL OF CX)MEON-l ENTS DURING NCRMAL l

REEUE11sU OPEilATION 31.16 B-N-2 INTERIOR ATTACHMENTS IDF APPLICABE AND CORE SUPPORT POR PWR'S 2

STRUCIURES B1.17 B-N-3 REMOVABM CORE SUPPORT WIREE

• 100% OF DIE VISU-APO VISUALLY ACCES-l SIB m SURFACES OF ME CORE SUPPORT

)

S110CIURE 1

{

Bl.18 B-O CONTROL ICD DRIVE HOUSINGS PERIPHERAL CRD HOUSINGS DIREE 2

t i

5 B1.19 B-P EXEMPTED COMPONENFS

• ALL COMPOtlafrS

• PERFOPMED BY ILANT EXEMPTED FROM PE3EiOtML IN ACCORD-l NOWBETRIC APO ANCE WIMI IWA-5000 j

SURFACE EXAMINATION DURING EACH SYSTEM i

BY I m-1233 MAKAGE 'IES"' AND EAG SYSTEM HYDID-SfATIC TEST REQUIhED BY IWB-5000 l

FORM I 7-24 76 s/70 FORM MO.458+9998 N ~

4 NORTHERN STATES POWER CO.

TABLE SI 2 PRA'RIE ISLAND UNIT _ 2 __...

PAGE 1

OF 2

INSERVICE 3NSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PRESSURIZER I

SUB INSP.

R EQ'b.

AMT.

ITEM INSPECTION E-DE TION ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMuaED i

B2.1 B-B IONGI'IUDINAL AND i

CIPI1]MFERElff1AL WEIDS IINGI'IUDINAL NEIBS 4

j ELD NO. 1

'IEREE 5'%

'IUREE 5%

)

ELD NO. 2 NE 5%

5%

BorICH 'IO 'IOP 76-45,67

'IND 5%

8%

W-5 DO E 11"78-104,112,118 t

(W)

CIRCUMFERENTIAL WEIDS EBOM NAMEPLATE:

NELD NO. 3 INE 1.7%

33%

+10 ' 'i0 +18 '

76-43,69

'IM) 1.7%

13%

+7'6" 'IO +10'8"78-105,115,122

'IMEE 1.8%

1 EID W). 4 WE 1.7%

33%

+8 ' 'IO +16 '

76-44,66

'IWO l.7%

6%

+8 '4" 'IO +9 ' 10"78-103,114,119

'IHREE 1.8%

g 1

NEID NO. 5 CNE 1.7%

33%

+10 ' 'IO +18 '

76-29,68

)

'IND 1.7%

12%

+6 ' 10" 'IO +9 '9"78-113,116,121

'IHREE 1.8%

B2.2 B-D N0ZZLE 'IO VESSEL WEIDS

-NONE-25/10 j

R2.3 B-E HEA'IER PENETRATIN

• EACH ITEM INSPEC'IED YRS-BY PLANT PERS0ttiEL B2.4 B-F N0ZZLE 'IO SAFE END WEIDS WE 2

2 W-1A S.E.(8010A) 76-26,53 j

W-1A S.E.(80108) 76-61,52 i

'INO 5

5 W-15 S.E.

78-31,100 W-1A S.E.(RELIEF) 80-58,87,170 W-22A S.E.(SPRAY) 80-57,85,168 W-1A S.E.(8010A)80-188,192,192R,192Ra W-1A S.E.(80108)80-189,131,191R 2

W-1A S.E.(8010A) 81-6,6R,37,63 W-1B S.E.(80108) 81-23,23R,39,62 mm 2

raggg;gg.m i

i NORTHERN STATES POWER CO.

TA"iLE S1.2 PRAIRIE ISLAND UNIT 2

PAGE 2

OF 2

INSERVICE INSPECTION-EXAMINATION SUfAMARY MAJOR ITEM:

PRESSURIZER EXAM COWMENT OR SYSTEM SUS INSP.

R EQ*D.

AMT.

ITEM INSPECTION mfd ITEM y'

I PER.

AMT.

EXAM IDENTIFICATION REPORTNO.

EE M NED B2.5 B-G-1 PRESSURE-RETAINING BOLTS

-NOTE-B2.6 Ato S' IUDS (> 2 IN. DIA.)

{

AND B2.7 (W)

FROM NAMEPLWE:

B2.8 B-H INTEGRALLY WEIDED VESSEL WEID SKIRT WEID WE 3.3%

3.3%

+8"'IO -8" 76-77

'INO 3.3%

23%

+6 ' 'IO +11 ' 9"78-106,107,117

'IHREE 3.4%

4 i

B2.9 B-I-2 VESSEL CLADDIt1G

'HIREE 36 SQ.

IN.

PA'IGi B2.10 B-P EXEMPIED COMPWENIS INSTRUMENT N0ZZE N'). 5A 'DIRD SH

• EAOi ITEM INSPECTED PENE'IRATIWS BY PLAlff PERSONEL SAMPLE N0ZZE

10. 6

• EACH ITEM INSPECTED PENETRATIN BY PLAlff PERSQt4EL B2.11 B-G-2 PhESSURE REffAINING EOLTING MANNAY BOLTS 04E 5

5 BOLTS 1 'DIRO 6 76-30

'INO 5

5 BOLTS 6 'DIRU 10 78-82 2

BOLTS 1 'DIRU 16 81-60

'HIREE 6

FORM 37 2476 5/78 FOnan No. ess-teel PP9-A-7

NORTHERN STATES POWER CO.

TATLE s1.3 1 0

PRAIRSE ISL AND UNIT _ ?

PAGE 1

OF 3

4 INSERV(CE !?iSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

STEAM GENERATORS I

^M N

8 SUB INSP.

R EQ'D.

AM1.

STEM INSPECTION TE-DE R Tl N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED I

B3.1 B-B IINGITUDINAL MO CIRCUMFERENPIAL WEIDS (N TIE PRIMARY SICZ IINGITUDINAL WEIDS

-NONE-(CW)

CIRCLMPERENPIAL WELDS ImOM NAMEPLATE:

SIEAM GENERA'IOR NO. 21 OE 1.9%

37%

+8" 10 +13'8"76-111,101,118 IWO 1.9%

8%

+23'8" "IO +26'8"78-108,110,120 THREE 1.8%

SPEAM GENERATOR NO. 22 OE 1.9%

31%

+2' 10 +13'76-112,102,119 4WO 1.9%

17%

+21'10" 10 +28'78-109,111,123 1HREE 1.8%

93.2 B-D NOZZLE TO IIEAD WEIDS

-NONP.-

B3.3 D-F NOZZLE TO SAFE END WEIDS JII:AM GENERATOR NO. 21 TWO 1

1 ROC-A-5 S.E.81-116,125 THREE 1

SPEAM GENERATOR NO. 22 CNE 1

1 BCC-B-5 S.E.

76,136,139 THREE 1

B3.4 B-G-1 PRESSURE RETAINING BOLTS

-tKNE-B3.5 AND STUDS (> 2 IN. DIA.)

AND B3.6

-NONE-B3.7 B-II INTEGRALLY IELDED VESSEL SUPPORTS roam ar-asis sire ronu no.........

PP9-A-8

NORTHERN STATES POWER CO.

TA'lLE S1.3.1 PRAIRIE ISLAND UNIT 2

PAG.E 2

OF 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

SIEAM GENERA'IQlS EXAM COMPONENT OR SYSTEM SUB INSP.

R EQ'D, AMT.

ITEM INSPECTION ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

RY IT M O E EX M NED i

B3.8 B-I-2 VESSEL CLADDING SrEAM GENERA'IOR NO. 21 INIEP SIDE 04E 36 SQ.

36 SQ. CP-1, BEIIM MANEY 76-124 IN.

IN.

PA'IO1 OLTPLET SIDE QE 36 SQ.

36 SQ. CP-2, BEIIM MANEY 76-124 IM.

IN.

PNIOl STEAM GENERNIOR NO. 22 INLET SIDE 04E 36 SQ.

36 SQ. CP-3, BEIIM MANEY 76-123 IN.

IN.

PNIOi QJTLET SIDE QiB 36 SQ.

36 SQ. CP-4, BEIIM MANEY 76-123 IN.

IN.

PA'IOl B3.9 B-P EXEMPPED COMKNENPS

-NONE-B3.10 B-G-2 PRESSURE RETAINING l

BOLTING (< 2 IN. DIA.)

S'IEAM GENERA'IOR NO. 21 MANWAY BOLTING INIEP MANEY OE 5

6 BOLTS 1 'HIRU 6 76-99

'INO 5

5 BOLTS 6 'HIRU 10 78-83 BOLTS 1 'HIRU 16 81-25,31,45

'HIREE 6

ronu s7-aere s/7s ronu no. ess-soes PP9-A-9 m

8 49 9-8 5

8 3

O NO.

N M

S ON p R I

R oO TT 5

O CR F

EO 4,

T 1

A P P 3

R S

1 4

4 E

E N

1 3

N IR 3,

4, 4,

0 0

S E

935 279 279 G

982 1 72 1 72 E

M 681 681 681 LE A 778 778 778

!GET AAS TP N

05 06 06 I

61 1 61 1 61 1 O

T M

A UUU UUU UUU E

MC RRR RRR RRR I

I UH UI HHU T

EI MTT MTD T1T F

I TI IT R

N 1 61 161 1 61 O

E J

I SSS SSS SSS D

TTT TTT TTT A

LLL LLL LLL M

OOO OOO OOO BBB BBB BBB T.MA M

65 65 65 X

A E D.

O' T.

MA 5 5' 6

55 6

55 6

E R

P.

E E

E R

E E

E SNE EO R

Eo R

EO R

IP NW H

iw N

I 1

O

'I 1

OT T

OT 1

1 YRA 22 M

D M

E N

O U

N NI S

M Y

Y lA A

R Y

A N

TX W

O G A

W O

IE N

T N W

N I

E A

A I N

A T

B M

R T A

M A

EO E L M

N P

N O P

N DT E

B T

E E

)

I M

D I

G E

1 O

M NE I

Y L

I T

T C

A I

f J

M A N

Q Q

A W I

f R

X 0

E N e

E2 E

0 T A S M W

(

O N

PTO I I SNT E U C T

E

. Y 2

ADP E

TN S R

O G

6 N

SAI G

7

/

L B

6 N SE 6 0 RI C 71 4 -

EEI 3 A-HI V 0

7 T RR BM 1

9 9

UE I

R A S I

3 MP E

ST B

RP OR N O

NPI F

4 :

,I;

liij'

,4 l;

4 i

NORTHERN STATES POWER CO.

TAILE S1.4 PRAIRIE ISLAND UNIT 2

PAGE 1

OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BO(.EDARY I

SUB INSP.

H EQ'D.

AMT.

BTEM INSPECTION E.

N DE I I N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.1 B-F SAFE Em 'IO PIPING Am SAGE END IN BRANCH PIPING WEIDS

)

REACIOR VESSEL REACIOR CORE COOLANT OE 1

1 W -1 A, 29-2BC-1 A 77 _W RW REPORT &

77-022,112 SYS'IEMS

'INO 1

1 BCC-B-1 S.E.

81-W RW REPORT L 81-21

'IEREE 2

4 SAFETY IMJECTION QE 1

1 W-2, 4-2RC-14A 77 _W RW REPORT &

77-024,113 SYSIEMS

'IHREE 1

I STEAM GENERA'IOR NO. 21 i

REACIOR CORE COOLAMP

'INO 1

1 BCC-A-5 S.E.81-116,125 I

SYS'IEM

'IHREE 1

SIEAM GENERA'IOR No. 22 REACIOR GEE COOLANP QE 1

1 W-5, 31-2HC-2B 76-136,139 i

SYSTEM

'IHREE 1

PRESSURIZER SAFETY LINES OE 2

2 W-1, (8010A) 76-26,53 W-1, (8010B) 76-61,52

'INO 2

2 W-1, (8010A)80-187,192,192R,192Ra W-1, (80108)80-190,191,191R 2

W-1, (8010A) 01-7,7R,38,61 W-1, (8010B) 81-22,22R,40,64 SURGE LINE

'IND 1

1 W-15 SE, 10-2RC-4 78-31,100 RELIEF LINE

'IND 1

1 W-1B 80-58,88,169 1

'DIREE 1

4 FORM s 7-as7e e/7s ronne no.ess-soas PP9-A-13

l NORTHERN STATES POWER CO.

TATLE S1.4 PRAIRIE ISLAND UNIT 2

PAGE 2

OF 19 i

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BOUNDARY t

" 8 "

EUS INSP.

R EO'D, AMT.

ITEM INSPECTION E-N DE R TI N ITEM PER.

AMT.

EXAM-IDENTIFICATION REPORT NO.

j GORY ITEM TO 8E EXAMINED

~

.i B4.1 B-F (00tff'D) i

^

SPRAY LINE

'IWO 1

1 W-228 80-56,56R,86,167 W-22B 81-5,5R,24

'IHREE 1

B4.2 B-G-1 PRESSURE REMAINING BOLTS

-N WE-B4.3 Ato S' IUDS ( >2 IN. DIA.)

l AND B4.4 B4.5 B-J CIRCUMPERENPIAL AIO I

LONGIWDINAL PIPE WEIDS LONGI'IUDINAL WEIDS

-NONE-CIRCUMFERENPIAL WELDS (1.5 IM. NOM.DIA.' SYS'IEMS)

I SEAL INJECTION A (NE l

'IWO 1

1 W-4 78-12 mREE i

4 SEAL INJECTION B (NB 1

1 W-9 77-57

<1yo

'IHREE 1

(2.0 IN. NOM DIA. SYS.)

SEAL INJECTION A mE 3

3 W-21,22,24 77-18,19,20

'IWO 3

3 W-34,35,36 78-14,16,17

'IHREE 4

SEAL INJECTION B OE 4

4 W-54,55,58,59 77-10,11,13,12

'IWO 5

5 W,29,33,34,36,37 80-91,90,89,92,93

'mREE 4

Fonu s7 a47s e/7e ronu no.ess-sees PP9-A-14

i NORTHERN STATES POWER CO.

TABLE St.4 PRAIRIE ISLAND UNIT

?

PAGE

'l OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PDFR91RE BOLNDARY

^

I SUB INSP.

R EQ'D.

AMT.

STEM INSPECTION TE.

N DE I Ti N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.5 B-J (00tff'D)

OIARGING LINE WE 6

6 W-81,82A,80,83B, 77-9,8,7,6,5,4 CVCS 83A,83 4WO 6

6 W-32,33,36 78-20,21,22 W-37,38,39 80-96,97,98

'IHREE 6

2 IEIDOM4 LINE AND WE 1

1 W-22 77-27 NAIN LINE TWO 2

2 W-6,7 80-94,95 I

WIREE 2

l AUXILIARY SPRAY WE 1

1 W-1 77-28 10 PRESSURIZER TWO 1

1 W-11 78-71 DIREE 2

RESIDUAL 'IEMPERATURE WE 1

1 W-20 77-42 DE1ECTOR SAKE OFF-4WO 1

1 W-6 80-177 ODID IEG A THREE 1

RESILE TEMPERATURE WE 1

1 W-18 77-60 DE'IEClOR 1AKE OFF-4WD 2

2 W-8,9 80-116,117 00ID IEG B 11REE 1

i RESIDUAL 1EMPERATURE WE 1

1 W-24 77-58 IEIEC10R 1AKE OFF-1ND 1

1 W-29 80-178 IDP LEG A

'IHREE 2

RESIDUAL TEMPERA'IURE WE 1

1 W-19 77-59 DETECTOR 'IRKE OFP-1ND 1

1 W-23 80-104 IDP IEG B

'IHREE 2

SAFETY INJECPION OE HIGi HEAD A TWO 1

1 W-2 78-15 MIREE 1

FORMI 476 4/78 FOR04 NO. ISI-S tel

NORTHERN STATES POWER CO.

TATLE R1_4 PRAIRIE ISLAND UNIT 2

PAGE a

OF to INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PTPTNG PRFRRIIRE InNDARY SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E

N DESCRI Tl N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.5 B-J (CONP'D)

SAFETY INJECTIN WE 1

1 W-7 77-43 IIIGi llEAD B TWO 111REE 1

DRAIN LINE W WE 1

1 W-14 77-26 CROSSOVER A TWO 1

1 W-7 78-13 DIREE 1

8 REACIOR VESSEL WE 1

1 W-12 77-17 SA M INJECTIW

'IWO 1

1 W-9 78-19 IDW llEAD A WIREE 1

REACTOR VESSEL WE SAFET1Y INJECTION TWO 1

1 W-2 78-23 ION HEAD B

'DIREE 1

(3.0 IN. NOM. DIA. SYSTEMS) l l

SPRAY 'IO PRESSURIZER WE 3

3 W-5,7,8 77-38,40,39 BRANCII A iWO 3

3 W-20,24,25 80-121,120,119

'HiREE 4

SPRAY 'IO PRESSURIZER NE 2

2 W-18,19 77-48,46 l

BRAN 01 B

'INO 3

3 W-3,4,5 80-118,122,103 TIREE 2

RESIDUAL TEMPERATURE WB 1

1 W-5 77-41 DETECTOR IEIURN A 4WD 1

1 W-2 78-66 11REE 1

l RESIDUAT. TEMPERATURE WE 1

1 W-7 77-56 l

DETECTOR RETURN B 4WD 1

1 W-6 78-85 l

UIREE 1

1 raggs ene vanu na.,s,.....

g

NORTHERN STATES POWER CC.

TA!LE Sl+4 PRAIRIE ISLAND UNIT 2

PAGE 5

op 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURF. 0011DARY M

SUB INSP.

R EO'O.

AMT.

ITEM INSPfC'ItON E.

N DESC I Ti N ITEM PER.

AMT.

EXAM IDENTIFICATION SEPOH1 NO.

GORY ITEM TO BE EXAMINED B4.5 B,J (OWT'D)

PRESSURIZER RELIEF WE LINE A

'INO TIREE 1

PRESSURIZER RELIEF WE 1

1 W-4 77-47 LINE B,

'IND 1

1 W-9 80-99 THREE 1

(4.0 IN. NOM. DIA. SYSTEMS)

SAFETY INJECTIm WE 1

NONE m 'mESE IDW HEAD A TWO WFTIE ARE ACCES-WIREE SIBIE; TIEY ARE IOCA'IED WITHIN ME ONCREfB SHIELD WALL SAFETY INJECTIm QE (SAME AS IOOP A)

ION HEAD B

'IWO DIREE 1

(6.0 IN. NOM. DIA. SYSIEMS) i REACTOR VESSEL OE SAFETY INJECTIm SWO 1

1 W-6 80-100 IDWHEAD A MIREE 1

REACTOR VESSEL WE 1

1 W-9

(+W-8) 76-37 (+76-38)

SAFETY INJECTION

'IWO l

IOW HEAD B UIREE 1

i SAFELY INJECTION OE l

HIGi LEAD A

'lWO i

HIREE 1

l l

roggggene l

l NORTHERN STATES POWER CO.

TAOLE S1 4 PRAIRIE ISLAND UNIT

?

PAGE 6

OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PRESSURE BOLNDARY M

8 SUB INSP.

R EQ'O, AMT.

ITEM INSPECTION E-N DE I Tl N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED 3

I B4.5 B-J (00tff'D)

SAFETY INJECTIN OE 1

1 W-1 76-143 HIG1 IEAD B 1WO

'HIREE i

i PRESSURIZER SAFE 71Y OE i

LINE A.

