ML20003B140

Inservice Insp Rept on 780911-801107.Summarizes Examination of Reactor Vessel for Refueling Outage.Results of Pressure Piping Attachment Weldments Survey Serve as Baseline Data for New Mods on Existing Support Components

ML20003B140
Person / Time
Site:	Beaver Valley
Issue date:	01/30/1981
From:	Lefebvre B, Williams H DUQUESNE LIGHT CO., WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20003B135	List: ML20003B134 ML20003B140
References
NUDOCS 8102100413
Download: ML20003B140 (78)

Text

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INSERVICE I^4SPECTION REPORT FOR THE BEAVER VALLEY NUCLEAR POWER STATION I

UNIT NO. 1 FOR Q

DUQUESNE LIGHT COMPANY SHIPPINGPORT, PENNSYLVANIA 15077 f

PREPARED BY:

Westinghouse Electric Corporation Nuclear Service Division Inspection Service P.O. Box 2728 Pittsburgh, Pennsylvania 15230 G

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o FORM NIS-1 OWNERS

• DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner h esne Licht Ce=oanv. 435 Sixth Avenue, Pittsburgh. PA 15219 (Narne and Address of Owner)

2. Plant 3eaver Vallev Power Statim, P.O. Box 4, Shippingport, PA 15077 (Name and Address of Plant)

3. Plant Unit 1-856 Ir4

4. Owner Cernficate of Authonzation (if required)

N/A

$. Com ncreial Service *Date 09 30-76 6. National Board Number for Unie

7. Components inspected Manufacturer Component or Manufacturer or Installer State of National Appurtenance or Installer SenalNo.

Provmce No.

Board No.

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Reactor Vesse Combustion Engin.

l 69103 l B-105642 21011*

Reactor Vessel closure Head Co bustion Engin.

69203 N/A 21011 Reactor Vessel Intemals Westinghouse DLW-Z305 N/A N/A lPA434676 l68-50 Dressurizer Westinghouse 1311 Steam Genera to rs Westinghouse l434597 l 68-45

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Loop 1 1301 Loop 2 -

1302 434598 6 8-46 Loop 3 l

1303 434599 68-47 Reactor Coolant Pu=os Wes tinghous e Loop 1 1-618J931G01 N/A N/A Loop 2 2-618J931G01 N/A N/A Loop 3 l

3-618J931G01 N/A l

N/A

.b3Y S.W. Fabricating N/A N/A N/A P"uifIIA Wiping systeng Schneider N/A N/A N/A l

5eEI*f.xcNa$$N Atlas Manufacturing 1308 N/A 1127 l

Boron Iniection Tank Struthers ' Jells Corp. l N/A l 434783 l

13347 Note: Supplemental sheets in form of lists sketches. or drawings may be used provided (!) size is 8% in. x 11 in (2) information in items I through 6 on thes data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at th < :op of tais form.

• Commonwealth of PA, Certificate of Boiler or Pressure Vessel Operation, No. B105642 l

This fcrm iEMS) eev be cetairied frtra the Orcer cect., ASME. 345 L 47th St.. New York, N.Y. 10C17 I

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o FORM NIS 1 OWNERS

• DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner Duquesne Light Company, 435 Sixth Avenue, Pittsburgh, PA 15219 (Name and Address of Owner)

2. Plant Beaver Valley Power Station, P.O. Box 4. Shippingport, PA 15077 (Name and Address of Plant)

3. Plant Unit 1-856 W N/A

4. Owner Certificate of Authorization (if required)

5. Commercial Service Date 09,30-76

/A

6. National Board Nurnber for Unit

7. Components inspeered Manufacturer Component or Manufacturer or insta!!er State or Nanonal Appurtenance or Installer Serial No.

Province No.

Board No.

Residual Heat Exchanger (s)

Joseph Oat & Sons 1832-1 434682 368 1832-2 434583 369 Seal Water Heat Excnanger Atlas 1233 434717 1056

,, o n-EIE"ExNNIer Joseph Oat & Sons 1830-1 434718 361 Regenerative heat exchanger.foseph Oat & Sons 1831-10

'4346 %

Shell 1:438 434687 Shell 2:439 434688 Shell 3:440 Volume Control T,,k Joreph Cat & Sons 1879-1 434716 457 Ir!$ Y$I!ers bfEIlona Filters

$38-10 N/A 1398 539-10 N/A 1399 Reactor Coolant Filter AMF, Cuno 115 N/A 2613 Seal water Return Filter AMF, Cuno 102 434723 2615 Safety Inj.