'INO 3

3 W-8,W-3,4 80-102,81-59,58

'I11REE 1

PRESSURIZER SAEETY OE 2

2 W-1,2 76-54,61 i

LINE B 1NO 2

2 W-6,7 81-57,56 1HREE 1

1 PID-CAP A QE L'

gye g

'HIREE 1

1 PID-CAP B QE 4

1NO 1

1 W-1 80-101

'niREE (8.0 IN. NOM. DIL. SYSTEMS)

RESIDUAL HEAT REMOVAL OE 2

2 W-11,12 77-33,32 l

'mKE OFF A 1WO 3

3 W-5,6,8 78-90,94,92

'nmEE 3

IESIDUAL 1 RAT RENNAL OE 3

8 W-25,27,28 76-74,58,56 l

'mKE OPP B

(+W-8,10,11,12,26 )

(+76-70,71,72,73,58)

'INO 2

2 W-12,14 78-95,91

'DIREE 3

FOftM 3 7-2474 e/78 FOftM 000. BSt-leet PP9-A-18

NORTHERN STATES POWER CO.

TABLE SI 4 PRAIRIE ISLAND UNIT 2

PAGE 7

OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BOWDARY M

SUB INSP.

R EQ'D.

AMT.

ITEM INSPECTION E-N E

IT N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.5 B-J (CONF'D)

(10.0 IN. NOM. DIA. SYSTEMS)

RESIDUAL HEAT BEiCVAL WE l'

2 W-1

(+W-9) 76-9 (+76-7)

RETURN B

'INO 1

1 W-7 78-102

'IHREE 1

PRESSURIZER SURGE WE 1

4 W-12 (+W-11,13,14) 76-81 (+76-78,81,79)

LINE B

'IND 1

1 W-14 78-101

'IHREE 2

(12.0 IN. NOM. DIA. SYSTEMS)

ACCWULA'IOR DISCHARGE A WE 1

1 W-11 77-35 TWO 1

1 W-7 80-35,36

'IHREE 1

l ACCUPULATOR DISchARG B OE 2

5 W-1,15 (+W-13,14,76-146,18 (+76-20, 16) 21,19)

THO 1

1 W-13 80-34,37 THREE 2

i (27.5 IN. NOM. DIA. SYSTEMS)

REACIOR CORE COXMr OE CDID EG (INLET) A INO THREE 1

REACIOR CORE COOLANT WE COID EG (INIEf) B 1NO 1

1 BCC-B-12 81-87,94 THREE 4

l ra p9'_rg g */r*

ranu no. isi-issi p

I NORTHERN STATES POWER CO.

TACLE S1.4 PRAIRIE ISLAND UNIT 2

PAGE 8

OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ll EM:

PIPING PRESSURE BOLNDARY SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E

N DE RI TIO IT EM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO E;E EXAMINED B4.5 B-J (CONT'D)

(29.0 IN. NOM. DIA. SYSTEMS)

REACIOR CORE COOLAMP WE 1

1 W-3, 29-2RC-1A 77-044 l

IUP IEG (OUILET) A 1NO

'DIREE REPCIOR CORE COOLAMP WE IDP IEG (OUTIEP) B 1WO

'niREE 1

i (31.0 IN. NOM. DIA. SYSTEMS)

REACIOR CWE COOIMP WE 1

CROSSOVER A

'INO 2

2 BCC-A-6 81-1'15,115R,152 BCC-A-7 81-117,124

'HIREE l

REACIOR CORE COOLAMP WE 1

3 W-6 (+W-7,8 )76-140 (+76-141,142)

CROSSOVER B 1WO

'HIREE 1

B4.6 B-J BRANCil PIPE CONNECTICH WEIDS EXCEEDING SIX INCH DIAFEER ACCLMJIKIOR DISC!!AIGE A ACCtMJLATOR DISCilABGE B WE 1

1 W-R 76-145,137 RESIDUAL HEAT REMOVAL TAKE OFF A RESIDUAL IIEAT REMOVAL IND 1

1 W-Roor 81-113,121,126 TAKE OFF B r o u s7-a47s e/7s ronu wo. sse-soos 79-A-20

NORTHERN STATES POWER CO.

TA!LE S1.4 PRAIRIE ISLAND UNIT 2

PAGE 9

OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PRESSURE BOUNDARY 3UB INSP.

R EO'O.

AMT.

ITEM INSPECTION 4

E-DE I TION ITEM PER.

AMT.

EXAM IDENTIFICATION REPCRT NO.

GORY ITEM TO 8E EXAMINED B4.6 B,J (CONF'D)

PRESSURIZER SURGE

'HIREE 1

I ME B l

B4.7 B-J BRANCH PIPE C0tt4ECTION WEIDS SIX INCH DIMF11TR AND SMALLER (6.0 IN. NOM. DIA. SYS'IDE)

PID-CAP A PID-CAP B SMEIY IMJECTION i

HIGi HEAD A SAFETY IMJECTION 03E 1

1 W-R 76-138,144 HIGi HEAD B i

(3.0 IN. NOM. DIA. SYSTEMS)

SPRAY 'IO PRESSURIZER BRANCH A SPRAY 'IO PRESSURIZER

'DIREE 1

BHANCH B RESIDUAL 'IEMPERA'1VRE DETEC'IOR RE'IURN A l

RESIDUAL 'IEMPERA'IURE DE'IEC'IOR RE'IURN B j

i 4

FORM i7-2476 4/78 rwg pg g33.gg3, i

PP9-A-21

NORTHERN STATES POWER CO.

TABLE S1.4 PRAIRIE ISLAND UNIT

~)

PAGE 10 OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BOUNDARY EXAM COMPONENT OR SYSTEM SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION

[ORY ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

IT M TO E EX M NED B4.7 B-J (OONT'D)

(2.0 IN. NOM. DIA. SYS'IEMS)

IESIDUAL TEMPERATURE DETECTOR 'IAKE OFF OOLD IEG A BESIDUAL 'IEMPERATURE TWO 1

1 W-ROOP 81-89 DETECIOR 'IRKE OFF ODED IEG B NAIN LINS W CROSSOVER A DRAIN LINE W WE 1

1 W-R 76-131 CHOSSOVER B CHAIGING LINE CVCS REACTOR VESSEL SAFETY INJECTION IDW HEAD A REACIOR VESSEL

'IHREE 1

SAFETY INJECTION IDW HEAD B B4.8 B-J SOCKET WEIDS (2.0 IN. NOM. DIA. SYSTEMS)

SEAL INJECTIN A OE

'INO 1

1 SW-9 78-25 THREE 1

ronne s 7-a47s e/ss ronas peo.ess-seos PP9-A-22 1

NORTHERN STATES POWER CO.

TACLE SI 4 PRAIRIE ISLAND UNIT 2

PAGE 11 OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PRESSURE BOUNDARY N

SUB INSP.

R EO'O.

AMT.

ITEM INSPECTION E-N DE I I N ITEM PER.

AMT.

EXAM IDENTIFICATICN REPOR T NO.

GORY ITEM TO BE EXAMINED B4.8 D-J (CCNf'D)

SEAL INJECTION B 04E 1

1 SW-64 76-5

'INO DIREE 1

OlARGING LINE B WE 1

1 SW-54 (+SW-57,87) 76-49 (+76-49,6)

'IWO 1

1 SW-27 78-28 MIREE 1

DRAIN LINE AND WE 1

1 SW-1 (+SW-24)76-131 (*76-40)

[EIDOW1 LINE B

'IWO 1

1 SW-10 80-158 TIREE 1

AUXILIARY SPRAY OE 1

1 SW-4 76-42

'IO PRESSURI?ER

'INO MIREE RESIDUAL 'IEMPERA'IURE QE 1

1 SW-13 77-117 Iriullutt 1AKE OFF 4WD 1

1 SW-4 78-27 COLD IEG A TIREE 1

RESIDUAL TEMPERNIURE QE 1

1 SW-15 77-120 DE'IEC' LOR 1AKE OFF TWO 1

1 SW-4 78-26 COED IEG B UIREE 1

RESIDUAL TEMPERATURE OE Dtriu;1un TAKE OFF

'INO 1

1 SW-31 80-154 l

IUr LEG A MIREE 1

RESIDUAL TEMPERATURE OE l

DETECIOR 1AKE OFF

'IWO 1

1 SW-29 80-157 IDP LEG B TIREE 1

SAFErY INJECTION OE llIGI LEAD A

'INO 91REE 1

• In va,, na,,,,...,

"y9'jy*3

4 NORTHERN STATES POWER CO.

Tall.E. S1.4 PRAIRIE ISLAND UNIT 2

PAGE 12 OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PRESSURE BOUNDARY XAM MwONEM OR SYSTEM SUB INSP.

R EQ'D.

AMT.

BTEM INSPECTnON

[ORY f

ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

IT M O E EX M NED B4.8 B-J (CONr'D)

SAFETY IMIECTI N OE 1

1 SW-8 77-110 HIGI IIEAD B

'INO

'IHREE DRAIN LINE W WE 1

1 SW-13 77-114 CROSSOVER A

'lWO mingg 4

REACIOR VESSEL OE 1

1 SW-13 77-111 SAFETY INJECTION

'INO IDW HEAD A

'IIIREE REACIOR VESSEL WE SAFETY IMJECTION

'INO IDW HEAD B

'IIIREE 1

B4.9 B-K-1 INIERALLY WEIDED SUPPORTS SEAL INJECTION A

'IND 1

1 H

78-18,30,39 RESIDUAL 'IEMPERNIURE DE'IECIOR 'IRKE OFF IDPIE A SAFETY IMJECTION HIGI HEAD A SPRAY 'IO PRESSURIZER BRANCil A

'IND 1

1 L

80-76,123,156 BRANCH B

• 111REE 1

RESIDUAL HEAT

'IND 1

'1 U

78-29,50,93 REMWAL TAKE OFF A

.n=

ragogy4

l l

NORTHERN STATES POWER CO.

TATLE R1.4 PRAIRIE ISLAND UNIT

?

PAGE 13 OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BOUNDARY j

SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E.

N DE i i N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.9 B-K-1 (CONF'D) ifCUl0LA10R DISCHAPGE A SEAL INJECTION 5 TWO 1

1 A

80-49,105,155 I

OIABGING LINE CVCS QE 1

2 Z (+X)76-109,106(+76-110-6) 1

'IWO SHREE 1

RESIDUAL 'IEMPERA1'JRE l

DETIEC'IOR 'IRKE OFF CDID IEG B RESIDUAL TEMPERATURE it'p2.'wR 'IKKE OFF l

IOP IEG B RESIDUAL HEAT QE 1

1 Q

76-60,59 t

REMOVAL TAKE OFF B 4

RESIDUAL HEAT THREE 1

RENNAL RETIURN B I

j ACCUMULATOR DISCHARGE B OE 1

1 B1 76,39-3 SAFETIY IMJECTIQ1 HIGH HEAD B AUXILIAPY SPRAY CWS 1

REACTOR VESSEL

'IHREE 1

SAFE'IT IMJDCT!ON A i

FORM i7-34 74 4/73 FOR M 900. 858-9 Ge t PP9-A-25

NORTHERN STATES POWER CO.

TAILE SI 4 PRAIRIE ISLAND UNIT 2

PAGE 14 OF 19 INSERVICE INSPECTION-EXATA NATION SilMMARY M AJOR ITEM:

PIPING PRESSURE BOUNDARY SUB INSP.

R EQ'D.

AMT.

ITEM INSPECTION E.

N DESCRI T4 N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B4.10 B-K-2 SUPPORT COMPONENTS SEAL INJECTION A WE 4

3 A1, N/G 76-96/77-133 (IER J ADDED,PER.2)

'INO 5

6 F,I,J 78-38,40,65 A,B,C 80-148,147 TIREE 6

4

^

DRAIN LINE W WE CROSSOVER A 7WO TIREE 1

RESIDUAL TFJiPERATURE 04E 1

1 A

76-97 4

IEIECTOR TAKE OFF

'INO 1

1 B1 80-144,144R B1 81-139,139R ODID IEG A TIREE 2

RESIDUAL TEMPERA'IURE 04E

?.

2 C,D 77-144 Dt;m;wK TAKE OFF 7WO 2

2 G,H 80-146 IDP IEG A TIREE 3

SAFE'IY I!UECTION OE 1

1 C

77-131 11101 LEAD A

'INO 1

1 D

80-132 TIREE 1

i RESIDUAL TEMPERATURE Q4E 1

1 C

76-98 DETECTOR RL'IURN A TWO 1

1 B

78-41 illREE 1

SPRAY 70 PRESSURIZER Q4E 4

4 J/h,N,0 76-107/77-151 BRANOI A

'INO 5

5 B,C,D,Il 78-42,43,44,45 V

80-135 l

TIREE 5

SPRAY TO PRESSURIZER WE 3

3 G,H,F 76-107 BRANCil B 7WO 3

3 D,E,F1 80,129,130,131 TIREE 3'

roppffg g */n ron o.isi-ies

NORTHERN STATES POWER CO.

TA'LE SI 4 PRAIRIE ISLAND UNIT 2

PAGE 15 Op 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

PIPING PRESSURE BOUNDARY EXAM COMPONENT OR SYSTEM SUB INSP.

R E Q'D.

AMT.

8 TEM INSPECTION T

^

ITEM PER.

AMT.

EXAM JOENTIFICATION REPORT NO.

RY lT M TO BE EX M NFD B4.10 B-K-2 (00h*P'D)

IESIDUAL lEAT OE 5

5 O,P,Q,S,T 76-41 REMOVAL TAKE OFF A

'IWO 5

5 B,o,D,Il 78-46,47,48,49 C,E 80-54,23 UIREE 6

ACCUMULA'IOR D1 'CilARGE A WE 2

2 H,I 76-33

'IWO 3

3 D,E,G 80-25,50,51 DIREE 3

SEAL INJECTIN B WE 4

4 O,P,N/Q 76-32/77-157

'IWO 4

4 D,E,b,M 80,53,52,47,46 TIREE 5

OIAIGING LINE CVCS WE 5

5 R,S,V,W,Y 76-51,85

'IWO 7

7 K,M,N,0 78-53,53,52,51 O,Q,T,V 80-80,127,126,125 TIREE 8

RESIDUAL 'IEMPERA'IURE WE 2

2 A,A1 77-156 Dtan'10u TAKE OFF

'IND 2

2 B,C/C 78-54,55/80-145 CDID IEG B HIREE 2

RESIDUAL 'IEMPERA'IURE WE 1

1 A2 77-134 DETIECTOR TAKE OFF

'INO 2

2 A1,A 80-73,73R,72 A1 81-140 IDP IEG B TIREE 2

DRAIN LINE AND PE 2

2 F/C 77-135/76-108 IE'ID0ldi LINE B

.0 2

2 A,B 80-73,78 i

MIREE 2

IESIDUAL TEMPERA'IURE OE DETECTOR RETURN B

'IND 1

1 A

78-56 MIREE rogif-ag ein

,o..

o.........

NORTHERN STATES POWER CO.

TAILE SI 4 PRAIRIE ISLAND UNIT 2

PAGE 16 op 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE DOUNMY M

" S M i

SUB INSP.

R E Q'D.

AMT.

ITEM INSPECTION E-N DE i TI N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

t GORY ITEM TO BE EXAMINED B4.10 D-K-2 (CONP'D)

RESIDUAL IIEAT REMOVAL WE 5

5 It/L,M,N,0 76-63/77-145,149 TAKE OFF B

'IWO 5

5 A,B,C 78-57,57,58 C,D,K 80-65,64,133 MIREE 6

RESIDUAL lEAT RDIOVAL WE 1

1 A

77-132

]

RE'IURN,B

'IWO 1

1 B

78-59 TIREE 1

ACCUeULA'IOR DISC 11ARGE B UE 3

3 E,F,C 77-138

'INO 3

3 B,B1/A 78-60/80-48 MIPEE 4

SAFETY INJECTION WE 1

1 C

77-127 IIIW IEAD B

'INO MIREE 1

NJXILIARY SPRAY WE 1

1 A

76-46

'IO PRESSURIZEP.

'IWO 1

1 B

78-61 WIREE 2

REACIOR VESSEL WE 1

1 A

77-128 SAITI"I INJECTION

'Iwo IOW IIEAD A HIREE REACIOR VESSEL WE SAFETY INJECTION

'INO 1

1 A

80-134 IIM llEAD B WIREE PRESSURIZER RELIEF WE LINE B

'INO VIREE 1

PEACIOR VESSEL WE 1

1 D

77-130 SAFF11"I INJECTION

'IWO 1

1 B

l 78-62 IDWIEAD 3 (6 x 4")

91REE 2

l ogg.y.g.n.

NORTHERN STATES POWER CO.

TA2LE S1.4 PR AIRIE ISLAND UNIT _ 2 PAGE 17 _ OF 19 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPItG PRESSURE DOUNDARY ll SUB f

INSP.

R EQ'D.

AMT.

BTEM INSPECTION N DE Ri Tl N ITEM GGAh ITEM TO BE EXAMINED PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

84.10 B-K-2 (OCNP'D)

REAC'IOR VESSEL WE 1

1 D

77-129 SAFETY ITUECTION

'ItD 1,

1 A

80-75 IIM llEAD A (6x4")

HIREE 2

PRESSURIZER SAFETY WE 1

1 A1 77-152 LINES A & B

'INO 1

1 A2 80-128

'DIREE PRESSURIZER SUHGE B WE 3

3 K,J,I 76-48

'INO 4

4 A,B/C,D 78-64,63/80-70,71 TIREE 5

REACIOR (DRE C00RNr WE CROSSOVER A

'IND 1

1 A1 81-138

'HIREE 1

REACIDR CORE COOU NP WE 1

1 B1 76-106 C.NB

'INO

'I11REE 1

B4.11 B-P EXEMPP AND NON-EXEMPP

• ALL COMPONEN'IS PERFORMED BY COMPWEN_IS EXAMINED IN PLANT PERSOWEL ACCORDANCE WI'I11 HYDROSTATICALLY PRESSURE IWA-5000 AND

'IES'IED 'IO IWA-5000 AT IWB-5000 DURING SYSTEM IEAKAGE END OF 'IEN YEAR INTERVAL PLUS SYS'IEM IEAKEAGE

'IEST 4

EXAM EACH SCHEDUED REFUELING OUTAGE FORM 9 7-2474 S/78 FORM NO. ISt-lGGS PP9-A-29

NORTHERN STATES POWER CO.

TATLE S1.4 PRAIRIE ISLAND UNIT 2

PAGE 18 OF 19 INSERVICE INTECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING PRESSURE BOUNDARY

^

SUS INSP.

R EQ'D.

AMT.

ITEM INSPECTION E-N DES I N

ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

i GORY ITEM TO BE EXAMINED B4.11 B-P (OCNf'D)

EXEMPF:

1 RESISTANCE 'IEMPERA'IURE DETIEC'IOR 'IRKE OFF 1-2RC-7A EXCESS IEIDOW LINE A 1-2RC-8 1-2VC-7 1-2VC-9 RESISTANCC 'IEMPERA'IURE 3

DE1EC10R TAKE OFF

]

1-2BC-7B BEAC'IOR VESSEL CILSURE IEAD VENP 1-2RC-36 REACTOR VESSEL CICSURE IEAD FIANGE i

1-2RC-9A 1-2RC-9B B4.12 B-G-2 PRESSURE RETAINING BOLTING (ONLY SYSTEMS APPLICABIE

'IO 'nlIS I'IEM ARE LIS'IED) l SEAL INJECTION A i QE 4

4 BOLTS 1-4 9 W-2 76-76

'IWO 4

4 BOLTS 1-4 0 W-4 78-81 RESISTANCE 'IEMPERATURE

'DIREE 8

DETECTOR RETURN A ronne a 7-move e/7e conne no. sse-s ee n PP9-A-30 1

J P

A DN U

9 OB 1

NO E

O FR tN OJ TT M

CR E'

EO P P 4

P S E P

N I

9 P

IR 5

2 S_1 3

7 7

G 1

1 1

N E

I 0

0 6

LEP 8

8 7

I EGP AA TP N

2 O

-W I

0 T

M A

E MC 2

2 T

EI 1

4 1

F I

TI A

IT R

N 1

1 1

O E

0 D

s1 s

S J

I t0 t

T A

l8 l

L M

o-o O

B2 B

B

.M 2

2 T A 1

4 -

1 M X A E I

.D.

Q' TM 2

2 E A 1

44 8

1 R

E E

P SR E

E E

D DR R

E N

IP N

WH H

N

'I I I C

I Y

R E

A R

M U

D I

M E

Y i

A N

U r

RB I

NI S

0M r

B E

E 8A r

PN E

N TX A

N MR A

O IE S

O EU S

RE I

I I T

B R

T

' E R

I E

C ER E

A "EO Z

E C

Z N

DT I

J NR I

O I

M R

N mO R

M NE UA I

T Ub S

S' C S

C T

A I

)

D SE L

IE SE R

X EN A

S I'

EN E2 E

'P RI E

EE RI W

N PL S

RD PL O

O N

C PTO

(

I I SNT E U C T

E

.Y 2

ADP E R TNS

^

G N

n.

SAI G

L B

N SE RI C y

EEI y

HI V 2

T RR BM 1

y UE I

RA E ST 4

p S

I 8

p OR N o

NPI r

' i j

l 1

i J

NORTHERN STATES POWER CO.

TASLE St.5 PRAlHIE ISLAND UNIT.

2 PAGE 1

OF 3 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

IEACIOR CORE CODIRTP PUMPS 8

INSP.

R EO*D.

AMT.

ITEM INSPECTION TE.

N DE RI 1 N IT W PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B5.1 IFG-1 PRESSURE RETAINING BOLTS AND AND S' IUDS, IN PIACE B5.3 (2: 2 IN. DIA.)

FLANGE BOLTS PUMP A WE 8

8 BOLTS 1 THRU 8 76-87

'IwO 8

8 BOLTS 9 'HIRU 16 78-67 MIREE 8

PUMP B OiB 8

8 BOLTS 1 THRU 8 76-86

'Iwo 8

8 BO[.TS 9 'HIRD 16 78-68

'I11REE ITEM B5.2 SEAL HOUSE BOLTING PUMP A 04E 4

4 BOLTS 1 'HIRD 4 76-89

'INO 4

4 BOLTS 5 'HIRD 8 78-69

'HIREE I 4 IUMP B 04E 4

4 BOL'IS 1 'HIRU 4 76-88

'IWO 4

4 BDLTS 5 ' HIP.0 8 78-70

'HIREE 4

B5.2 B-G-1 PRESSURE RETAINING BOLTS AND AND SIUDS, NHEN REMNED B5.3 (2 IN. DIA.)

PUMP A

'INO 12 12 BOLT 1 'HIRU 12 81-46,47 SEAL IlOUSE BOLTING PUMP B MIREE 24 FIANGE BOLTING IUMP B Mir;rE 12 SEAL IKXJSE BOLTING roam s t-aste sire com u PP9-B-2

@ $)

s

+

TEST TARGET (MT-3)

' a EM s

l.0 e "a HE==

3

,_ n l,l . f, IN ll!llN l

l

/

l.8 1.25 I l.4 l.6 l

l l

/

6" e

l l

1 4ll*%y

/ S4%

• hk

1. 34

/

. $777,

NORTHERN STATES POWER CO.

TACLE St.5 PRAIRIE ISLAND UNIT 2

PAGE 2

op 3 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM: REACIM OCRE COONf PUMP,S__

E N

8 SUB INSP.

R EQ'O AMT.

BTEM INSPFCTION E

DE N

ITEM PER.

AM T.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED B5.4 B-K-1 INIM RALLY WELDED SUPPORTS PUMP A

'IWO 3

3 SUPIORT A,B,C RELIEP No. 47 81-129,131,130 PUMP B

'IWO 3

3 SUPIORT A,B,C 81-132,134,137 UIREE 3

B5.5 B-K-2 SUPPORT COMPONENTS *

• (DINCIDENT WITil SEISMIC BOLTING PUMP A (DWM AND WE 1

1 00WW 1 77-67,163,158 IATERAL SUPPORTS

'IWO 1

1 00W W 2 80-181,107,174 DIREE 1

WMP B 00W E AND WE I

1 COWM 1 77-64,162,161 IATERAL SUPPOR'IE

'IWO 1

1 OOWm 2 80-181,107,108 TIREE 1

B5.6 B-L-1 PUMP CASING WEW S WMP A

-NONE-WMP B

-NNE-B5.7 B-L-2 PUMP CASINGS TIREE 1

WMP A & B B5.8 B-P EXEMPIED COMRNENIS

-NONE-B5.9 B-G-2 PRESSURE RETAINING

-NONE-BOLTING (< 2 IN. DIA.)

ronM s 7-a47s etre ronu seo.sse-seos PP9-B-3

NORTHERN STATES POWER CO.

TABLE S1.5 PRAIRIE ISLAND UNIT

~1 PAGE 3

OF 3 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

REACIOR CORE 000U@TP PCMPS M

8Y8 "

SUS INSP.

R EO'D.

AMT.

ITEM INSPECT 60N E.

N DE I T10N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINED PtNP FLYMEEIS RMP A & B OE 2

2*

PLMP-21, FLMIEEL 76-113,117,116 IUMP-22, FLYWHEEL 76-93,82,92

'INO 2

2 R MP-21, FLYWHEEL 80-141,142,143 RMP-22, FLYWHEEL 80-124,139,140

'AIREE

• BDI11 FLYWiEEIS WERE BENOVED AS A RESULT OF MODIFICA-TION 'IO 'DE PLEP IAERICATION SYS'I1M

'nE BORE AND KEY-WAY'S WERE Fr EXAM-INED & 'IllE REMAIN-DG SURFICES WERE MT EXR4INED.

U.T.

WAS USED 'IO VOWME-

'I1UCALLY EX.BMINE

'I1E FLYWIIEEIS (!K7IE

'IECH SPT 4.2-1)

FORM 9 7-2476 6/74 FORM sec. ISt-9 001 PP9-B-4

4 NORTHERN STATES POWER CO.

TABLE S1.6 PRAIRIE ISLAND UNIT 2

PAGE 1

OF 4 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM:

VALVE PRESSURE BOLNDARY

^M PON 8 M SUS INSP.

R EO*D.

AMT, ITEM INSPECTION TE.

N DES I Tl N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

CORY ITEM TO BE EXAMINED B6.1 B-G-1 PRESSURE RETAINING

-10NE-B6.2 BOLTS Ato SIUDS AND

(< 2 IN. DIA.)

B6.3

-NONE-B6.4 B-K-1 INTEGRALLY WEIDED SUPPORTS B6.5 B-K-2 SUPIORP OCNPCNENTS

• INCLIOE IN

'mBIE 1.4 UNDER B4.10

-Note-E6.6 B-M-1 VALVE BmY WEIDS B6.7 B-M-2 VALVE BODIES

(> 4 IN. NOM. PIPE SIZE)

REACIOR VESSEL DREE 1

SAFETY INJECTIW IDW HEAD A RESIDUAL HEAT DREE 1

RDOVAL TAKE OFF A PRESSURIZER SAFETY

'IHREE 1

LINE A RESIDUAL HEAT

'IHREE 1

REMNAL REIURN B ACCtMULATOR DISCHARG A

'IHREE 1

B6.8 B-P

-EXEMPPED COMPONENTS 100%

ITEMS INSPECTED INSPECIED BY DURING EACH PIANT PERSCNNEL IEAWE 'IEST roa u sv-34 s sire ro m...........

PP9-B-5

NORTHERN STATES POWER CD.

TABLE SI.6 PRAIRIE ISLAND UNIT 2

PAGE 2,

OF 4 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITElWI:

VALVE PRESSURE BOLNDARY M

"E S M Suir INSP.

H EQ'D.

AMT.

BTEM INSPEOTION E-ND DE q

ITEM PfR.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINED B6.9 B-G-2 PRESSURE RF? RAINING

• tDIE SUPPLEMENT BOLTING B6.9 AT 3.4.3 AOCUMUIROR DISQiART OE 16 16

QiECK, 2-8841A 76-12 LOOP A - 12"

'I11REE 16 ACCtNUIATOR DISCHAH2

'INO 16 16

OlECK, 2-8841B 80-82 IOOP B.- 12"

'DIREE 16 RESIDUAL HEAT OE 16 16 M.O. GNIE, 2-8703 76-13 REMOVAL Rfm]RN B-10" RESIDUAL HEAT

'IWO 16 16 M.O. GAIE, 2-8701 A 78-80 RENOVAL TAKE OFF A-8"

'HIREE 16 PCSIDUAL HEAT OE 16 16 M.O. GATE, 2-8701B 76-16 RENOVAL TAKE OFF B-3" OE 16 16 M.O. GA3E, 2-8702B 76-16 SAFETY INJECTIO4

'INO 12 12

OlECK, 2-8842A 80-166 HIGl HEAD A - 6" SAFETY INJECFION

'DIREE 12 HIG1 HEAD B - 6"

?

PRESSURIZER SPRAY IOOP A - 3"

'HIREE 8

IOOP B - 3" OE 8

8 runRR(2-PCV-431B) 76-28

'DIREE 8

RESISTANCE YEMPERA7URE TWO 12 12 GATE, 2-8001 A 78-79 DETECIOR RETURN IOOP A - 3" RESISTANCE 'ITNPERA'IURE

'IND 12 12 GAIE, 2-8001B 78-78 DEmrIOR RET. URN IOOP B - 3" ronne 32-34n ein ronu no. ise-i.es Pn9-B-6

e NORTHERN STATES POWER CO.

TABLE St.6 PRAIRIE ISLAND UNIT 2

PAGE 3

OF 4 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

VALVE PRESSURE BOIN RRY M

SUB INSP.

R EO'D.

AM1.

ITEM INSPECTION E-O DE I N ITEM PER.

AMT.

Ex/ M

DENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED I

B6.9 B-G-2 (ODNr'D)

RESI3TANCE 'IYMPERATURE DE 2

2

2r58, 2RC-1-6 76-95 DETIECTOR 'IME OFF

'INO 2

2

2T58, 2HC-1-7 80-152 ODID IEG A - 2" MIREE 2

RESISTANCE TEMPERATURE

'INO 2

2

2T58, 2RC-1-15 80-137 DETECTOR 'IME OFF qwo 2

2

2r58, 2RC-1-16 80-165 ODID IEG B - 2" DIREE 2

RESISTANCE 'IYMPERA'IURE

'IW 2

2

2r58, 2RC-1-9 80-150 DETECTOR 'IME OFF INO 2

2

2r58, 2ac-1-10 80-151 IDr LEG A - 2" MIREE 2

RESISTANCE TYMPERATURE OE 2

2

2r58, 2RC-1-12 76-103 DETECTOR 'IME OFF TWO 2

2

2r58, 2BC-1-13 80-136 IUP IEG B - 2" DIREE 2

PRESSURIZER RELIEF OE 12 12 M.O. GATE, 2-8000B 76-14 LINES 3"

QE 6

6 GOBE, 2PCV-431C 76-14

'INO 6

6 GDBE, 2PCV-430 80-149 UiREE 12 REACIOR VESSEL SAFETY INJECTION IOW IIEAD A - 6" OE 12 12

OIECK, 2-8843A 76-91 INO 12 12

OIECK, 2-8844A 80-171 IDW HEAD B - 6" OE 12 12

OIECK,

'2-8843R 76-36 MIREE 12 AUXILIARY SPRAY DIREE 6

CVCS - 2" FOR84 5 7-1476 6/78 Popes MO. ISO-8 84 8 PP9-B-7

NORTHERN STATES POWER CO.

TABLE SI.6 PRAIRIE ISLAND UNIT 2

PAGE 4

OF 4 INSERVICE INSPECTION-EXAMINATION StJMMARY M AJOR ITEM:

VALVE PRESSURE BOLNDARY SU8 INSP.

R EQ'O.

AMT.

ITEM INSPECTION E-N DE I Tl N ITW PEN.

AMT.

EXAH IDENTIF8 CATION REPORT NO.

GORY ITEM TO BE EXAMINED B6.9 B-G-2 (ODNP'D)-

DRAIN LINE DE 2

2

2r58, 2RC-1-3 76-11 CN CROSSOVER B

'IHREE 2

' DRAIN LINE GE 2

2

2r58, 2RC-1-2 76-15 ON CROSSOVER A-2"

'IHREE 2

IEI006ti LINE B - 2" OE 8

8 A.O. GOBE, 76-10 2ILV-427

'INO 2

2

2r58, 2RC-1-5 80-81

'IEREE 8

CHAIGING LINE B - 2"

'INO 6

6 A.O. GLBE, 78-24 2-8142 SEAL INJECTION A - 2" OE 2

2 2T-58, 2VC-7-18 76-94 SEM. IMJECTIOJ B - 2" OE 2

2 2P-58, 2VC-7-19 76-84 L

ro'ene a r-aeva sus rones no, ess-s ees PP9-B-8

NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISI.AND UNIT II PAGE 1

0F 7

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYSTM ISO METHOD IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS REACTOR VESSEL Bl.3 VESSEL-TO-FLANGE AND llEAD-TO-FLANGE CIRCUMFERENTIAL WELDS VESSEL-TO-FLANCE 42 UT W-1 81-W NONE NONE NONE RPV REPORT llEAD-TO-FLANCE 41 UT W-6 81-141 NONE NONE NONE 81-144 NONE NONE NO S-1 FLANCE

('l-143 NONE NONE NO S-1 FLANCE Bl.4 PRIMARY N0ZZLE-TO-VESSEL WELDS AND N0ZZLE INSIDE RADIUSED SECTION REACTOR CORE COOLANT OUTLET 40 UT RCC-B-1 81-W NONE NONE NONE N0ZZLE i(PV REPORT I

i

• UNDERCLAD CRACKING 50 UT N0ZZLE A 81-W N/A

1. INDICATION

' NONE RPV i

REPORT (SEE SECTION 4 0F INTRODUCTIO I

FOR AHALYSIS) 1 i

l FORM NO. ISI-1003

NORTHERN STATES POWER COMPANY TABl.E II PRAIRIE ISLAND UNIT II PAGE 2

0F 7

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS N0ZZLE B 81-W

1. INDICATION RPV REPORT N/A (SEE SECTION 4 NONE OF'INTRrDUCTIO 4

~

FOR AN.. LYSIS)

Bl.6 N0ZZLE-TO-SAFE END WELDS REACTOR CORE COOLANT 40 UT RCC-B-1 S. E. 81-W NONE NONE NONE OUTLET N0ZZLE RPV REPORT PT RCC-B-1 S.E. 81-21 NONE NONE NONE Bl.8 CLOSURE STUDS AND NUTS STUDS 39 UT 17,18,20,21 81-162 NONE NONE NONE

& 24 UT 19,22,23,25 81-167 NONE NONE NONE TilRU 32 MT li TilRU 32 81-165 NONE NONE NONE NUTS 39 UT 17 TilRU 32 81-163 NONE NONE NONE MT 17 TilRU 32 81-166 NONE NONE NONE Bl.9 LIGAMENTS BETWEEN TilREADED STUD 110LES LICAMENTS 42 JT 9 TO 11 81-W NONE NONE NONE UT 36 TO 46 RPV" l

REPORT Bl.10 CLOSURE WASilERS AND BUSilINGS WASilERS 39 VT 17 TilRU 32 81-164 NONE NONE NONE Bl.11 PRESSURE RETAINING BOLTING l

MARMON CLAMP 38 VT NO. 2 81-170 NONE NONE NONE FORM NO. ISI-1003

I NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 1

0F 7

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METil0D IDENT.

NO.

INDICATIONS ATIONS LIMITATIONS MARMON CLAMP 38 VT NO. 1 81-170 NONE NONE NONE MARMON CLAMP 38 VT NO. 3 81-170 NONE COR(ODED TliREADS NONE Bl.13 CLOSURE IIEAD CLADDIN(

47 VT llCP-3 81-155 NONE NONE NONE IICP-4 81-155 NONE NONE N0i10 llCP-1 81-155 NONE NONE NONE Bl.14 VESSEL CLADDING 48 VT VCP-3 81-W-NONE NONE NONE (2 PATCllES)

RPV REPORT PRESSURIZER B2.4 N0ZZLE-TO-SAFE END WELD l

SAFETY LINE A 30 UT W-1A S.E.

81-37 NONE NONE BEST EFFORT S-1 &

l S-2 LIMITED SCAN AREA UT 81-63 NONE NONE B.E. ALL SCANS j

CONFIGURATION PT 81-6 3 LINEAR 2 LINEAP.

NONE

-l SEVERAL SEVERAL ROUNDED ROUNDED PT 81-6R AS ABOVE SEVERAL ROUNDED NONE SAFETY LINE B 30 UT W-1B S.E.

81-39 NONE NONE B.E. S-1 & S-2 LIMITED SCAN AREA UT 81-62 NONE NONE B.E. ALL SCANS CONFIGURATION PT 81-23 NONE 1 LINEAR NONE PT 81-23R NONE NONE NONE FORM NO. ISI-1003

NORTNERN SIATdS POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 4

0F 7

BASELINE COMPARISON SUMMARE NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /3YSTEM

_ IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS ISO METHOD B2.11 PRESSURE RETAINING BOLTING PRESSURIZER MANWAY BOLTS 36 UT BOLT 1-16 81-60 NONE NONE NONE STEAM CENERATORS B3.3 N0ZZLE-To-SAFE END WELDS STEAM GENERATOR 21 32 UT RCC-A-5 S.E.81-125 NONE S-2 ID GEO. 75%

NO S-1 N0ZZLE CROSSOVER PT 81-116 NONE NONE NONE

]

B3.10 PRESSURE RETAINING l

BOLTING K2 INCil DIA.)

STEAM GENERATOR NO. 21 MAINAY A BOLTS 37 Ur BOLTS 1-16 81-45 N/A NONE NONE i

MT BOLTS 1-16 81-25 N/A NONE NONE MAINAY B BOLTS 37 UT BOLTS 1-15 81-45 N/A NONE NONE MT BOLTS 162 81-31 N/A 1 BOLT LINEAR NONE MT BOLTS 3-15 81-25 N/A NONE

' NONE B4.1 SAFE END-TO-PIPING AND SAFE END IN BRANCll PIPING WELDS REACTOR VESSEL REACTOR CORE COOLANT 33 UT RCC-B-1 S. E. 81-W NONE NONE NONE RPV REPORT PT 81-21 NONE NONE NONE FORM NO. ISI-1003

NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 5 OF 7

BASELINE COMPARISON

SUMMARY

NSl' NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM

_ IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS ISO METHOD STEAM GENERATOR NO. 21 REACTOR CORE COOLANT 32 UT RCC-A-5 S.E.81-125 NONE GEO. @l:00, 75%

NO S-1 SAFE END PRESSURIZER SAFETY LINE A 30 UT W-1 81-38 OD.GEO 401 NONE NO S-1 SAFE END UT (8010A) 81-61 (SAME)

NONE NO S-1 SAFE END PT 81-7 NONE 2 LINEAR NONE PT 81-7R NONE-INDICATIONS NONE BUFFED OUT SAFETY LINE B 30 UT W-1 81-40 S-2 OD GEO NONE NO S-1 REDUCER (80108) 40%

UT 81-64 (SAME)

NONE NO S-1 REDUCER PT 81-22 NONE LINEAR NONE PT 81-22R NONE-INDICATION NONE BUFFED OUT I

SPRAY LINE 7C UT W-22B 81-24 S-1,ID GEO.