Accu:nulators Delta Southem Co.

IA N/A 434680 2710 IB N/A 434678 2711 1C y/A 43447o

379, Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8% in. x 11 in (2) information in items I through 6 on this data report is mciuded on each sheet, and (3) each sheet is numbered and the number of sneers is recorded at the top of this form.

This ferri (E00C29) may be otrtemed from the Creer capt., ASME. 345 L 47tn St. New York. N.Y. 10017

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FORM NIS 1 (back)

8. Examination Dates C-11-78 to _f I-7-80

9. Inspection Interval from 9-30-76 to 9 86

10. Abstract of Examinations. Include alist of examinations and a statement concerning status of work required for current interval.

Reference Tab C of Final Report

11. Abstract of Conditions Noted Reference Tab 3 of Final Report

12. Abstract of Corrective Measures 4tecommended and Taken Referente Tab B of Final Report We cernfy that the statements made in this report are correct and the --=i--! and correctzve men-sures taken conform to the rules of the ASME Code Scence XI.

N

! Signed Duquesne I.ight Co.

gy JA4+d 19 Dase Owner p Station Superintendent Certificate of Authorisation No. (if applicable!

N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION to the undersigned, holding a valid commismoM by the National Board oi and P ect and/or the State or Provmee of MA and employed b," e M/ of Insp,M M' have inspected th ponents daicnbed in this Owners' Data Repbr! duking the period C/ - // - 7 7 to //~ Y,

and state that to the best of my knowledge and belief, the Owner hd performed'examinanons and (aken correenve measures desenbed in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.

By signing this cemficate neither the Inspector nor his employer makes any warranry, expressed or implied, I

concerning the examinations and correcuve measures described in this Owners' Data Report. Furthermore, l

neither the Inspector nor his employer sha!! be liable in any manner for any personalinjury or property damage or a loss of any k ansing from or connected with this inspection.

19 Date l

.WAhNco.,ni.i.n, d B M K B o72 W l

/ [ /InspecterjSignature K National Board. State, Province and No.

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DUQUESNE LIGHT COMPANT BEAVER VALLEY UNIT

• l, POWER STATION REFUELING OUTAGE CORE I-II EXAMINATION

SUMMARY

An Inservice Examination of the reactor vessel was performed using the remote tool in accordance with the Program Plan and Westinghouse Procedure 151-152, Revision 6, Dated October 10, 1978. This examination was conducted in February,1980 and the detailed explanation of the tool operation is located under Tab I of this report.

The program utilized volwnetric non-destructive methods in accordance with both the requirements of:

a) ASME Section XI,1974 through the Summer,1975 Addenda.

b) Technical Specification. Section 4.4-4 The initial calibration of the complete ultrasonic system was performed at the Westinghouse NSD Waltz Mill Facility in accordance with procedure WMF-95044-P-001.

All areas examined were found to be acceptable to the requirements of the ASME Code.

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i DUQUESNE LIGHT COMPANY BEAVER VALLEY UNIT ONE POWER STATION INSERVICE INSPECTION INTERVAL 1 PERIOD 1 OUTAGE 1 EXAMINATION

SUMMARY

INTRODUCTION An inservice examination of Class 1, 2 and 3 conponents and piping was conducted at the Beaver Valley Station Unit #1 from September, 1978 thru November, 1980. The examinations were performed in accordance with an approved examination program plan located under Tab C of the Final Report.

Additionally, a surface examination performed on Loop #2, Weld #4DM, was a result of a Duquesne Light Company commitment made to the NRC during an NRC inspection on January 8-11, 1980, Report No. 50-334/30-02. The original examination was performed on Loop #1, Weld #4DM, program items nos. 25 and 28 and is part of NRC unresolved item no. 78-29-03.

During the first refueling outage at BVPS Unit #1 the A, 3, & C reactor coolant pump motors were disassembled for maintenance. While disassembled the flywheels from all three motors were avamined by ultrasonic and liquid penetrant methods.

The main steam and feedwater postulated break points (high energy program) in the main steam valve house were examined as required by Appendix D, Section D.3.2 of the 3VPS Unit #1 Final Safety Analysis Report (FSAR).