S-2,OD GEO. 60%

B.E. ALL SCANS 45%

REDUCER S-2,ID GEO.

25%

S-2 OD GEO.

44%

PT 81-5 3/16'i.INEAR 4 LINEARS NONE PT 81-SR 4NONE-INDICATIONS NONE BUFFED OUT B4.5 CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS i

REACTOR CORE COOLANT 33 UT RCC-B-12 81-94 NONE NONE ALL SCANS LIMITED COLD LEG (INLET) B 11:45-12:15 & 8:45-9:15 BRANCil CONNECT PT 81-87 NONE NONE NONE 1

FORM NO. ISI-100.'

NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 6

0F 7

BASELINE COMFARISON

SUMMARY

COMPCNENT/ SYSTEM

-I NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION ISO MET 110D IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS REACTOR CORE COOLANT 32 UT RCC-A-6 81-152 NONE NONE B.E. ALL SCANS CROSSOVER A MACllINING TAPER Pi 81-115 NONE NUMEROUS LINEARS NONE PT 81-115h NONE-INDICATIONS NONE BUFFED OUT 32 UT RCC-A-7 81-124 NONE NONE NO S-1 MACllINING TAPER PT 81-117 NONE NONE NONE PRESFURIZER SAFETY A 30 UT W-3 81-59 NONE S-1, ID GEO. 30%

B.E. S-2 ELBOW S-1, OD GEO. 35%

INNER RADIUS S-2, OD GEO. 30%

30 UT W-4 81-58 NONE S-1, ID GEO. 30%

B.E. S-1 & S-2 S-2, ID GEO. 20%

E.I.R.

PRESSURIZER SAFETY B 30 UT W-6 81-57 N/A S-1, OD GEO. 30%

B.E. S-2 S-2, ID GEO. 30%

E.I.R.

30 UT W-7 81-56 N/A NONE B.E. S-1 6 S-2 E.I.R.

S-2 6:00 FITTING j

l B4.6 BRAi4Cll PIPE CONNEC-

~

TION WELDS EXCEEDING SIX INCil DIAMETER RESIDUAL llEAT REMOVAL 20A UT W-ROOT 81-121 NONE S-2, ID CEO. 50%

NO S-1 BRANCH TAKE OFF B 81-126 NONE NONE NO S-2 BRANCH PT 81-113 NONE NONE NONE B4.7 BRANCil PIPE CONNEC-TION WELDS SIX INCll l

DIAMETER AND SMALLER l

RESISTANCE TEMPERAT*JLE 14 PT W-ROOT 81-89 NONE NONE NONE DETECTOR TAKE OFF B FORM NO. ISI-1003

MORTHERN FTATES POWER COMPANY T.GLE II PRAIRIE ISLAND UNIT II PACE 7 0F 7

BASELINE COMPARISON

SUMMARY

I NSP NDE

( W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS B4.10 SUPPORT COMPONENTS RESISTANCE TEMPERATURE 3

VT B1 81-139 NUT NOT liANGER TILTED NONE DETECTOR COLD LEG A FLUSli 81-139R NONE - IIANGER NONE STRAICitTENED RESISTANCE TEMPERATURE 15 VT A1 81-140 LOOSE BOLTS NONE NONE DETECTOR 110T LEG B REACTOR CORE COOLANT 32 VT A1 81-138 N/A NONE NONE CROSSOVER A l

REACTOR CORE COOLANT PUMPS B5.2 P_RESSURE RETAINING BOLTS AND STUDS WilEN REMOVED (&2 IN DIAMETER)

SEAL 110USE BOLTING PUMP A 12 UT 12 BOLTS 81-47 NONE NONE NONE MT 81-46 NONE 2 BOLTS CORRO-NONE SION ON THREADS i

B5.4 INTEGRALLY WELDED j

SUPPORTS PUMP A PT SUPPORT A 81-129 N/A NONE 4" UNACCESSIBLE TT SUPPORT B 81-131 N/A NONE NONE PT SUPPORT C 81-130 N/A NONE 4" UNACCESSIBLE PITclP B PT SUPPORT A 81-132 N/A NONE 4" UNACCESSIBLE PT SUPPORT B 81-134 N/A NONE NONE PT SUPPORT C 81-137 N/A NONE 4" UNACCESSIBLE i

I FORM NO. ISI-1003 i

o s

Table III N0 h 1ERN STATES POWER CO.

PAE 1

0F 4

PRAIRIE IS1AND UNIT 2 ISOMETRIC SLM1ARY CLASS 1

~

REVISIW 00MPONDE OR SYSTD4 IDOP R

2-ISI-1 0

SEAL INJECTION (GENERAL VIEW)

A 1 "62" A

1" 1 -2VC-21A 1

2-ISI-1A 0

A 2"

2-2VC-21A 3

2-ISI-1B 0

A 2"

2-2VC-21A 3

2-ISI-1C 0

A 2"

2-2RC-10A 3

2-ISI-2 0

CROSSOVER DRAIN 2-2RC-11A 3

A 2"

2-2RC-8A 3

2-ISI-3 0

RTD TAKEOFF COLD LEG A

2" 2-2RC-7A 3

2-I3I-4 0

RTD TAKEOFF 110T LEC A

2" 2-2SI-35A 3

2-ISI-5 0

SAFETY INJECTION HIGH HEAD A

3" 3-2RC-6A 4

2-ISI-6 0

RTD RETURN A6B 3"

SPRAY TO PRESSURIZER (GENE.7AL VIEW)

A 3"

3-2RC-5 4

2-1SI-7 0

2-ISI-7A 0

A 3"

3-2RC-5 4

2-ISI-7B 0

A 3"

3-2RC-5 4

2-ISI-7C 0

8 3"

3-2RC-5 4

2-ISI-7D 0

A 6"

6-2RC-13B 6

2-ISI-8 0

SAFETY INJECTION HICll HEAD A

6" 6-2RC-13A 6

2-ISI-9 0

PLO-CAP A

8" RHR TAKE OFF (GENERAL VIEM) 8" 8-2RC-15A 8

2-ISI-10 0

2-ISI-10A 0

8" 8-2Ril-1A 8

2-ISI-10B 0

8" 8-25tH-1 A 8

2-ISI-10C 0

A 12" 12-2RC-16A 11 2-ISI-11 0

ACCUMULATOR DISCHARGE 12-2SI-27A 11

---m-

i e

Table III PORTHEPN STATES PWDt CD.

PAq 2 0F 4 PRAIRIE ISLAND INIT 2 ISOMETRIC SLM4ARY SIh I

REVISICN (XHOENT OR SYSTDI ILOP ER 2-ISI-12 0

SEAL INJECTION (CENERAL VIEW)

B lb"&2" 2-ISI-12A 0

5 2"

2-2VC-21B 3

2-ISI-128 0

B 2"

2-2VC-21B 3

2-ISI-12C 0

B 1\\"

lb-2VC-21B 1

i 2-ISI-13 0

CHARGING LINE (GENERAL VIEW)

B 2"

2-ISI-13A 0

B 2"

2-2RC-17 3

2-ISI-138 0

B 2"

2-2VC-5 3

2-ISI-13C 0

5 2"

2-2VC-6 3

2-ISI-13D 0

B 2"

2-2VC-6 3

2-ISI-14 0

RTD TAKEOFF COLD LEG B

2" 2-2RC-8B 3

2-ISI-15 0

RTD TAFIOFF HOT LEC B

2" 2-2RC-7B 3

2-ISI-16 0

CROSSOVER DRAIN AND LETDOWN B

2" 2-2RC-10B 3

2-2RC-115 3

2-2RC-12 3

2-ISI-17 0

RTD RETURN B

3" 3-2RC-6B 4

2-ISI-18 0

SAFETY INJECTION HIGH HEAD B

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-203 0

B 8"

8-2RH-15 8

2-151-20C 0

8 8"

i 8-2RH-15 8

2-1S1-21 O

RHR RETURN B

10" 10-2SI-26 10 2-ISI-22 0

ACCUMULATOR DISCHARGE B

12" 22-2RC-165 11 12-25I-27B 11 I

Tablo III NORIHERN STATES POWER CO.

PAE 3 0F 4 PRAIRIE ISLAND LNIT 2 ISOMETRIC SlMMRY fife Ab REVISI(N COMPONENT OR SYSTDI 1DOP R

2-ISI-23 0

SAFETY INJECTION HICll HEAD B

2" 2-2SI-35B 2

2-ISI-24 0

AUXILIARY SPRAY 2"

2-2RC-19 3

2 2-2VC-4 3

2-ISI-25 0

F.EACTOR VESSEL SAFETY INJECTION A

2" 2-2SI-24A 3

2-ISI-26 0

REACTOR VESSEL SAFETY INJECTION B

2" 2-2SI-24B 3

2-ISI-27 0

PRESSURIZER RELIEF A6B 3"

3-2RC-21 4

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

2-1S1-29 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-20R 6

2-ISI-31 0

PRESSURIZER SURCE B

10" 10-2RC-4 10 2-ISI-32 0

REACTOR COOLANT A

29" 29-2RC-1A 15 A

31'-

31-2RC-2A 15 j

A 27h" 27h-2RC-3A 15 2-ISI-33 0

REACTOR COOLANT B

29" 29-2RC-1B 15 B

31" 31-2RC-2B 15 B

27b" 27 -2RC-3B 15 6

2-ISI-34 0

RECENERATIVE HEAT EXCilANGER 2-ISI-35 0

PRESSURIZER SAFETY AND RELIEF N0ZZLES

l Table III

'NORlHERN STATES POWER 00.

PAG 4

OF 4

PRAIRIE ISIAND INIT 2 l

ISOMETRIC SLM4ARY LINE LINE LTT - CAL' NSP ISO ISI N

I SIZE NtNBER STANDARD MNBER i

25A/16 2-ISI-36 0

PRESSURIZER 25A 2-ISI-37 0

STEAM GENERATORS A&B 2-ISI-38 0

REACTOR VESSEL CONOSEAL BOLTING STUDS-17 2-ISI-39 0

REACTOR VESSEL STUDS, NUTS & WASHERS 2-ISI-40 0

REACTOR VESSEL N0ZZLES 25A 2-ISI-41 0

REACTOR VESSEL HEAD WELD 2-ISI-42 0

REACTOR VESSEL SHELL WELDS 2-ISI-43 0

RC PUMP SEAL !!0USING BOLTIt;G 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 2-ISI-47 0

REACTOR VESSEL CLOSURE CL-1 HEAD CLAD PATCHES 2-ISI-48 0

REACTOR VESSEL CLAD CL-1 PATCH IDENTIFICATION i

O

Table III NORIHERN STATES POWER 00.

PAGE I

OF 1

PRAIRIE ISIAND LEIT 2 ISO!ETRIC SENARY - SEIS;iIC BOLTING AUGMENTED NSP ISO LINE LINE trf - CAL.

REVISI(N 00EONENT OR SYSTBI IDOP NtNBER SIZE NIMBER STANDARD 2-ISI-77 0

STEAM GENERATOR SUPPORT BASE A&B 4/ GENERATOR 2-ISI-78 0

STEAM GENERATOR SUPPORT TOP A&B 4/ GENERATOR 2-ISI-79 C

REACTOR COOLANT PUMP SUPPORT BASE A&B 3/ PUMP 3/ PUMP 2-ISI-80 0

REACTOR COOLANT PUMP SUPPORT TOP A&B 2-ISI-81 0

R.C. PUMP #22 LOWER LATERAL SUPPORT B

2-ISI-84 0

R.C. PUMP #21 LOWER LATERAL SUPPORT A

2-ISI-85 0

STEAM GENERATOR 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-853 0

PRESSURIZER BASE 2-ISI-89 0

ACCUMULATOR BASE A&B

--.___-y_

l

=

I<.

l l

1 APPENDIX B ASPE CLASS 2 EXAMINATION i

i I

l l

1 i

i i

l I

l l

l Page 1 of 1

NORTHERN STATES POWER CO.

TABLE S2.1 PRALRIE ISLAND i: NIT 2

PAGE I

OF 2 INSERVICE INSPECTION-EXAMINATIOf4

SUMMARY

MAJOR ITEM. PRESSURE VESSELS-S115AlfCElHA101 -

M

" T 8

SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E-ND DE R N

ITEM PER.

AMT.

EXAM IDEr;TIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINED i

l l

C1.1 C-A CIRCUMFERENPIAL RTPP WEMS *

• (3 AREAS, EQUALLY DIVIDED) l SPEAM GENERA'IOR No. 21 NEW B

'INO 82" 180.5" 0" 10 48",129" 10 81-127,128,133 189",270" 10 330"

& 439 '10 0" NEW F 111" SPEAM GENERATOR NO. 22 NE[D C 82" NEID E 82" iEID 11

'HIREE 111" C1.2 C-B NOzzm 10 VESSEL WEIDS STEAM GENERA'IOR 10. 21 MAIN S2 SAM Nozzm stEDmita NOzzm SPFAM GENERATOR NO. 22 MAIN STEAM NCzzm 111REE 1

stErweta mzzm

-NONE-C1.3 C-C IN1EGRALLY WEIDED SupeoarS I

,o. - o.........

rappp g g n-

R TIA R

E D

G 2

M A

d*O E

I pT ON oS TT CR EO S

PP 6

L S

1 E

E IR 4,

N 2

S S 2 S

08 97 1 5 77 E

77 67 77 44 V

1 1 1 1 1 1 1 1 ELEE 88 88 88 88 R

BGU AAS TPS ER P_

NO I

T M

A E

MC T

EIF I

TI IT R

N

)

)

)

)

P)

P)

F) f)

)

O N.

M M

0 M

J 8

(

A T.

T.

T.

T. ) T.

(

(

(

)

)

)

)

M VU VU VU VUVU

((

((

((

((((

.M TMA 77 00 88 88 - -

X A

1 1 22 1 1 1 1 E

)

)

)

)

)

0*T N

N N

N N

QM I

I I

I I

A 0M 0M 0M 0M0M E

R 2(

2(

2(

2(2(

2 2

2 2

2 E

P R E

S O

R NE O

O W

W W

W IP 1

1 1

I' 1

4 1

Y R

1 2

A 2

2 M

D G

G G

G M

E N

0 N

N O

N N

U 8

I I

N I

I NI 1

S M

T T

T T

A G

E L

L R

L L

O O

O O

O N

X N

T E

I T

D B

I D

B O

I E

N A

A' T

B I

R A

B R

A B

A EO A

E E

E r

N T

N Y

Y N

Y Y

N DT E

E A

A E

A A

M R

G W

H G

W W

O I

MNE N

N N

N M

T C

A I

E M

A A

M A

A R G A

M M

A M

M R

X U N E

E E2 E

S I

I I

W S T S

S E L O

N R O PTO P B I I SNT EU C T

E ADP MEY R

TNS O

D N

SAI G

L C-N SE

• 0 p,

RI C EEI HI V 7

4 g_

T RR B

J I

g -

RA E EU 1

S C

g.--

OR N o

NPI r

l

NORTHERN STATES POWER CO.

TABLE S2.2.1 PRAIRIE ISLAND UNIT 2

PAGE 1

OF 5 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM: PIPItG-CIRCUMEERENPIAL BUIT_WEILS SUS INSP.

R EO'D.

AMT.

ITEM INSPECTION E.

N DE I I N ITEM PER.

AMT.

EXAM IDENTIFIC# TION REPORT NO.

GORY ITEM TO 8E EXAMINED C2.1 C-G CIRCUMFERENPIAL BUIT WEIDS MAIN STEAM A 32-2MS-1 MIN SIEAM B 32-2MS-2 MAIN SIEAM A

'IND 1

1 MS-11 81-123 30-2MS-1

'IHREE 1

MAIN STEAM B

'INO 1

1 MS-83 81-43,55 30-2MS-2 MAIN STEAM A OE 1

1 MS-17 77-101,31 31-2MS-1

'INO 1

6 MS-16,17,18 81-52,83,4,54,85 MAIN SIEAM B M3-19,20,174 81-50,84,51,92,53,86 31-2MS-2

'IWO 1

1 MS-117 81-93 MAIN SIEAM A OE 1

1 MS-188 77-99,15 RELIEF HDR., 30-2MS-1 MAIN STEAM B RELIEF HDR., 30-2MS-2 MAIN STEAM A 6-2MS-1 MAIN SIEAM B 6-2MS-2 OE 1

1 MS-113 77-96,37 EEEDWA'IER A 16-2EW-13 OE 1

1 EW-161 77-45,55 16-2EW-12

'IWO 2

2 EW-161 80-20,27,83,185 16-2EW-11 EW-174 80-18,31,84,160 EW-177 80-19,29,40,162 EW-177 81-10,32,36,42,42R romu o-un ein ro..

o.........

PP9-B-11

NORTl!ERN STATES POWER CO.

TABLE S2.2.1

?RAIRIE ISLAND UNIT 2

PAGE 2

op 5 PIPING-61EUlGE16NfIAL Burr WEILS INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:_

YS SUB INSP.

R EO'D.

AMT.

ITEM INSPECTICN E-N DE I TION O ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED C2.1 C-G (CONT'D)

EEE0m ER B 16-2EW-16 OE 1

1 EW-116 77-97,3 16-2EW-15 TWO 1

1 EW-133 80,21,38,41,161 EW-133 81-11,37,35,41,41 R EEEDE'IER A (8 in) 3-2AF-11 EEEDWA'IER B (8 in) 3-2AF-12 REFUELING WATER SIORAGE

'IENK DISOIA'0E 14-2S1-1

'IND 1

1 W-58 (Pt only) 79-41 12-2SI-3A

'IWO 1

1 W-60 79-83 12-2S1-3B 12-2S-11 12-2SI-4

'RIREE 1

10-2S1-8 1NO 1

1 W-68W 79-84 STREAM 1

'1HREE 1

STREldt 2

'IWO 2

2 W-88,289 79-77, 76 OCNTAINN Nr SUMP B DIS 01AR3E LINES 14-2S1-33A 14-2S1-33B 12-2SI-34A

'INO 1

1 W-17 79-25 12-2SI-34B

'IND 1

1 W-5 79-26 12-2Ril-6A 12-2Ril-6B Fon u s7-aers e/7s ronu no sss-seen PP9-B-12

NORTHERN STATES POWER CO.

T/ ELE S2.2.1 PRAIRIE ISLAND UNIT 2

PAGE 3

OF 5 INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM: PIPING 4'IRCUMFERENTIAL BUl"r WEIES E M MPON T S M SUB INSP.

R EQ'D.

AMT.

ITEM INSPECTION E-D DE R I N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED C2.1 C-G (00Nr'D)

SAFETY IM ECTION

'UIP NO. 21 SUCTION 6-2Ril-10A BRANCII 1

'IWO 5'

5 W-285,93,161,96,95 79-59,78,79,82,80 BRANCH 2

'I11REE 1

SAFETY IM ECTIN RJMP NO. 22 SUCTIN 6-2Ril-10B BRANCH 1

'IWO 2

2 W-286, 135 79-57, 81 BRANCH 2 DIREE 1

RESIDUAL HEAT REMOVAL DISCHARGE 8-2REl-9A

'IWO 1

1 W-68 79-67 8-2Ril-9B

'I11RSE 1

'IND 1

1 W-53 79-65 8-2Ril-7A 8-2RIl-7B

'INO 1

1 W-201 79-63 BORIC ACID SUPPLY 'IO SAFETY INJECTIN i

6-2SI-13A

'IWO 1

1 W-272R 79-53 mires t

6-2SI-13B

'IWO 1

1 W-271 79-52 8-2S1-17 8-2S1-18

'IND 1

1 W-85 79-94

'111REE 1

RESIDUAL IIEAT RDUIAL SUClIN 10-2S1-9A

'INO 1

1 W-212 79-54 10-2SI-9B

'INO 1

1 W-143 79-55 rogy;gussin ronu o.........

3

NORTHERN STATES POWER CO.