Pressure piping attachment veldments resulting from Design Change Packages (DCP's) 253, 257 and 305 (baseplace and hanger modificaticus) were visually and surface examined (M.T. or P.T.), to fulfill the preservice requirements l

of Section II of the ASME Code. The visual examination was performed in accordance with Procedure Ntsnber IP-W-02.

The magnetic particle and liquid l

penetrant examinations were performed in accordance with procedures MT-969-1 and PT-969-1, Rev. 2 respectively. Additions and modifications that resulted from DCP's 253, 257 and 305 do not affect the 3VPS Unit #1 ten-year program. The results of the evamination are coviled under Tab E of this report. This data serves as baseline data for the newly added pressure l

piping attachment veldments made on the already existing support components.

Design Change Packages (DCP's) 162 and 189 resulted in the installation of new safety injection and recirculation spray lines which fall under the Class 2 requirements of Section XI of-the ASME Code. The newly installed line wolds were examined by ultrasonic methods to fulfill the baseline preservice requirements of Section XI.

In addition two welds in which the wall thickness was less than the 0.250 inches required by ultrasenic Procedure ISI-205 were examined by radiography.

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RESULTS Examinations resulted in recordable indication areas being noted on the basis of procedure recording criteria, which generally are more critical than specified in ASME Section XI Acceptance Standards. All of the indications were treated and dispositioned by EM (Engineering Memorandum),

NCAR (Nonconformance and Corrective Action Report), or Onsite Safety Committee review.

A summary of indications is as follows:

A.

Ten minor surface discrepancies were detected by dye penetrant examinations. Eight areas involving multiple linears, one rounded, and one cold lap, were removed by superficial blending. One involving nicks on a threaded stud were accepted as is.

B.

Twelve indications were detected by magnetic particle examinations.

Nine linears, one undercut, one cold lap and one gouge were removed by grinding or blending.

C.

One 3/4 inch subsurface planar indication detected by ultrasonic evamination of ferritic pipe on Loop A main steam weld DLC #4/1 was acceptable as is.

D.

Thirty two indications were detected by visual examinations. Twenty-one involving rust on bolting, of which thirteen were corrected and eight were accepted as is.

Three involving niched threads on bolting, of which two were corrected, and one was accepted. One involving corrosion of bolting of which defected bolting was replaced. Five involving gouges, of which four were accepted and one corrected.

Two involving porosity and one rounded, all of which were corrected.

I l

E.

Nineteen minor indications were detected during the system leakage l

test as a result of small leaks, none of which were uncontrolled, l

all of which were dispositioned. Sixty-two areas were found to have evidence of dried boric acid. All of which were dispositioned.

l EXAMINATIONS Examinations were conducted to review as much of the eynmination Zone as was practical, within geometric, metallurgical and physical limitations.

When the required ultrasonic examination volume or area could not be examined 100%, the examination was considered to be partial (PAR) and so noted. Generally PAR's are noted at fitting-to-fitting assemblies (as -

explained under LIMITATIONS) and in areas where integrally welded supports, lugs, or hangers, etc., preclude access to some part of the examination area.

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Ultrasonic examinations that produced greater than reference level sensitivity, f rom reflectors that are characteristic of metallurgical structure or the I.D. and or 0.D. surfaces of an item were acknowledged only. Examples of areas that generally produce such geometric indications are as follows:

1 (1) I.D. weld prep or root and or the crown overlay or toe.

(2) The I.D. radius of the tube sheet on the channel head to tube sheet veld of steam generators, when eyamining from tube sheet side.

(3) The metallurgical structure of the cast materials.

(4) Responses from the thread areas of bolting.

LIMITATIONS l

Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examination requirements of Section XI of the 1971 Code could be applied; consequently some examinations are limited or not practical due to geometric configuration or accessibility. Generally these limitations exist at all fitting to fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc.,

where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.

The limitations exist to a lesser degree at pipe to fitting assemblied, particularly where the weld is not ground flush with the pipe 0.D. surface.

At these joints examinations can be conducted from the pipe side; however, the fitting again limits or precludes examination from the opposite side.

i l

When the weld surface is flat, the fitting side examination is replaced l

by a calibrated straight beam examination on the weld.

In most cases, examinations in these areas were accomplished as a best effort attempt to cover as such of the code required area or volume (generally, the veld base metal for 1 "T" on each side) as is possible, however, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100%.

Areas where complete examination of 100% of the required volume of area could not be achieved are indicated by A PAR (partial) notation on the avaminers ' data sheet, and the limiting cause' is noted.