TABLE S2.2.1 PRAIRIE ISLAND UNIT 2

PAGE 4

OF 5 INSERVICE INSPECTION-EXAMINATION

SUMMARY

M AJOR ITEM: PIPING-CIRCUMFERENTIAL BUIT WEILS M

COM E OR YS M ITEM tNSP.

R EO'D.

AMT.

ITEM INSPECTION SUB PER.

AMT.

IXAM IDENTIFICATION REPORT NO.

GORY ITEM TO SE EXAMih*D C2.1 C-G (GNP'D)

N~JMJIA'IOR DISOIAIG LINES 12-2SI-28A 12-2SI-288 12-2SI-29A 12-2SI-29B OE 1

1 SI-316 77-49 C2.1 C-F IESIDUAL llEAT REMOVAL DISOIABGE 10-2Ril-11 OE 1

1 NI-294 77-33

'Iwo 1

1 W-176 79-30

'IliREE 1

6-2MI-12

'Iwo 1

1 W-331 81-66 6-2S1-10B

'IIIREE 1

RESIDUAL llEAT REMOVAL SUCTIOi 12-2MI r>A

'INO 1

1 W-105 79-27 12-2RII-5B TWO 1

1 W-142 79-47,50 8-2RH-4A

'1ho 1

1 W-100 79-68 8-2Ril-4B

'111REE I

1 10-2Ril-3 OE 2

2 Mi-255,Ril-256 77-50,51

'INO 2

2 W-225,226 79-28,29

'IHREE 2

8-2Ril-5A

'IW 1

1 W-104 79-69 8-2RIl-5B

'IND 1

1 W-138 79-64 rOnu 3 7-se7e e/7s FORM PeO tSI 9449 PP9-B-14

l!

]

E J

JFW t,o T

o s

IT M

as s.

o 5

L se A

NO.

s I

O e

p I' IN n

oN TT o

E CR r

1 R

EO P P 2

E S E E

N 2

M IR A

S 5 U

25 6

C 56 4

R I

11 7

E 78 7

LE<

BGG AAN TPI P

IP NO I

T M

A E

MC T

EIF I

TI IT R

N 2

O ED 39 6

J I

34 2

A 3

I I

M SW S

.M T A 1 1 -

1 M X A E D.

O' T.

M E

1 1 1 1

A R

E F.

E SR EOR E

NE IP WH Q '

'I O

I Y

RA M

U D M

E N

U 8 NI S

M N

A O

N IX LI O

IE ETA 8

SC5 5

I E

T B

SD 2 2

I EJ -

A N EO VNI 1

N DT IS S

I

• M R

2 2

O M

E OY -

T T6 6

C A

I

)

I D

CE R

X EW A

'P E2 E

W N

RS O

O N

C PTO

(

I I SNT E U C T

E ADP MEYR TNS O

F s

N SAI G

7

/

L C

e N SE s

5 RI C 7

1 4

EEI a

HI V

- B T RR BM 1

7 s

UE 9

I RA E ST 2

ne P _

S I

C n P GR N o

NPI r

S G

N I

T T

I t

F t

e N

t I

I S

B.

1 S

O T

)

N NO.

R N

3 M

I O

F%

IN 9

R O.

TT

+

O 2

CR

(

F D

IO P P 0

2 I

S E W

IR 3

N 3,

2 1

S 2

3 L

1 9

A E

N 7

1 I

8 7

LED BGU AAI T P' IG

- N GO N

NI O

2 8

I 1

1 I

T PM A

S S

IPE MC M

M T

EI F

I TI IT O

O R

N I'

I O

E 1

7 J

D A

I 1

1 M

S S

M M

.M T A 1

1 M X A E D.

Q' T.

MA E

1 l

R P

SR NE O

E IP W

4 I

G Y

1 2

R S

S A

S M

M M

M D N

I 2

2 M

E I

0 0

N U

8 O

3 3

NI S

M J

A N

X D

O 4E L

R R

E A

B A

B A

B ADBD I

E 1

2 1

2 1

2 H

H T

B W

M M-M-M -

M M-M M

A EO L

ASAS ASAS ASAS AFAF N

O IN DT A S CMEM EMEM EMEM EEEE

• M N G T2I 2 T2T2 T2T2 TITI M

NE I

N S

S' -

S-S -

S-S-SLSL C

T D

I 2

2 0

0 1

1 E

E A

I U T N3N3 N3N3 N3N3 NRNP R

X I T I

I I

I I

I I

I E2 E

I' I A

A A

A A

A A

A W

G F M

M M

M M

M M

M N

O N

O N PTO I

I I I SNT E U C T

E ADP ME.Y TN S R

O G

8 N

SAI G

7

/

L C

4 N SE 4

6.

RI C 7

1 4

EEI 2

T RR BM 2

- B.

HI V 7

UE 9.

3 I

RA E ST 2

M P S

I C

R P OR N O

NPI F

NORTHERN STATES POWER CO.

TABLE s2.4 PRAIRIE ISLAND UNIT 2

PAGE 1

OF 2

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

VALVES M

N 8 M SUB INSP.

R EO*D.

AMT.

ITEM INSPECTION E-N DE Tl N ITEM PER.

AMT.

E%AM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED C4.1 C-F VALVE BODY WEWS

-NONE-

1. U C-G C4.2 C-D PRESSURE RETAINING BOLTING MAIN STEAM A 31-2MS-1

'INO 26 26 (V) 81-9 3(MIN) 26 (Ur) 81-9 MAIN STEAM B 31-2MS-2 MAIN STEAM A (6") (OFF) RELIEF HDR Q1E 12 12 (V)

RS-21-11 77-54 30-2MS-1 2(MIN) 2 (UP)

RS-2-11 77-54

'INO 12 12 (V)

RS-21-14 81-73 2(MIN) 12 (Uf)

RS-21-14 81-73 MAIN STEAM B (6") (OFF) RELIEF IIDR 30-2MS-2

'INO 12 12 (V)

RS-21-20 81-8 2(MIN) 12 (UP)

RS-21-20 81-8

'IHREE 24 (V) 4(MIN)

(UP)

RESICUAL IIEAT REMOVAL WMP A 6-2Ril-12 WMP B 6-2S1-10B OE 12 12 (V) 2-88038 77-63 2(MIN) 2 (Ur) 2-8803B 77-63 FORM 9 7-24 74 6/TS FORM 800. 050-9 99 9 PP9-B-26

NOR1 N STATES POWER CO.

TABLE S2.4 PRAIR ISLAND UNIT 2 PAGE 2

op 2

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

VALVES

^

Sus t hSP.

REO 0.

AMT.

ITEM INSPECTION E

E I 4 N 61E M GORY 8 TEM TO BE EXAMINED PER.

AMT.

EXAM IDENTIFICATION REMT W.

C4.2 C-D (CONT'D)

ACCLMRATOR DISOIAIEE LINES 12-2S1-29A

'HIREE 16 (V) 2(MIN)

(Lfr) 12-2SI-298 C4.3 C-E-1 INTEGRALLY WEIDED SUPPORTS

-NCNE-C4.4 C-E-2 SUPIORT 00HPOtOfrS

-NONE-

?

'T 8

ro -.,.,...

ro =

PP9-B-27

NORTHERN STATES POWER CO.

TABLE S2.2.5 PRAIRIE ISLAND UNIT 2

PAGE 1

OF 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM: PIPING-INIEGRALLY lEILED SUPPOR'IS SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E-DE I N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINED C2.5 C-E-1 INIEGRALLY WEIDED SUPPORTS MAIN S'IEAM A

'IWO 2

1 P,H,A 81-16,48,48R,14,74, 74R,16 30-2MS-1 MIREE 2,

MAIN SIEAM B OE 1

1 I

77-147 30-2MS-2

'INO 2

2 A,H 81-13,30,15,34 MIREE 3

MAIN SIEAM A OE 3

3 J,K,M 77-154,140 31-2MS-1

'IWO 1

1 S

81-2,3 MAIN SIEAM B-31-2MS-2 DIREE 2

MAIN STEAM A 30-2MS-1 (R-HDR)

MIREE 1

MAINS'IEAM B 30-2MS-2 (R-LOR)

MAIN STEAM A 6-2MS-1

?

MAIN STEAM B 6-2MS-2 OE 1

1 P

77-103 EEEDWATER A 16-2EW-13 OE 1

1 K

77-105 16-2EW-12

'INO 10 10 A

80-5,5R,32 16-2EW-11 B,C 80-2,33,6,62 E,P 80-1,28,68,63 H,I 80-67,61,66,59 J,K,L 80-77,60,3,3R,44 80-8,26 A,K 81-19,67,67R,20,68 DIREE 3

roppt31.yfgens ro== no....-i...

NORTHERN STATES POWER CO.

TABLE S2.2.5 PRAIRIE ISLAND UNIT 2

PAGE 2 _op 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM: PIPING-INIEGRAILY wJr2n SUPPORTS j

EN Spg",

i,"@gs INSP.

R EO'D.

AMT.

ITE M INSPECTION sua i IO O I

PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINEO l

C2.5 C-E-1 (CONF'D',

l l

EEEDWA'IER B 16-2EW-16 ONE 2

2 "G,H 77-104,148 16-2EW-15 SWO 8

8 A

80-16,16R B,C,D,E,P 80-9,10,42,74 G,H 80-11,11R,12 A,G 81-18,17

'IUREE 1

REEUELING WA'IER SIORAGE

'IRNK DISCHAICE 12-2SI-4

'IWO 1

1 C

79-42,34 OWTAINPENT SUMP B DISCHARGE LINES 12-2S1-33A 12-2S1-33B SAFETY INJECTION IUMP NO. 21 SUCTIN BRANCH 1 6-2Ril-10A GE 1

1 B

77-119 BRANOI 2 6-2RH-10A WE 1

1 G

77-119 SAFETY IMJECTIm PUMP NO. 22 SUCTION BRANCH 1 6-2RH-1GB

'IWO 1

1 D

79-35,38,38R BRANCH 2 6-2RH-10B

'IHREE 1

RESIDUAL HEAT REMNAL SUCTIm PUMP A 8-2RH-4A

'IWO 1

1 A

79-19,44 i

g._g.g.n.

NORTHERN ?TATES POWER CO.

TABLE S2 2.5 l

PRAIRIE ISLAND UNIT 2

PAGE 3

op 3

l lNSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM: PIPING-INEGRALLY wrIFn SUPPORTS i

EXAM COMPONENT OR SYSTEM

$RY EXAM 1NED

^

PE.'

A EXANI IDEN FICATION EP NO.

IT O

C2.5 C-E-1 (CONT'D)

RESIDUAL llEAT REM 0/AL DISCIPIGE PUMP B 8-L'ui-98 RESIOUAL llEAT RENNE DISCHARGE PUMP A 1 0 - 2161-1 1 NE 1

1 L

77-115

'HIREE 1

RESIDUAL HEAT REMCNAL DISCHARGE PUMP B 6-2SI-10B

-NONE-RESIDUAL HEAT RE2KNAL SUCTIN 14]MP B 10-2Ril-3 (IE 1

1 C

77-118

'19 0 1

1 E

79-37,40,40R 8-2Ril-4B

'INO 1

1 J

79-36,39,39R

'IHREE 1

REACDOR VESSEL SAFETY IMJECTIN A 6-2S1-25A WE 1

1 A

77-109

'IWO 1

1 B

81-27,49,49R

' DIRE 1

REACIOR VESSEL SAFETY INJECTIW B 6-2S1-25B WE 1

1 A

77-108 ronu 37-asts afra ronae no.sse-seet PP9-B-21

NORTHERN STATES POWER CO.

TABLE 92.2.6 PR AIRIE ISLAND UNIT

?

PAGE 1

OF 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING-N31 IIEIReD SUPPGtTS M

M "

I "

SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E-N DE I I N ITEM PER.

AMT.

EXAM IDENTIFICA(ION REPORT NO.

GORY ITEM TO 8E EXAMINED C2.6 C-E-2 SUPPORT COMPONCNIS MAIN STEAM A 31-2MS-1

'IHREE 1

MAIN STEAM B 31-2MS-2

'HIREE 1

MAIN S'IEAM A 30-2MS-1

'Iwo 1

G 81-12,128 MAIN S'IEAM B 30-2MS-2

'IHREE 1

MAIN STEAM A RELIEF HDR., 30-2MS-1 QE 1

1 O

77-140 MAIN STEAM B RELIEF HDR., 30-2MS-2

'Iwo 1

1 0

81-1,1R FEED 4NIER A 16-2EW-13

'Iwo 2

2 D,G 80-4,69

'IIIREE 1

REFUELING WNIER S10 RAGE TANK DISCilARGE 12-2S1-4

'Iwo 1

1 B

79-45 ro n u ir-ser eir.

ronu no. isi-i...

PP9-B-22

NORTH 5RN STATES POWER CO.

TABLE S2.2.6 PRAIRIE ISLAND UNIT 2

PAGE 2

op 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING-tKN wrre SUPFORTS YI SUS INSP.

R EO*a AMT.

ITEM INSPECTION E.

DE I ON ITEM PER.

MT.

EXM IDENTIFICAT10N REMT NO.

GORY STEM TO BE EXAMINED C2.6 C-E-2 (CONT'D) 10-2S1-8 BRANCH I DIREE 1

BRANCH 2 SAFETI IRTECTION RNP NO. 21 SUCCICN BRANCH I 6-2Mi-10A

-ERE-BRANOi 2 6-2RH-10A

'IWD 1

1 E

79-46

'DiBEE 1

SAFETI IRTECTION RMP NO. 22 SUCTICM BRANCH 1 6-2Mi-108

-TOE-DRANOi 2 6-2RH-10B

'INO 1

1 A

79-33,33R TIREE 1

RESIDUAL EEAT RDD/AL DISOIAICE RNP A 6-2Mi-12 CNE 1

1 M

77-136 RMP B 6-2SI-108 RESIDUAL HEAT REMOVAL SUCTICN RMP B 10-2RH-3 CNE 2

2 A,B 77-155

'IWO 1

1 F

79-9 TGiEE 2

RMP A 8-2Mi-4A

'IWO 1

1 B

79-18 RMP B 8-2Mi-4B DIREE 1

roa u is-u r..ir.

io==

....-i...

PP9-B-23

NORTHERN STATES POWER CO.

TABLE S2.2.6 PRAIRIE ISLAND UNIT 2

P.",G E 3

OF 3

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

PIPING-tKN WEIDED SUPPORIS M

YS M SUB INSP.

R CO*D.

AMT.

STEM INSP2CTION E-N DE I TIOq ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO 8E EXAMINED C2.6 C-E-2 (CONr'D)

RESIDUAL HEAT REM (NAL DISCHARGE PWP A 8-2Ril-9A IUMP B 8-2Ril-9B

'II.REE 1

ACOMJLMOR DISCilAFCE LINES LINE A 12-2SI-28A OE 1

1 B,77-137 12-2S1-29A LINE D 12-2S1-28B

'HIREE 1

12-2SI-29B BORIC ACID SUPPLY

'IO SAFETY INJECTIOi 6-2SI-13A CNE 1

1 B

77-153 6-2SI-13B REAC'IOR VESSEL SAFETY IRJECTION LINE A 6-2SI-25A CNE 1

1 H

77-150 LINE B 6-2SI-25B

'IWO 1

1 B

OCNTAINMENT SUMP DISOIAKE LINES LINE A

-NOE-LINE B

-NOE-FORM 9 7-24 76 6/78 FONM MO. SSI-9 99 9 PP9-B-24

NORTHERN STATES PONER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 3_OF 6

l BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD

_ IDENT, NO.

INDICATIONS INDICATIONS LIMITATIONS PRESSURE VESSELS

' STEAM CENERATORS l

C1.1 CIRCUMFERENTIAL BUTT WELDS STEAM CENERATOR NO. 21 37 UT W-B 81-127 N/A NONE NONE WELD B 81-128 TUBE SilEET GSO NONE 81-133 TUBE SIIEET GEO NONE i

C1.4 PRESSURE RETAINING BOLTING STEAM GENERATOR No. 21 36 UT MANWAY A 81-78 N/A 1 BOLT 65% LOSS NONE 17 BOLTS OF BACK WALL MT 81-70 N/A 16 BOLTS STEAM i40NE C')UGES UT MANWA7 B 81-77 N/A NONE NONE 20 BOLIS MT 81-69 N/A 3 DOLTS DENTED NONE i

THREADS STEAM CENERATOR No. 22 36 UT MANWAY A 81-76 N/A NONE NONE 18 BOLTS MT 81-71 N/A 10 BOLTS STEAM NONE COUGES r

UT MANWAY B 81-75 N/A NONE NONE l

18 BOLTS MT 81-72 N/A 3 BOLTS DENTED NONE THREADS 1

i 9ts' FORM NO. ISI-1003

NDRTPERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 2

OF 6

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM

_ IDENT.

FO.

INDICATIONS INDIC%TIONS LIMITATIONS ISO MET 110D PIPING - CIRCUMFERENTIAL BUTT WELDS C2.1 CIRCUMFERENTIAL BUTT WEl.DS MAIN STEAM A 46A UT MS-II 81-123 N/A S-2, ID GEO.50%

NONE 46B UT MS-17 81-4 NONE NONE NONE UT MS-16 81-83 MONE NONE NO S-1 PENETRATION S-2 LIMITED SCAN ADJACEh'i WELD MT 81-52 NOWE NONE 46B UT MS-18 81-85 NONE S-1, OD GEO.30%

LIMITED SCAN S-2, OD GEO.35%

5:30 TO 6:30 IIANGER MT 81-54 ARC STRIKE NONE 81-54R NONE-INDICATION NONE BUFFED OUT UT MS-19 81-84 NCNE NONE B.E. S-1 ENCAPSUL-l ATED NO S-2, S-3, S-4 MT 81-50 NONE B.E. LNCAPSULATED UT MS-20 81-92 NONE NONE No S-1, S-3, S-4 ENCAPSULATION B.E.

S-2 LIMITED SCAN AREA 5:30 - 6:30 llANGER MT 81-51 NONE B.E. ENCAPSULATED l

l UT HS-174 81-55 NONE S-1, OD CEO.35%

S-1 LIMITED ADJACENT j

WELD S-2 LIMITED AT 12:00 BRANCil MT 81-53 NONE NONE l

I FORM NO. ISI-1003

NORTHERN STATES POWER COMPANY TABLE PRAIRIE ISLAND UNIT II PACE 3

0F 6

i BASELINE COMPARISON

SUMMARY

' l NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM ISO METHOD:

IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS MAIN STEAM B 47A UT MS-83 81-55 N/A S-1 OD GEO. 30%

NONE S-2 ID CEO.70%

E-2 OD GEO. 30%

MT S1-43 DISSIMILAR METAL NONE 47B UT MS-117 81-93 N/A S-2 OD GEO. 25%

NO S-1 " TEE" S-2 LIMITED VALVE B.E. S-3, S-4 VALVE FEEDWATER A 48A UT W-177 81-32 S-1 ID GEO. S-1 ID GEO. 90%

NONE 50%

S-1 ID CEO. S-2 ID GEO. 60%

60%

S-2 ID CEO.

S-2 OD GEO. 60%

40%

S-2 OD CEO.

50%

UT 81-36 (AS ABOVE)

S-1 ID GEO. 50%

NONE S-2 OD GEO. 60%

PT 81-10 N/A NONE NONE MT 81-42 N/A 4 LINEARS NONE MT 81-42R NONE-INDICATIONS NONE BUFFFD OUT FEEDWATER B 49A UT W-133 81-33 S-1 ID CEO. S-1 ID CEO. 90%

NONE 39%

S-1 OD GEO. S-2 ID CEO. 60%

43%

a S-1 ID CEO.

39%

-l S-2 ID GEO.

l 44%

i S-2 OD GEO.

I 39%

S-2 ID GEO.

48%

j J

FORM NO. ISI-1003

o NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAVD UNIT II PAGE 4 OF 6

BASELINE COMPARISON

SUMMARY

NSP NDE

}{ BASELINE REPORT BASELINE ISI EXAMINATION CGMPONENT/SYSTDI ISO METHOD IDENT.

h0.

INDICATIONS INDICATIONS LIMITATIONS FEEDWATER B (CONT) l UT 81-35 (SAME AS S-1 ID GEO. 70%

UONE ABOVE)

S-1 OD GEO. 70%

S-2 ID CEO. 40%

S-2 OD GEO. 40%

PT 81-11 N/A NUMEROUS LI"(EARS NONE MT 81-41 9 LINEARS 23 LINEAT'S NONE MT 81-41R NONE-INDICATIONS BUFFED OUT 9"91 DUAL IIEAT REMOVAL 56 UT W-331 81-66 N/A S-2 OD CEO. 50%

B.E.

S-2 VALVE Df SCliARGE REACTOR VZSSEL SAFETY 72 UT W-349 81-65 N/A S-1 OD GEO. 40%

NO S-2 VALVE INJECTION A C2.2 LONGITUDINAL WELD JOINTS IN FITTINGS MAIN STEAM A 46A UT MS-11 TO 81-123 N/A NONE NO SCANS CN ELBOW MS-12 OUTER RADIUS AT AREA 0F SUPPORT ATTLCHMENT C2.5 INTEGRALLY LTJLDED SUPPORTS MAIN STEAM A 46A MT F

81-48 N/A ARC STRIKE NOI-S MT 81-48R N/A NhE-INDICATION NONE BUFFED OUT

~

VT 81-16 N/A NONE NONE MT 11 81-74 N/A 1/2" LINEAR 1 PAD INACCESSIBLE ON BOTTOM SIDE

!!T 81-74R NONE-INDICATION NONE BUFFED OUT VT 81-14 N/A NONE NONE l

FORM NO. ISI-1003

o NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLlJiD UNIT II PAGE 5

0F 6 MASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT /SYSTDi

_ IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS ISO MET 110D MAIN STEAM A (CONT)

MT S

81-2 N/A NONE NONE VT 81-3 N/A NONE NONE MAIN STEAM B 47A MT A

81-30 N/A NONE INACCESSIBLE AREA ADJACENT llANGER VT 81-13 N/A NONE NONE MT 11 81-34 N/A NONE GUARD PIPE VT 81-45 N/A NONE GUARD PIPE VT A

81-26 N/A NONE NONE FEEDWATER A 48A MT A

81-67 NONE 1/2" LINEAR NONE MT 81-67R NONE INDICATION NONE BUFEED OllT VT 81-19 LOASE BOLTS NONE NONE MT K

81-68 NONE NONE NONE VT 81-20 MISSING NUT NONE NONE EXTRA NUT FEEDWATER B 49A VT A

81-18 LOOSE NUT NONE

,i3ARD PIPE VT C

81-17 1/4" GAP ON NONE NONE BASE PLATE, NUT NOT FLUSil REACTOR VESSEL SAFETY 73 PT B

81-49 N/A 7 LINEARS NONE INJECTION PT 81-49R NONE-INDICATIONS NONE BUFFE9 OUT p

B2.6 SUPPORT COMPONENTS i

MAIN STEAM A 46A VT G

81-12 N/A LOOSE BOLTS NONE 81-12R NONE-BOLTS l

TIGitTENED I

1 l

FORM NO. ISI-1003

NORTHERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 6

0F 6 BASELINE COMPARISON

SUMMARY

a-NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION Cel W NENT/ SYSTEM ISO HETHOD IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS I

MAIN STEAM B 47B VT 0

81-1 N/A LOOSE BOLTS NONE i

81-1R NONE - BOLTS NONE TIGHTENED REACTOR VESSEL SAFETY 71 VT B

81-28 N/A NONE NONE INJECTION B VALVES C4.2 P_RESSURE RETAINING R

BOLTING i

MAIN STEAM A 46B UT 26 BOLTS G 81-9 N/A NONE ONE END ONLY CV-31116 UT 12 BOLTS @

81-73 N/A NONE ONE END ONLY RS-12-14 MAIN STEAM B 47B UT 12 BOLTS @

81-8 N/A NONE ONE END ONLY RS-21-20

~

1 l

l l

l FORM NO. ISI-1003

TABLE III NOREEIW STATES PGiER CG.

pag 3 op 3

PIMJRIE ISIAND 1 HIT 2 ISLt41HRIC S!!+1ARY - CLASS 2 n

LINE LIFE IIT - CAL.

tes? ISO REVISIQ1 00MPONDir OR SYSTDI 1DOP SIZE tati3ER STNRIARD PAFBER 26 2-1S1-37 0

STEAM GENERATORS A6 '4 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

2-1S1-47 0

MAIN STEAM (CENERAL 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 13/16 2-151-48A 0

A 16" 16-2 W-13 2-ISI-48B 0

A 16"

'16-2W-12 13 16" 16-2 W-11 11 8"

3-2AF-11 NO.

2-ISI-49 0

FEEDWATER (GENERAL VIEW) 8 13736 2-ISI-49A 0

E 16" 16-2 W-16 2-ISI-49B 0

L 16" 16-2W-15 13 8"

3-2AF-12 NO.

22-2-ISI-50 0

RilR PUMP B SUCTION (WELDS)

B 10" 10-2Rii -3 29 2-I31-51 0

Ri!R PUMP B SUCTION (IIANCERS)

B 8"

8-2RH-4B 29 B

8" 8-2RH-5B 32 B

12" 12-2RH-5B 22 B

10" 10-2SI-98 2-IS1-52 0

Ri!R PUMP A SUCTION (WELDS)

A 8"

8-2RH *A 29 29 2-ISI-53 0

RHR PUMP A SUCTION (HANGERS)

A 8"

8-2RH-5A 32 A

12" 12-2RJ-5A A

10" 10-2SI-9A 22 I

O

TABLE III NOR11!ERN STATES NWER CO.

PAGE 2 0F 3 PRAIRIE IS!AND INIT 2 ISGEIRIC SlM1ARY - CLASS 2 I

LINE 1.INE IIT - CAL.

REVISI m 00MPONIWT OR SYSUN ILOP SIZE NINllEll STANDARD g

29 2-ISI-54 0

RllR PUMP B DISCllARGE (WELDS)

B 8"

8-2Ril+78 29 2-ISI-55 0

RilR PUMP B DISCllARGE (llANGERS) a 8"

8-2RIl-98 27 B

6" 6-251-10B 2-ISI-56 0

RilR PUMP A DISINARGE (WELDS)

A 8"

8-2RH-7A 29 2-ISI-57 0

RiiR PUMP A DISCIIARGE (llANGERS)

A 8"

8-2Ril-9A 29 22 A

10" 10-2Rii-11 27 A

6" 6-2RH-12 32 2-ISI-58 0

CONTAINHENT SU.T B DISCllARGE (WELDS)

B 12" 12-2 Ril--6 B 2-ISI-59 0

CONTAIhl!ENT S'JMP B DISCliARGE (llANGERS)

B 14" 14-2SI-33B NO.

B 12" 12-2SI-34B NO.

2-ISI-60 0

CONTAINNENT SUMP B DISCHARGE (WELDS)

A 12" 12-2RH-6A 32 2-ISI-61 0

CONTAINMENT SUMP B DISCllARGE (llANGERS)

A 14" 14-2SI-33A NO.

A 12" 12-2SI-34A NO.

2-ISI-62 0

SAFETY IN?ECTION PUMP 22 SUCTION (WELDS)

B 6"

6-2RH-10B 27 2-ISI-63 0

SAFETY IN.IECTION PUMP 22 SUCTION (llANGERS) 2-ISI-64 0

SAFETY INJECTION PUMP 21 Si:CTION (WELDS)

A 6"

6-2R11-10A 27 2-ISI-65 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 35 2-ISI-67 0

REFl!LI.ING WATER STORAGE (HANGERS) 12" 12-2SI-3B 33 TANK DISCllARGE 12" 12-251-4 33 10" 10-2SI-8 31 12" 12-2SI-11 33 2-ISI-68 0

BORIC ACID SUPPLY TO (WELDS) 6" 6-2SI-13A 28 l

SAFETY INJECTION 6"

6-2SI-13B 28 2-ISI-69 0

BORIC ACID SUPPLY TO (HANCERS) 8" 8-2SI-17 30 SAFETY INJECTION 8"

8-2SI-18 30 4

TABLE III NOCIllERN STATES POWER 00.

PAE 3 0F 3 PRulRIE ISLAND UNIT 2 ISOf4ETRIC SitMRY - CLASS 2 REVISIO4 00MPdNDIT OR SYSTkN ILOP j

h II R STN

,y, 2-ISI-70 0

REACTOR VESSEL SAFETY INJECTION (WELDS)

B 6"

6-2SI-25fi 6

2-ISI-71 0

REACTOR VESSEL SAFETY INJECTION (llANGERS) 2-1S1-72 0

REACTOR \\ESSEL SAFETY INJECTICN (WELDS)

A 6"

6-2SI-25A 6

2-ISI-73 0

REACTOR VESSEL SAFETY INJECTION (llANGERS) 8" 8-251-18 30 2-ISI-74 0

BORIC ACID SUPPLY (WELDS)'

2-ISI-75 0

ACCIR!ULATOR DISCllARCE (WELDS)

A 12" 12-2SI-28A 11 2-ISI-76 0

ACCUWJLATOR DISCllARGE (llANGERS) 12" 12-2SI-29A 11 B

12" 12-2SI-73B 11 12" 12-2SI-29B 11

~

l

i A?PENDII C FSAR AUGMETTED EXAMINATION NO EXAMINATIONS SCHEDULED THIS OUTAGE -

PAGE 1 of 1

-,_.c.

-_.-.*,.,..,-*y

f l

h i

.i 1

l i

APPENDIX D SEISMIC BOLTING EXAMINATION i

t d

I t

i l

i 9

Page 1 of 1

NORTHERN STATE 3 POWER CO.

TABLE 2 PRAIRIE ISLAND UNIT 2

PAGE I

OF 6

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

SEISMIC BOLTING cNE-"

INSP.

R E Q'D.

AMT.

ITEM INSPECTION sus N DE I Tl N ITEM PER.

AMT, EXAM aO8ENT'J3CATf0N 9EPCMT NO.

GORY ITEM TO BE EXAMINED N/A N/A STEAM GENERA'IORS SIEA14 GFNERA' LOR NO. 21 UPPER RING GIRDER WE 2

2 SNUBBER 1 77-72 (SNUBBER PINS)

'INO 2'

2 WUBBER 2 80-180 8

SNUBBER I 'I11RU 4 81-97 TIREE 4

UPPER RING GIRDER WE 5

5

'IOP ROW 77-143 (SNUBBER WALL BOLTS)

'INO b

5 GWIER ROW 80-110 15 ALL BOLTS81-106 UIRLE 5

UPPER RING GIRDER WE 8

8

'IOP ROW W GIRDER 77-143 (SNUBBER BOLTS)

'INO 8

8

'JOP ROW CN WALL 80-176 32 ALL BOLTS 81-98 TIREE 16 UPPER RING GIRDER WE 10 10 RING 00N. 2 77-159 (RING 00tNECT BOLTS)

'IND 10 10 RING 00N. I 80-110 40 PAD 1 THRU 4 81-119,114,114R TIREE 20 brPER RING GIRDER WE 10 10 10 EXAMINED 77-159 (RING WALL BOLTS)

'IWO 10 10 10 EXAMINED 80-110 30 PAD 1 UlRU 4 81-107,108,109,110

'IIIREE 10 (REPEAT INSP.)

ODIDW PINS WE 2

2 B0r COL 1/10P OLL 4 77-69,70

'INO 2

2 Bor & 'IOP CDL 2 80-182 8

00 WPW 1 DIRU 4 81-135

'IOP & BOPIOK

'IliREE 4

FORM 9 7-34 74 S/70 FOftM NO. SSt-lett PP8-B-22

TABLE SB NORTHERN STATES POWpR CO.

2 op b

PRAWlE ISLAND UNIT PAGE_

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

st;ISMIC BOLTING NE T S M SUB INSP.

R EO'O.

AMT.

BTEM INSPECTION E-D p

q ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO DE EXAMINED N/A N/A (S.G. NO. 21 CONP'D) i BASE ANCHOR BOLTS CNE 8

8 BASE OF 00W m 1 77-143 UNO 8

8 BASE OF GXUm 2 80-106 32 BASE OF OQU M4 1 81-80 WIRL) 4 711REE 16

'IOP 00WW 04E 4

4 TOP OF 00W M 1 77-165 00m ECTING BOUIS

'IWO 4

4

'IOP OF 00w m 2 80-173 16 TOP OF CDwm 1 81-136,149 TH10 4

. 'IHREE 8

UPPER RING GIRDER 2

SGH-2,SGH-4 81-111,112 (SPRING HANGER)

SUPPORT PAD 04E 6

6 (Dwm 1 77-62 HELI-CDIL SCREWS

'INO 6

6 COWW 2 80-183 24 ALL HELIODIL SCREW 81-122 111REE 12 STEAM GENERA'IOR NO. 22 UPPER RING GIRDER Q4E 2

2 SNUBBER 1 77-71 (SNUBBER PINS)

'INO 2

2 94UBBER 2 80-180 8

fNUBBER 1711RU 4 81-96

':IIREE 4

UPPER RING GIRDER Q4E 5

5

'IOP ROW 77-142 (SNUBBER WALL BOLTS)

'INO 5

5 CENIER ROW 80-111 15 ALL BOLTS 81-99 111REE 5

UPPER RING GIhDER Q4E 8

8 TOP B0 lion GIRDER 77-142 (SNUBBER BOLTS)

'INO 8

8

'IOP ROW ON WALL 80-112 32 AIL BOLTS 81-95 111REE 16 ronM 37-a47s e/re rones no. ess-s ees PP8-B-23

\\

NORTHERN STATES POWER CO.

TABLE SB PRAIRIE ISLAND UNIT _2 PAGE 3

OF_6___

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

SEISMIC BOLTING 8

SUB INSP.

R E O'D.

AMT.

BTEM INSPECTION E.

N DE PTl0N ITEM

PER, AMT.

2XAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED N/A N/A (S.G. NO. 22 00NF'D)

UPPER RING GIRDER

@E 10 10 RI!G OQN. 4 77-160 (RING CONECT BOLTS)

'IND 10 10 RING G A. 1 80-111 40 PAD 1 'HIRU 4 81-118,120

'HiREE 20 UPPER RING GIRDER 04E 10 10 10 EXAMINED 77-160 (RING WAIJ. BOLTS)

'IWO 10 10 10 EXAMINED 80-111 30 PAD 1 'DiRU 4 81-102,103,104,105

'IHREE 10 (REPEAT INSP.)

00W M PINS Q4E 2

2 Cows 1 77-65

'IWO 2

2 00wm 2 80-182 8

00mm 1 'IHRU 4 81-135

'IOP & BOI'IOM

'IHREE 4

BASE ANOIOR BOLTS OE 8

8 BASE OR COW m 1 77-160

'IWO 8

8 BASE OF QXUm 2 80-106 32 BASE OF COwm 1 81-79

'DIRU 4

'DIREE 16 UPPER RING GIRDER 2

SCH-2,SGH-4 81-100,101 (SPRING HANGER)

'IOP COLUM WE 4

4

'DOP OF 00w!N 1 77-165 CONNECTING BOLTS

'INO 4

4

'IOP OF Cows 2 80-113 16

'IOP OF COWN 1 81-137,148

'DIRU 4

'IHREE 8

SUPPORT PAD WE 6

6 OOwm 1 77-61 IELI-COIL SCREWS

'INO 6

6 00wm 2 80-184 24 ALL HELIODIL SCREWS81-151

,, m..n.

TABLE 2 NORTHERN STATES POWgR CO.

PRAIRIE ISLAND UNIT PAGE 4

OF 6

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

SEISMIC BOLTING EXAM COMPONENT OR SYSTEM SUB g p.9' ft EO'D.

AMT ITEM INSPECTION E-A D DE ITEM Pert.

AMT.

EXAM IDENTIFICATION REPORT NO.

y yO EE A NED N/A N/A (PUMP NO. 21 GNf'D)

PRESSURIZER BASE ANOIOR BOLTS OE 8

8 1-8 BOLTS77-146 1NO 8

8 9-16 BOLTS80-114 24 AIL BOIIIS 81-91 VIREE 8

ACCUMJIATOR A BASE ANOlOR BOLTS OE 8

8 1-8 BOLTS77-141

'INO 8

8 9-15 BOLTS80-115 24 AIL BOLTS 81-90 THREE 8

ACCUMJIA'IOR B BASE ANO10R BOLTS JE 8

8 1-8 IK>LTS77-141 INO 8

8 9-16 BOLTS80-115 24 AIL BOLS 81-88 TIREE 8

N/A N/A REACIOR COOLANT PUMPS PUMP NO. 21 CDIAM1 PINS OE 2

2 00WW 1 77-67

'INO 2

2 00W W 2 80-?81 6

00WW 1 DIRU 3 81-135

'IOP & B0frIOM THREE 2

BASE ANOIOR BOLTS OE 8

8 BASE OF 00WMN' 1 77-158 TWO 8

8 BASE OF 00WW 2 80-107 24 BASE OF 00W W 1 81-82

'IHRU 3 TIREE 8

roned s 7-sere e/7e roame eso. ese-s ees PP8-B-25

A 2

TABLE NORTHERN STATES POWpR CO.

D PRAIRIE ISLAND UNIT PAGE Of

""C NN INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:_

SUB INSP.

R EO'D.

AMT.

ITEM INSPECTION E.

N DE I Tl N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED N/A N/A (PtXP NO. 21 00NP'D) 00mm CONNECPING OE 6

6

'IOP OF 00WM 1 77-163 BOLTS

'INO 6

6

'IOP OF 00wm 2 80-174 18

'IOP OF CDwm 1 81-154,156 MiW 3

'111REE 6

TIE BACK BOLTS OE 1

1 PAD 1 77-77

'INO 1

1 PAD 2 80-179 3

PAD 1 MiRU 3 81-150,157,160,161

'111REE 1

TIE BACK PINS GE 1

1 PAD 1 71-6 8

'INO 1

1 PAD 2 80-186 3

PAD 1 DIRU 3 81-135

'IliREE 1

'IllD00Gil ANCIKE QE 2

2 PAD 1, SOUrti 2 77-161 BOIES

'INO 2

2 PAD 1, CENIER 2 80-175 6

PAD 1, ALL BOLTS81-157,168 DIREE 2

IA'IERAL SUPPORP AND OE 4

4 PAD 2 7/-158 ELL BC.LTS

'IW) 3 3

PAD 3, 'IOP ROW 80-175 10 PAD 2 & 3,ALL BOLTS81-160,161 DIREE 3

PlTAP NO. 22 00wMN PINS

'OE 2

2 00W M 1 77-64

'IWO 2

2 Comm 2 80-181 6

Cows 1 DIRU 3 81-135

'IOP & LCfl0M DIREE 2

FORM 37 2476 6/78 FORM AO. B51-9 99 9 PP8-B-26

NORTHERN STATES POWER CO.