The principal basis for PAR's is to identify the inability to examine 100%

of the required base metal volume for the 1."T" distance beyond the edge of the weld on a fitting or component. Examples are (1) ultrasonic examination

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l of a pipe to elbow assembly, where scanning on the intrados of the elbow causes de-coupling of the sound beam and (2) a pipe to flange or valve assembly, where scanning the entire volume on the fitting or component side is limited by configuration.

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4 The resulting coverage is such that examination of the weld, heat affected zone and base metal for 1 "T" on the pipe side can be achieved by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, j

etc.

However, the volume on the fitting or component side additionally l

cannot be scanned completely for transverse indications as required by Code. In either case,100% of this 1 "T" volume cannot be assured, thus a PAR is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.

Specific limitations and restrictions for all evaminations are as indicated on the raw data sheets - Section D of the Outage Report.

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REACTOR VESSEL INSERVICE EXAMINATION PROGRAM FOR DUQUESNE LIGHT COMPANY SEAVER VALLEY UNIT 1 This document details the planned scope of reactor vessel examinations by Westinghouse for refueling outage I-II, including items and areas selected for examinations, examination and documentation crocedures, and drawincs or sketches containing identification of all areas to be examined.

Certifications and oualifications of examiners, materials and equipment will be available on site for review prior to the start of examinations.

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This program and the crocedures incorporated herein require approval by DLC and the Authorized Inspector orier to the start of the examination.

Westinghouse Electric Corporation Prepard by.

O W Approval:

e B.6ILefebvrOLevelIII 1

DLC i -

b' 1b Fe-Representative:

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Authorized Inspector:

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DUQUESNE LIGHT COMPANY

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BEAVER VALLEY UNIT 1 REACTOR VESSEL INSERVICE INSPECTION REFUELING OUTAGE CORE I-II The areas listed below were examined as required by the plant Technical Specification and the 1974 Edition of Section XI of the ASME Boiler and Pressure Code with Addenda through Sumer 1975 utilizing the Westinghouse remotely operated tool.

I VESSEL-TOOL INTERFACE PARA"ETERS (a) Vessel head alignment pins located at 0, 90, 180 and 270 degrees vessel axis.

(b) Closure head guide studs located in stud holes #5, #21, and #37 on 171.25 inch pitch circle diameter.

(c) Tool aligned on pin at 90 degrees, other two legs at 210 and 330 degrees.

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EXAMINATION REQUIREMENTS IWB-2600 Item Bl.3 VESSEL TO FLANGE WELD l

Thirty percent of the total length of the weld to be examined. Examine from centerline of stud hole #8 at 43.45 degrees axis, clockwise around to stud hole #3 at 74.68 degrees vessel axis, 7,d from stud hole #40 at 242.07 degrees to stud hole #52 at 316.55 degrees vessel axis (105 degrees total).

l IWB-2600 Item S1.4 OUTLET N0ZZLE TO SHELL WELD Examine nozzle to shell weld and nozzle protrusion of Loop 1 and 2 outlet nozzles. Centerline of nozzles located 82.86 inches from top surface of l

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flange.

Outlet nozzles located at 25.03 and 144.90 degrees vessel axes.

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IWB-2600 Item Bl.6 0UTLET N0ZZLE TO SAFE-END WELD

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Examine nozzle to safe-end weld on Loop 1, 2 and 3 outlet nozzles at location given under Item 1.4 and Loop 3 nozzle at 65 degrees. Centerline of safe-end weld 122.38 inches from centerline of vessel. This examination also includes requirement for examination of safe-end to pipe weld IWB-2600 Item B4.1.

IWB-2600 Item Bl.9 LIGAMENTS BETWEEN THREADED STUD HOLES Thirty-three percent of the vessel flange ligaments are to be examined.

Examine ligaments around stud holes #8 through #13 and #40 through #52 (19 total). Stud holes are threaded 6"-8N-3B, are 11 inches deep and are located on 171.25 inches pitch circle diameter.

Flange surface is 0.5 inches above flange seal surface.

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m EXAMINATION The above listed areas were examined utilizing the remotely operated vessel inspection tool in accordance with the requirements of procedure ISI-152.

Examinations were performed utilizing search unit sizes, frequencies and refracted angles as defined in the following table. Detailed parameters for the examination of each individual weld or area, including the location of each scan with reference to the vessel axis and datums, the -

number of scans, the incremental distances between scans are defined in the inspection program input data prepared in accordance with procedure RV-ISI-01. (Refer to the input data sheets under this Tab).

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IRlW ENCV INCIDINi RI.FRACIT.D f

) CATION SFARGI UNIT MI:

AEl.1 ANCI.E

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Outlet No::le to Shell Weld US 2.25 te (F

and No::le Protrusica nb 2.25 4'

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5 1R7 2.25 23' (0

TRS 2.25 23' 00" Outlet No::le Safe lade TRO 2.25 0'

0' TRI 2.25 10 U2*

25*l.

TR2 2.25 10 1/2" 45'I.

33 2.25 to 1/Ja 1%^t na 2.25

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Flange to ShcIl US 2.25 0'

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TR9 2.25 1*

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Flange Ligament TRO 2.25 0*

n' CALIBRATION All search units were calibrated utilizing the information given in -

Ap;endix A in accordance with the requirements of procedure WMF-95044-P-001 Appendix E Part 1.

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CALIBRATIOil IIIQJIRIFUNTS 4

SEAROI UNIT AREA 10 BE INCIDINT RITRACED CAL. BLOCK WATER PA'111 l'tANIIUIATOR EXMlINED ANGIE ANGII IDINil'IY DISTANCE R I TIES OR TION (STEP 6.3)

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(6.3.3)*

(6.3.4).

hTION l'Iole B ible A Vertical O'

IWi-27 11" Ible C 16*l.

BVI-27 11" llote C llole B llole A Vertical

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d Nozzle Inside 23

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BV1-23 12" llole D llole E N/A Vertical Padius 1:lange to 0*

0 IWi-27 10" llole D

P C llole A lbrizontal Vessel Weld I

4L BVI-27 10" llole D llole C llole A Ik)rizontal 3*

11*I, BVI-27 10" Ible D llole C llole A florizontal 1.igaments 0*

O BVI-27 9 1/2" llole A lble B Ilole D Ilorizontal Safe-End Weld

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Figure 2 5"

Ilole A Ilole B lble C Vertical 10 1/2*

45*L Figure 2 5"

llole A Ilole B llole C Vertical i

• See Procedure hMF-95044-P-001, Appenlix E, Part 1, for referenced paragraphs.

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A PRIL. I!, M7j 1l ELD IDENTITY:

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( fel 6b /297 03) ilUMBER OF STEPS / STUD H0LES (49)

VESSEL Rt.DIUS/INDEX 1 (7 7. b9 )

,fl0ZZl.E RADIUS /INDEX II

( 14 d 9 )

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C PLANT SITE: DE AL'ER. V'At LEY l

DATE:

APRJL I 1, l'7 74 WELD IDENTITY:

FL AacF. Lc;Arne>Jrs VELO LOCATION:

blTCH C ICC-L6 MTERIAL THICK!iESS: $'TU D b'oLEC btA = 17l.? 5"

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(152.07 / 22b.5 5 )[ 313.4 5 j.344. 4 6 ')

H0ZZLE CENTERLINE / SCAN LIMITS NUMBER OF STEPS / STUD HOLES

((7 )

VESSEL RADIUS /INDEX 1

( b207 )

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DUQUESNE LIGHT C0!Tr.T BEAVER VALLEY UNIT fl POWER STATION REFUELING O' TAGE CORE I-II J

INSERVICE INSPECTION HIGH ENERGY PROGRAM The main t.eam and feedwater postulated break points in the main steam valve house were examined as required by Accendix D. Section D.3.2 of the BVPS Unit il Final Safety Analysis Report (FSAR). A baseline examination was perfomed on 100 percent of the subject weld during the first refuel-ing outage at BVPS Unit #1 as required by the FSAR. The following is a list of all the welds and the examination performed as part of this program.

PROGRAM COMPONENT &

EXAMI.1ATION REF.

ITEM IWC REF.

AREA & EXTENT OF EXAM PROCEDURE SKETCH VOL SURF VIS DLCf1 70 1.

C2.5 Loop A 32" Mainsteam examin-ed welds A-1, A-2 A-3.A-4 A-5, A-6*,A-7*, A-8*, A-9,? -10*,

A-11*

DLC-#2 70 2.

C2.5 Loop B 32" Mainsteam examined welds B-1.B-2,B-3, B-4,B-5,B-6*,B-7*,B-8*,B-9, B-10*,B-11*

DLC-f3 70 3.