TABLE SB PRAIRIE ISLAND UNIT _ 2 PAGE 6

op 6

INSERVICE INSPECTION-EXAMINATION

SUMMARY

MAJOR ITEM:

SEISMIC BOLTING SUB INSP.

R EO'D.

AMT.

ITEM tNSPECTION E-N DE RI I N ITEM PER.

AMT.

EXAM IDENTIFICATION REPORT NO.

GORY ITEM TO BE EXAMINED N/A N/A (PUMP NO. 22 00Nr'D)

BASE ANCHOR BOLTS WE 8

8 BASE OF 00w s 1 77-161

'IWD 8

8 BASE OP 00w m 2 80-107 24 BASE OF 00w m 1 81-81 DIRU 3 DIREE 8

00w m 00m ECTING WE 6

6

'IOP OP OXUm 1 77-162 BOLTS

'IWO 6

6

'IOP OP 00w m 2 80-108 18

'IOP OF ODwm 1 81-142,153 DiRU 3 UIREE C

TIE BACK BOLTS WE 1

1 PAD 1 77-76

'IWO 1

1 PAD 2 80-179 3

PAD 1 DIRU 3 81-145,147,158,159 DIREE 1

TIE BACK PINS WE 1

1 PAD 1 77-66

'IWO 1

1 PAD 2 80-186 3

PAD 1 DIRU 3 81-135 "IIIREE 1

'IIIROUGil ANCHOR WE 2

2 PAD 1, SOLTI112 77-158 BOLTS

'IWO 2

2 PAD 1, CENIER 2 80-109,109R 6

PAD 1, ALL BOLTS81-145,168

'I11REE 2

LATERAL SUPPORT AND QE 4

4 PAD 2 77-161 WALL BOLTS

'IWO 3

3 PAD 3,'IOP ROW 80-109 10 PAD 2 & 3,ALL BOLTS81-158,159

'IliREE 3

ronne a 7 247e e/7s rones seo.ese-seos PP8-B-27

NORTNERN STATES POWER COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 1

OF 4

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPO N / SYSTEM

_ IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS ISO MET 110D SEISMIC BOLTING PRGURAM STEAM GENERATOR NO. 21 UPPER RING GIRDER 85 UT 8 PINS 81-97 NONE NONE NONE SNUBBER PINS UPPER RING GIRDER 86 UT 15 BOLTS81-106 NONE NONE NONE SNUBBER WALL BOLTS UPPER RING GIRDER 85 UT 32 BOLTS 81-98 NONE NONE NONE SNUBBER BOLTS UPPER RING GIRDER 85 UT 40 BOLTS81-119 NONE NONE NONE RING CONNECT BOLTS VT 40 BOLTS81-114 NONE LOOSE NUT NONE 81-114R NONE - NUTS NONE TIGitTENED UPnER RING GIRDER 85 UT 10 BOLTS81-107 NONE NOME NONE WALL BOLTS UT 4 BOLTS81-108 NONE NONE NONE UT 10 BOLTS81-109 NONE NONE NONE UT 6 BOLTS 81-1M NONE NONE NONE COLUMN PINS 78 UT 4 PINS-TOP 81-135 NONE NONE NONE 77 UT 4 PINS-BOT 81-135 NONE NONE NONE BASE ANCllGR BOLTS 77 UT 32 BOLTS 81-80 NONE NONE NONE

~l TOP COLUMN CONNECTING 87 UT 16 BOLTS81-136 NONE NONE NONE BOLTS VT 16 BOLTS81-149 NONE NONE NONE IIELI-COIL SCREWS 87 UT 24 SCREWS81-122 N/A NONE-BASELINE NONE t

UPPER RING GIRDER 85 VT SGil-2 81-100 N/A NONE NOME SPRING llANGER VT SGil-4 81-101 N/A NONE Nc Mf; I

FORM NO. ISI-1003

NORTHERN STATES POWEh COMPANY TABLE II PRAIRIE ISLAND UNIT II PAGE 2

0F 4

BASELINE COMPARISON SUMMART NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM I

ISO MET 110D IDENT.

NO.

INDICATIONS INDICATIONS LIMTTATIONS STEAM GENERATOR NO. 22 TIPPER RING GIRDER 85 UT 8 PINS 81-96 NONE NONE NONE SNUBBER PINS UPPER RING GIRDER 86 UT 15 BOLTS 81-99 NONE NONE NONE l

SNUBBER WALL BOLTS l

l I

UPPER RING GIRDER 85 UT 32 BOLTS 81-95 NONE NONE NONE SNUBBER BOLTS UPPER RING GIRDER 85 UT 40 BOLTS81-120 NONE NONE B.E. " TIT" ilING CONNECT BOLTS VT 40 BOLTS81-118 NONE NONE NONE UPPER RING GIRDER 85 UT 10 BOLTS81-102 NONE NONE NONE WALL BOLTS UT 4 BOLTS81-103 NONE NONE NONE UT 10 EOLTS81-104 NONE NONE NONE UT b BOLTS81-105 NONE NONE NONE COLUMN PINS 78 UT 4 PINS-TOP 81-135 NONE NONE NONE

• 77 UT 4 PINS-BOT 81-135 NONE NONE NONE BASE ANCi!0R BOLTS 77 UT 32 EOLTS 81-79 NONE NONE

,NONE TOP COLUMN 87 UT 16 BOLTS81-137 NONE NONE NONE CONNECTING BOLTS VT 16 BOLTS81-148 NONE LOOSE BOLTS NONE 81-148R-NONE-BOLTS NONE TIGllTENED llELI-COIL SCREWS 87 UT 24 SCREWS81-151 N/A NONE-BASELINE NONE UPPER RING GIRDER 85 VT scil-2 81-111 N/A NONE NONE SPRING llANGER VT SGH-4 81-112 N/A NONE NONE I

g

~

FORM NO.1S1-1003 r

I II NORTHERN STATES POWER COMEANY TABLE PRAIRIE ISLAND UNIT II PAGE 3 0F 4

BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONEN'I'/ SYSTEM

. IDENT.

NO.

INDICATION.9 INDICATIONS LIMITATIONS ISO METilOD PRESSURIZER BASE ANCll0R BOLTS 88 UT 24 BOLTS 81-91 NONE NONE NONE ACCUMULATOR A BASE ANC110R BOLTS 88 UT 24 BOLTS 81-90 NONE BOLT #13 & 14 NONE 5% BACK REFLEC-TION ACCUMULATOR B BASE ANC110R BOUfS 89 UT 24 BOLTS 81-88 NONE NONE NONE REACTOR COOLANT PUMP NO. 21 COLUMN PINS 80 uT 3 PINS-TOP 81-135 NONE NONE nolle 79 UT 3 PINS-EUT 81-135 NONE NONE NONE BASE ANC110R BOLTS 79 UT 24 BOLTS 81-82 NONE NONE NONE COLUMN CONNECTING BOLTS 80 UT 18 BOLTS81-156 NONE NONE NONE VT 18 BOLTS81-154 NONE NONE NONE TIE BACK BOLTS 81 UT 1 BOLT 81-160 NONE NONE NONE j

UT 1 BOLI 81-161 NONE NONE NONE UT

'l ILOLT 81-157 NONE NONE NONE VT 3 BOLTS81-150 NONE LOOSE NUT NONE 81-150R NONE - NUT TIGitTENED TIE BACK PINS 84 UT 3 PINS81-135 NONE NONE NONE T11RU ANC110R BOLTS 84 UT 6 BOLTS81-157 NONE NONE NONE VT 5 BOLTS81-168 NONE NONE NOME FORM NO. ISI-1003

l t

l I

NOR111E15 STATES POWER COMPANY TABLE II l

PRAIRIL ISIAND UNIT II

PACE, 4 0F 4 BASELINE COMPARISON

SUMMARY

NSP NDE W BASELINE REPORT BASELINE ISI EXAMINATION COMPONENT / SYSTEM

_ IDENT.

NO.

INDICATIONS INDICATIONS LIMITATIONS ISO METHOD l

LATERIAL SUPPORT 84 UT 4 BOLTS81-161 NONE NONE NONE WALL BOLTS UT 6 BOLTS81-160 NONE NONE NONE REACTOR COOLANT PUK? NO. 22 COLUMN PINS 80 UT 3 PINS-TOP 81-135 NONE NONE NONE 79 UT 3 PINS-BOT 81-135 NONE NONE NONE BASE ANC110R BOLTS 79 UT 24 BOLTS 81-81 tiONE NONE NONE COLUMN CONNECTING BOLTS 80 UT 18 BOLTS81-142 NONE NONE NONE VT 18 BOLTS81-153 NONE NONE NONE TIE BACK BOLTS 81 UT 1 BOLT 81-145 NONE NONE NONE UT 1 BOLT 81-159 NONE NONE NONE UT 1 BOLT 81-158 NONE NONE

!!ONE VT 3 BOLTS81-147 NONE NONE NONE TIE BACK PINS 81 UT 3 PINS81-135 NONE NONE NONE TilRU ANC110R BOLTS 81 UT 6 BOLTS81-145 NUTS NOT NONE NONE FLUSil VT 6 BOLTS81-168 NONE

,NONE LATERIAL SUPPORT 81 UT 4 BOLTS81-159 NONE NONE NONE WALL BOLTS UT 6 BOLTS81-158 NONE NONE NONE FORM NO. ISI-1003

l

~

l

\\

APPENDIX E TABE I

- PERSONNEL LISTING l

TABE II - ULTRASONIC CALIBRATION BLOCKS TABE III - PROCEDURE LISTriG TABE IV - EQUIfMENT AND MATERIALS Page 1 of 1

1 NORTHERN STATES POWER COMPANY APPENDIX E

~

PRAIRIE ISLAND UNIT II TABLE

~

PERSONNEL LISTING PAGE 1 0F 1 ASNT LEVEL EXAMINER TITLE ORGANIZATION UT PT MT VT II II II (lb)

F. Abrigo Technician LMT (2)

L.R. Davis Technician LMT I

II I

R.A. Kellerhall Technician LMT II II II II (la,b)

R.W. Pechacek Techn cian LMT II II I '.

II (lb) d E.L. Thomas Supervisor LMT III III 111 III (la,b)

W.M. Tighe Technician IJIT II I

I G.T. Lenertz Production NSP II II II (lb)

Engineer II (la,b)

L.C. Dahlman M&SP Special-NSP II II list D.B. Hansen Assoc M&SP NSP III III III III (lb)

Engineer C. Lindstrom ANII Hartford Steam Boiler Inspection

& Insurance Co.

FOOTNOTES:

(la) Certified by NSP to perform Visual Determination of Structural Integrity for Hanger Assemblies in accordance with NSP-VT-2.

(lb) Inspection experience and NDE Qualifications were judged to be adequate to perform Visual Examinations in accordance with NSP-VT-1.

(2)

Organization:

Lambert, MacGill, Thomas, Inc. (LMT) 771 Brokaw Road San Jose, CA 95&l2

10RTllERN STATES POWER COMPANY APPENDIX E PRAIRIE ISLAND UNIT II TABLE II ULTRASONIC CALIBRATION BLOCKS F! SE 1 0F 2 PIPE SCllEDULE SERIt.L OR 1

NSP NO.

SIZE & DIA.

& TilICKNESS MATERIAL llEAT NUMBER CALIBRATION REPORTS DATE 4

3" Scil 160

.438" 316 M5900 hK-1 2-26-81 6

6" Scil 160

.718 316 M3715 BMT-4 3-2-81 RK-2 2-28-81 RWP-7 2-28-81 RWP-8 3-2-81 8

8" SCll 120

.719 316 J2338 ELT-1 3-11-81 15 CAST R.C. PIPE A-351 B2877 RK-7 3-5-81 CF8A RK-14 3-10-81 RK-20 3-17-81 23 30" 1.045" A-515 88526 ELT-3 3-11-81 CR. 70 RWP-6 2-28-81 24 31" 1.534" A515 79114 BMT-1 2-24-81 CR. 70 RWP-10 3-3-81 RWP-12 3-4-81 25A 5-5/16" +

SA533 C2220/1 EMT-8 3-14-81 Cl.AD (T) X CR. B CL. 1 RK-15 3-13-81 7-1/16" (W)

RK-16 3-13-81 X 17-3/4" (W) 26 3-1/2"(T)

A-533 52391 BMT-6 3-11-81 X 6" (W) X CR. A CL. 2 BMT-7 3-12-81 12" (L)

DBil-1 3-11-81 27 6"

SCll 40

.280" 304 2P5951 RWP-9 3-2-81 36 16" Scil 100 1.031" &

A-106 45124A RWP-3 2-27-81

.585" CR. C RWP-4 2-27-81

~

i h

2_

M E

1 F

1 O_

X I

2 1 1 D

88 NE E

ELE T

67 PBG A

1 1 PAA D

ATP 33 S

TRO PE R

N 34 O

1 1 I

T PP A

WW R

RR B

ILAC

.R RE OBM 0

LIR 4

At S

I A

RT S

EA SE l

l L

D A

U I

T R

S E

T A

V.

M R

ELS US DE EN 1

K 1CC SI l

ET P

I &

Y S

P N

T.

A C

P O

M L

O B

.)

CI A

AL IN I

1(

R O

D D"

ETI 2

WTT OI A 4

PNR E

/ '5 UB Z

3 S

I I

EDL S

5X TNA

!'. AC TL SSC I I N

N REO O

0 N

EI S 5

lIRA TI R PS RAT H

ORL NPU tl IT1 lI l}ll lll

NORTilERN STATES POWER COMPANY APPENDIX E

PRAIRIE ISLAND UNIT II TABLE III PROCEDURE LISTING PAGE I 0F 1

PROCEDURE NUMBER FIELD PLANT APPROVAL FIELD CilANGE j

AND REVISION CllANGE PROCEDURE TITLE DATE REMARKS CIIANGE DESCRIPTION NSP-MT-1, REV. 2 N/A MAGNETIC PARTICLE l-8-81 NONE EXAMINATION NSP-MT-2, REV. O N/A WET MAGNETIC PARTICLE l-8-81 NONE EXAMINATION NSP-FT-1, REV. 2 N/A LIQUID PENETRANT l-8-81 NONE EXAMINATION NSP-UT-1, REV. 1 N/A ULTRASONIC EXAMINATION 1-8-81 NONE OF PIPE WELDS NSP-UT-2, REV. 1 N/A AU'IDMATIC DATA RECORDING 1-8-81 N')NE NSP-UT-3, REV. 1 N/A ULTRASONIC EXAMINATION 2-20-81 NONE OF FERRITIC VESSELS NSP-UT-4, REV. 1 N/A UL*1RASONIC EXAMINATION 1-8-81 NONE 0F STUDS, BOLTS AND NUTS NSP-UT-4B, REV. 1 N/A AXIAL ULTRASONIC EXAMINA-2-20-81 NONE TION OF S' IUDS AND BOLTS NSP-UT-11, REV. 1 N/A UL'IRASONIC EXAMINATION 2-20-81 NONE OF CAST STAINLESS STEEL PIPING NSP-VT-1, REV. 2 N/A VISUAL EXAMINATION 1-8-81 NONE l

NSP-VT-2, REV. 2 N/A VISUAL EXAMINATION OF 1-8-81 NONE I! ANGER ASSEMBLIES g

I

NORTHERN STATES POWER COMPANY APPENDIX E

PRAIRIE ISLAND - UNIT 2 TABLE IV EQUIPMENT AND MATERIALS PAGE 1 0F 2

MATERIAL OR TYPE OR CALIBRATION DATE REMARKS EQUIPMENT SERIAL NUMBER OR BATCH NUMBER 1

ULTPASONIC:

NORTEC 130 S/N 130-60 CAL:

1-6-81 NORTEC 130D S/N 130-63-D CAL:

1-6-81 NORTEC 131D S/N 128 CAL:

1-2-81 NORTEC 131D S/N 311 CAL:

2-18-81 NORTEC 131D S/N 322 CAL:

12-2-80 0FF SITE 3-7-81 NORTEC 131D S/N 322 CAL:

3-9-81 NORTEC 131D S/N 360 CAL:

9-19-80 RECAL ON SITE 3-13-81 SONIC FTSMK1 S/N 755111 CAL:

12-24-80 RECORDERS:

GOULD 222 S/N 928 CAL:

2-20-81 GOULD 222 S/N 929 CAL:

2-20-81 COULL 222 S/N 1382 CAL:

2-20-81 TEMPERATURE CAUCES:

PTC SURFACE S/N 237 CAL:

5-28-80 CERTIFIED BY THERMOMETER S/N 240 CAL 5-28-80 MANUFACTURER S/N 256 CAL:

5-28-80

~

S/N 271 CAL:

12-3-80 S/N 353 CAL:

1-12-81 S/N 356 CAL:

1-12-81 MAGNETIC PARTICLE:

MAGNAFLUX YOKE S/N LMT-100 CAL:

2-23-81 ON SITE QUALIFICATION MAGNAFLUX YOKE S/N GTL 001 CAL:

3-20-81 ON SITE QUALIFICATION MAGNAFLUX COIL S/N GTL-2 BLACK RAY METER S/N 14935 CAL:

9-29-80 ROMPAS BLOCKS 304 S/S S/N 4 CERT 9-13-76 BY ORLA' S ??AC9INE SHOP 304 S/S S/N 14 CERT 5-17-78 BY ORLA'S MACH 1NE SHOP 4140 C/S S/N 17 CERT 5-17-78 BY ORLA'S MACHINE SHOP IIW BLOCK ASTM-A-36 S/N LMT-2 CERT 5-09-80 BY DIMAC MACHINE CO.

MATERIALS:

MAGNAFLUX PENETRANT SKL-HF/S BATCH NO.

80C094

NORTHERN STATES POWER COMPANY APPENDIX E

PRAIRIE ISLAND - UNIT 2 TABLE IV EQUIPMENT AND MATERIALS PAGE 2

0F 2

MATERIAL OR TYPE OR CALIBRATION DATE REMARKS EQUIPMENT SERIAL NUMBER OR BATCH NUMBER MATERIALS (CONT'D)

SPOTCHECK DEVELOPER SKD-NF BATCH NO 80H091 CLEANER SKC-NF BATCH No.79M015 MAGNAFLUX

1. 14AM FLUORESCENT BATCH No.79J109 PREPARED BATH MAGNAGLO

1. 20A FLUORESCENT BATCH NO.80C149 UATER MIX ULTRASON'.C LMT CEL BATCH NO.

COUPLANT LMT 979152 ULTRASONIC TRANSDUCERS:

SIZE FREQUENCY HARISONIC3 013570

.250" 5 MHE HARIS0NICS N1126

.750" 2.25 MHE HARIS0NICS P377

.5" x.5" 2.25 MHE HARIS0NICS P8120

.5" x.5" 2.23 MHE HARIS0NICS Q1032

.5" x.5" DUAL 1.5 MHE HARIS0NICS Q1265

.5" x.5" DUAL 1.5 MHB HARIS0NICS R9167

.25" x.25" 5 MHE HARIS0NICS R10021

.5" x 0 2.".5 MHE HARIS0NICS R12200

.25" x.25" 2.25 MHE HARIS0NICS R9159A & B 1" x 1" DUAL 1 MHB PANAMETRIC A $34 -S

.5" 2.25 MHE AER0 TECH 015450

.5" 2.25 MHE AER0 TECH 015*)63

.5" 2.25 MEE AER0 TECH 016575 1"

2.25 MHZ NORTEC 983

.5" x 1" 2.25 MHE NORTEC 1386 1" x 1" 2.25 MHE NORTEC 6807

.75" 2.25 MHE NORTEC 6948

.5" 2.25 MHE NORTEC CSS-679 1"

1 MHE l

I

APPENDIX F FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTION I

l l

l l

f L

i t

(

PAGE 1 0F 1 i

1 l

FORM NIS-1 OWNERS' DATA RE? ORT FOR INSERVICE INSPECTIONS l

l (As Required by the Provisions of the ASME Code Rules)

I 1.)

Owner NORTHERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLIS, MINN 2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit II 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 facturer or Installer State or National Appureenance or Installer Serial No.

Province No.

Board No.

Bl.0 REACTOR VESSEL CREUSOT-LOIRE 687 MINN. 200-51 Bl.3 VESSEL-TO-FLANGE AND HEAD-TO-FLANGE CIRCUMFERENTIAL WELDS VESSEL-TO-FLANGE CREUSOT-LOIRE W-1 e

HEAD-TO-FLANGE CREUSOT-LOIRE W-6 Bl.4 PRIMARY N0ZZLE-TO-VESSEL AND N0ZZLE INSIDE RADIUSED REACTOR CORE COOLANT CREUSOT-LOIRE N0ZZLE (OUTLET)

RCC-B-1 UNDERCLAD CRACKING EXAMINATION REACTOR CORE COOLANT CREUSOT-LOIRE I

N0ZZLE (OUTLET)

N0ZZLE A N0ZZLE B 31.6 N0ZZLE-TO-SAFE END WELDS REACTOR CURE COOLANT CREUSOT-LOIRE N0ZZLE (OUTLET)

RCC-B-13.E.

Bl.8 CLOSURE STUDS AND NUTS STUDS 17-32 CREUSOT-LOIRE NUTS 17-32 Bl.9 LIGAMENTS BETWEEN THREADED STUDE HOLES 9 TO 11 & 36 TO 40 CREUSOT-LOIRE ISI-1019, Rev. O Page 1 of 15

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, MINN.

2.)

Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT,-UNIT II Addreas WELCH, MINNESOTA 3.)

Plant Unit II 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 Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

Bl.10 CLOSURE WASHERS AND BUSHINGS WASHERS L7-32 CREUSOT-LOIRE l

Bl.ll PRESSURE RETAINING BOLTING CONSEAL BOLTS CREUSOT-LOIRE PER MARMON CLAMP l-3 Bl.13 CLOSURE HEAD CLADDING HCP-3 CREUSOT-LOIRE HCP-4 HCP-1 Bl.14 VESSEL CLADDING VCP-3 CREUSOT-LOIRE 2 PATCHES B2.0 PRESSURIZER WESTINGHOUSE 1191 68-57 B2.4 N0ZZLE-TO-SAFE-END WELDS SAFE'lY LINE A NAVC0 W-1A S.E.

SAFETY LINE B NAVC0 W-1B S.E.

B2.ll PRESSURE RETAINING BOLTING PRESSURIZER MANWAY BOLTS NAVC0 B3.0 STEAM GENERATOR WESTINGHOUSE 1181 68-39 ISI-1019, Rev. O Page 2 f

15

l t

{

I i

I 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, HINNEAPOLIS, MINN.

2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II Address WELCH, MINNESOTA II 4.)

Owner (Certificate of Authorization) --

3.)

Plant Unit 5.)

Comercial Service Date 12-21-74 6.)

Nartonal Board Number for Unit--

7.)

Components Inspected Mantfacturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

B3.3 N0ZZLE-TO-SAFE END WELDS STEAM GENERATOR NO. 21 RCC-A-5 S.E.

NAVC0 B3.10 PRESSURE RETAINING BOLTING (42 INCH DIAMETER)

STEAM GENERATOR NO. 21 WESTINGHOUSE 1181 68-19 MANWAY A BOLTS MANWAY B BOLTS 4

B4.0 PIPING PRESSURE BOUNDARY B4.1 SAFE END TO PIPING AND SAFE END IN BRACH PIPING WELDS REACTOR VESSEL REACTOR CORE COOLANT RCC-B-1 S.E.

NAVC0 STEAM CENERATOR NO. 21 RCC-A-5 S.E.

NAVC0 PZR SAFETY LINE A W-1 NAVC0 PZR SAFETY LINE B W-1 NAVC0 PZR SPRAY LINE W-22B NAVC0 I

ISI-1019, Rev. O Page 3 f 15

FCRM N.5-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As gaquired by the Provisions of the ASME Code Rules) 1.)

Owner NORTHERN STATES POWER COMPANY Address 414 NICOLLET MALL, MINNEAPOLIS, MINN.

2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit II 4.)

Owner (Certificate of Authorization) --

5.)

Cournercial Service Date 12-21-74 6.)

National Board Number for Unit --

7.\\

Components Inspected Manu fa cturer Component or Manufacturer or Installer State or National Aopurtenance or Installer Serial No.

Prov! nee No.

Board No.

B4.5 CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS REACTOR CORE COOLANT CROSSOVER LINE B RCC-B-12 NAVC0 LINE A RCC-A-6 NAVCO RCC-A-7 NAVC0 PZR SAFETY LINE A W-3 NAVC0 W-4 NAVC0 PZR SAFETY LINE 5 W-6 NAVC0 W-7 NAVC0 B4.6 BRANCH PIPE CONNECTION WELDS EXCEEDING SIX INCH DIAMETER RESIDUAL HEAT REM 07AL TAKE OFF W-ROOT NAVC0 B4.7 BRANCH PIPE CONNECTION WELDS SIX INCH DIAMETER AND SMALLER RESIDUAL TEMPERATURE DETECTOR TAKE OFF W-ROOT NAVC0 B4 10 SUI >

T COMPONENTS RE'iIDUAL ' JERATURE DEW CTOR.and 0FF COLD LEG B1, PRRCH-281 NAVC0 ISI-1019, Rev. O Page 4 of 15

FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTICNS (As Required by the Provisions of tne ASME Code Rules) 1.)

Owner NORTHERN STATES POWER COMPANY Address PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II p

Address WELCH, MINNESOTA 3.)

Plant Unt:

II 4.)

Owner (Certificate of Authorization) 5.)

Connercial Service Date 12-21-74 6.)

National Board Number for Unit--

7.)

Components Inspected Manu facturer Component or Maau facturer or Installer S ta te or National Appurtenance or Installer Serial No.

Province No.

Board No.

B4.10 (CONT)

RESIDUAL TEMPERATURE DETECTOR TAKE OFF HOT LEG A1, 137-2RTD-5 NAVC0 REACTOR CORE COOLANT A Al NAVC0 B5.0 REACTOR CORE COOLANT PUMPS B5.2 PRESSURE RETAINING BOLTS AND STUDS, WHEN REMOVI') (22 INCH DIAMETER)

SEAL HOUSE BOLTING PllMF A B5.4 INTEGRALLY WELDED SUPPORTS PUMP A SUPPORT A SUPPORT B s

SUPPORT C I

PUMP B SUPPORT A SUI-PORT B SUPPORT C I

ISI-1U19, Rev. O Page 5 of 15 i

6 i

FORM NIS-L OWNERS' DA".A REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules) i NORTHERN STATES F0WER COMPANY l.)

Owner Address 414 NICOLLET MALL HINNEAPOLIS MINN.

2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT II Address, '. 4LCH, MINNESOTA 3.)

Plant' snit II 4.)

Owner (Certificate of Authorization) __

S.)

Commercial Service Date 12/21/74 6.)

National Board Number for Unit-o 7.)

Componeries Inspected Manu fa cturer Coisponent or Manufacturer or Installer State or National i

Appurtenance or Installer Serial No.

Province No.

Board No.

ASF3 CLASS 2

("

3 PRESSURE VESSELS, C1.1 CIRCUMFERENTIAL BUTI W'JLDS STEAM GENERATOR No. 21 l

W-B WESTINGHOUSE 1181 68-39 C1.4 PRESSURE RETAINING BOLTING STEAM GENERATOR NO. 21 1181 68-39 MANWAY A WESTINGHOUSE MANWAY B WESTINGHOUSE STEAM GENERATOR NO. 22 1

MANWAY A WESTINGHOUSE 1182 68-40 MANWAY B WESTINGHOUSE j

C2.0 PIPING C2.1 CIRCUMFERENTIAL BUTT WELDS MAIN STEAM A e

MS-ll NAVC0 MS-l7 NAVC0 MS-16 NAVC0 MS-18 NAVC0 MS-19 NAVC0 MS-20 NAVC0 MS-174 NAVC0 MAIN STEAM B MS-83 NAVCO MS-117 NAVC0 f

ISI-1019, Rev. O Page 6 15

FORM MIS-L OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rulcs)

NORTHERN STATES POWER COMPANY 1.)

Owner Address 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA i

2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT II Address WELCH, MINNESOTA l

l 3.)

Plant Unit II 4.)

Owner (Certificate of Authorization) --

5.)

Cournercial Service Date 12-21-74 6.)

National Board Number for Unit--

l 7.)

Components Inspected i

Manu fa cturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

C2.1 (CONT)

FEEDWATER A FW-177 NAVC0 FEEDWATER B FW-133 NAVC0 RESIDUAL HEAT REMOVAL DISCHARGE W-331 NAVC0 REACTOR \\ESSEL

. SAFETY INJECTION W-349 NAVC0 C2.2 LONGITUDINAL WELD JOINTS IN FITTINGS MAIN STLAM A MS-ll TO MS-12 NAVC0 C2.5 INTEGRALLY WELDED SUPPORTS MAIN STEAM A F, MSH-39 NAVC0 H, MSH-42 NAVCO S, MSH-17 NAVC0 MAIN STEAM B A, MSH-48 NAVC0 H, MSH-41 NAVCO A, MSH-50 NAVC0 FEEDWATER A A, FWH-66 NAVC0 K, FWH-58 NAVCO of ISI-1019, Rev. O Page 7 15

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, MINN.

Address 2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT,. UNIT II Address WELCH, MINNESOTA II 4.)

Owner (Certificate of Authorization) 3.)

Plant Unit 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.

C2.5 (CONT)

FEEDWATER B A, FWH-67 NAVC0 G, FWH-59 NAVC0 REACTOR VESSEL SAFETY INJECTION B, RHRRH-25 NAVC0 C2.6 SUPPORT COMPONENTS MAIN STEAM A G, MSH-54 NAVC0 MAIN STEAM B 0, MSH-82 NAVC0 i

EEACTOR VESSEL SAFETY INJECTION B, SIRH-6 NAVC0 C4.0 VALVES C4.2 PRESSURE RETAINING BOLTING

~

HAIN STEAM A CV-31116 NAVC0 MAIN STEAM A RELIEF HEADER RS-21-14 NAVC0 MAIN STEAM B RELIEF HEADER RS-21-20 l

ISI-1019, Rev. O Page 8 f

15

l-FORM NI3-1 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, MINN.

2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit II 4.)

Owner (Certificate of Authorization) --

5.)

Connercial Service Date 12-21-74 6.)

National Board Number for Unit -

a 7.)

Components Inspected Manu facturer Component or Manu facturer or Installer State or National or Installer Serial No.

Province No.

Board No.

Appurtenance SEISMIC BOLTING COMPONENTS STEAM GENERATOR 68-39 No. 21 WESTINGHOUSE 1181 SNUBBERS 1-4 8 PINS SNUBBER WALL BOLTS 15 BOLTS SNUBBER BOLTS

.)

32 BOLTS RING CONNECT BOLTS PAD 1-4 40 BOLTS RING WALL BOLTS PAD 1-4 30 BOLTS COLUMN PINS COLUMN 1-4 8 PINS BASE INCHOR BOLTS COLUMN 1-4 32 BOLTS COLUMN CONNECT BOLTS COLUMN 1-4 16 BOLTS HELI-COIL SCREWS COLU)ci 1-4 24 SCREWS l

ISI-1019, Rev. O Page 9 of 15

FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code Rules)

NORTHERN STATES POWER COMPANY 1.)

Wnn Address 414 NICOLLET MALL, MINNEAPOLIS, MINN 2.)

Piant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit II 4.)

Owner (Certificate of Authorization) --

5.)

Consnercial Service Date 12-21-74 6.)

National Board Number for Unit-"'

7.)

Components Inspected Manu facturer C.enponent or Manu facturer or Installer State or National l

Appurtenance or Installer Serial No.

Province No.

Board No.

I STEAM GENERATOR l

NO. 21 (CONT)

SPRING HANGER l

SGH-2 NAVCO SCH-4 NAVC0

-i STEAM GENERATOR NO. 22 WESTINCHOUSE 1182 68-40 I

SNUBBERS 1-4

• l 8 PINS SNUBBER WALL BOLTS 15 BOLTS

{

SNUBBER BOLTS 32 BOLTS l

RING CONNECT BOLTS i

PAD 1-4 40 BOLTS RING WALL BOLTS

[

PAD 1-4 I

30 BOLTS COLUMN PINS COLUMN 1-4 I

8 PINS l

BASE ANCHOR BOLTS COLUMN 1-4 32 BOLTS COLUEN CONNECT BOLTS l

COLUMN 1-4 l

(

16 BOLTS f

ISI-1019, Rev. O Page 10 *f 15 6

I

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 l

Address 414 NICOLLET MALL, MINNEAPOLIS, MINN.

2.)

Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit Il 4.)

Owner (Certificate of Authorization) 5.)

Commercial Service Date 12-21-74 6.)

Na tional beard Number for Unit --

7.)

Components Inspected Manu f acturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

STEAM GENERATOR No. 22 (CONT)

HELI-COIL SCREWS COLUMN 1-4 24 SCREWS SPRING HANGER SCH-2 NAVC0 SGH-4 NAVC0 PRESSURIZER WESTINGHOUSE 1191 68-57 BASE ANCHOK BOLTS 24 BOLTS ACCUMULATOR A DELTA SOUTHERN BASE ANCHOR BOLTS 24 BOLTS ACCUMULATOR B DELTA SOUTHERN BASE ANCHOR BOLTS 24 BOLTS REACTOR COOLANT PUMP 21 WESTINGHOUSE W510 COLUMN PINS COLUMN 1-3 6 PINS BASE ANCHOR BOLTS COLUMN 1-3 24 BOLTS l

l ISI-iO19, Rev. O Page of 7

15

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 2.)

Piant PRAIRIE ISLAh*D NUCLEAR GENERATING PLANT. UNIT TT Address WELCH, MINNESOTA 3.)

Plant Unit II 4.)

Owner (Certifieste of Authorization) __

5.)

Consnercial Service Date 12-21-74 6.)

National Board Number for Unit __

7.)

Coeponents Inspected Manu facturer Component or Manu facturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

REACTOR COOLANT PUMP 21 (CONT)

COLUMN CONNECT BOLTS COLUMN 1-3 18 BOLTS TIE BACK BOLTS COLUMN 1-3 3 BOLTS TIE BACK PINS COLUMN 1-3 3 PINS THRU ANCHOR BOLTS PAD 1 6 BOLTS LATERAL SUPPORT WALL BOLTS PAD 2 & 3 10 BOLTS REACTOR COOLANT PUMP No. 22 WESTINGHOUSE W-515

~

COLUMN PINS COLUMN 1-3 6 PINS BASE A!!CHOR BOLTS COLUMN 1-3 24 BOLTS COLUMN CONNECT BOLTS 1

COLUMN 1-3 18 BOLTS l

ISI-1019, Rev. O Page 12 o f 15

4 FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECIIONS l

(As Required by the Provisions of the ASME Code Rules) 1.)

Owner NORTHERN STATES POWER LCy?ANY Address _ 414 NICOLLET MALL, MINNEAPOLIS, MINNESOTA 2.)

Plant PRAIRIE ISLAND NUCLEAR GENERATING PLANT,-UNIT II Address WELCH, MINNESOTA 3.)

Plant Unit II 4.)

Owner (Certificate of Authorization) --

5.)

Consnercial Service Date 12-21-74 6.)

National Board Number for Unit--

7.)

Components Inspected Manu facturer Compor, ant or Manu facturer or Installer State or National Appurtenance or Installer _

Serial No.

Province No.

Board No.

REACT 0.1 COOLANT PUMP NO. 22 (CONT)

TIE BACK BOLTS COLUMN 1-3 3 BOLTS TIE BACK PINS COLUMN 1-3 3 PINS THRU ANCHOR BOLTS PAD 1 6 BO L'is LATERAL SUPPORT "ALL 3OLTS PAD 2 & 3 10 BOLTS ISI-1019, Rev. O Page 13 of 15

FORM NIS-1 (back) 8.)

Examination Dates 2-23-81 to 3-23-81 9.)

Inspection Interval 12-21-74 to 12-21-84 10.) Abstract of Examinations.

Include a list of examinations and a statement concerning status of work required for current interval.

This was the last inservice inspection in the Second Period of the First Ten Year Interval. The examinations completed the required pressure retaining components and their supports of the reactor coolant and associated auxillary systems classi-fied as ASME Class 1 and Class 2,100% of the Seismic Bolting program, and 100%

of the required volumetric, surface, and visual examinations of the reactor vessel welds, studs and cladding we.s performed.

In addition, both reactor vessel outlet nozzle bore area 3 were examined for the presence of underclad cracking.

11.) Abstract of Conditions Noted.

The results of these examinations indicated that the integrity of these systems was maintained. The following is a list of all anomalies detected:

System Item ID Exam Method Type & Number of Indications PER Safety A W-1 PT 2 linear W-1A S.E.

PT 2 linear & several rounded PER Safety B W-1 PT 1 linear W-1B S.E.

PT 6 linear PER Spray W-22B PT 3 linear FW Loop A W-177 MT 4 linear A, Hanger MT 1 linear FW Loop B W-133 MT 23 linears PT 23 linears MS Loop A G, Hanger VT Loose bolt H, Hanger MT 2 linears MS Loop B 0, Hanger VT Nut not flush with base RCC Loop A RCC-A-6 PT 14 linears RVSI B, Hanger PT 6 lin1ar RTD Loop A B1, Hanger VT Hanger tilted a

S/G 21&22 Primary MT 1 bolt - 1 linear, 1 bolt-Manway Bolts dented threads

^

S/G 21&22 Secondary VT 6 bolts - dented threads Manway Bolts 21 bolts gouged S/C 21 Upper Ring VT 2 loose bolts Grinder Connec-ting Bolts l

Page 14 of 15

System Item ID Exam Method Type & Number of Indications S/G 22 Top Column VT 2 loose nuts Connecting Bolts RCP 21 Tie Back Bolts VT 1 loose nut O

RPV Loop A Outlet Noz;1e UT 22 indications Bore Region RPV Loop B Outlet Nozzle UT 83 indications Bore Region 12.) Abstract of Corrective Measures Recommended and Taken.

All anomalies, with the exception of the rounded PT indications on Pressurizer Safety Line A and the indications on the Reactor Pressure Vessel Outlet Nozzle Bore Region, were corrected. The loose nuts and bolts were tightened, and the tilted hanger was straightened. The lirear MT and PT indications were removed by light hand grinding and blending the surface smooth. The bolts with major steam goug(.s and linear indication were replaced. All indications were corre;'.ted and reexamined with the same method that located them.

The several rounded indicaticns on Pressurizer Safety Line A were accepted as is, based on Westinghouse's evaluation conducted in the January 1980 outage. The indications on the Reactor Pressure Vessei Outlet Nozzle Bore Region was also accepted as is, See section 4 for acceptance analysis.

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of he ASME Code,Section XI.

Date Afe2 M

19 F SignedM7uculOmres ff m;m d). By M / A %

Owner V

Cert.ificate of Authorization No. (if applicable)

Expiration Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Mecuesel4 and employed by 64f.,1 Si. Gl..L,a.4 Ls. 0 of U,1 f., d Po e a.

have inspected the com-ponents described in this owner's Data Report during the period A. 23 9 I to 3 23 P/,

and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

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

Da M oco l M

19 Y I l

Commissions h t$ bi 3 2.

c.

300. b 9 Ins'pector's Signature National Board, State, Province & No.

Page 15 of 15