C2.5 Loop C 32" Mainsteam Examined welds C-1.C-2, C-3.C-4,C-5,C-6*,C-7*,

C-8*,C-9, C-10*, C-11

• II)

DLC-f4 4

C2.1 Loop A 32" Mainsteam 205 70 Examined Welds #1 and Weld A II) 5.

C2.1 Loop B 32" Mainsteam 205 70 DLC-f4 Examined Welds #1 &

Weld B III DLC-f4 6.

C2.1 Loop C 32" Mainsteam 205 70 Examined Welds #1 &

Weld C NDEII)

DLW-2-2210 7.

C2.1 Loop A 16" Feedwater 205 1.0 Es mined Weld #2 page 1 of 2 e,

o

SEP 121978 Program Ccmponent Examination Sketch No.

& IWB Reference Area and Extent of Examination Procedure Ref. OLW PRESSURIZER U/T P/T V/T 11 B2.1 Longitudinal Weld #1 Examine 47 8 1-2100 5' from 0" Ref. (Adjacent weld

1. 5) 12 B2.1 Longitudinal Weld 92. Examine 47 8 1-2100 20" to 25" from 0" Ref. (Adja-centweld#5) 8 1-2100 13 82.1 Longitudinal Wald #3. Examine 47 5" from 0" Ref.' (Adjacent weld

1. 6) 8 1-2100 14 B2.1 Circumferential Weld #4. Examine 47 5" C.W. from 0" Ref. (Adjacent Weld #1).

15 B2.1 Circtnferential Weld #5. Examine 47 8 1-2100 5" C.W. from 0" Ref. (Adjacent Weld #1).

8 1-2100 16 B2.1 Circumferential Weld #6. Examine 47 5" C.W. from 0" Ref. (Adjacent Weld #3).

8 1-2100 17 B2.1 Cirewiferential Weld #7. Examine 47 5"C.W.from0"Ref.(Adjacent Weld #3).

18 B2.4 14" Pressurizer Surge Safe-End 205 11 8 1-4500 Weld #9(OH) (See Item 131).

19 B2.4 4" Pressurizer Spray Safa-End 205 11 8 1-4504 Weld #52(DM) (See Item #32).

8 1-2100 20 82.8 Support Skirt Weld #8. Examine 205 9.5" C.W. from 0" Ref (Below and adjacentWeld#1).

8 1-2100 21 B2.11 Pressure Retaining Bolting (Manway) Examine Bolts from Posi-tion 1 thru 5.

STEAM GENERATOR 8 1-3100 Loop #1 Channel head to Tubesheet 47 22 B3.1 Weld #1-1.

Examine 7.5" C.W. from 0" Ref. (Top centerline of hot leg Manway).

page 2 of 21

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T 23 B3.1 Loop #2 channel. head to tube-47 8

1-3100 sheet weld #2-1.

Examined 7.5" C.W. from 0" ref. (top center-line of cold leg manway).

24 B3.1 Loop #3 channel head to tube-47 8

1-3100 sheet weld #3-1. Examined 7.5" C.W. from 0" ref. (top centerline of cold leg manway).

25 B3.3 Nozzle to safe-end welds #4DM 205 11 8

1-4100 ~

and #5DM (see Iten #28).

26 B3.10 Pressure retaining bolting.

8 1-3100 (hot leg manway) Examined bolts frors positions 1 thru 5.

(each gen.)

27 B3.10 Pressure retaining bolting (cold 8

1-3100 leg manway). Examined bolts from positions 17 thru 21.

(eachgen.)

PIPE TO SAFE-END g

28 B4.1 Loop #1 R.C. pipe. Examined 205 11 8

1-4100 welds #1DM, f4DM, #5DM and

1. 16 DM.

29 B4.1 Loop #2 R.C. pipe. Examined 11 8

1-4200 welds #1 DM and #16 DM.

(See item #5).

11 8

1-4300 30 B4.1 Loop #3 R.C. pipe. Examined welds #1DM and #160M. (See Item f6).

31 B4.1 14" Dia. pressurizer surge.

205 11 8

1-4500 Examined weld #90M.

32 B4.1 4" Dia. pressurizer spray.

205 11 8

1-4504 Examined weld 052 DM.

33 B4.5 Loop #1 R.C. pipe. Examined 205 11(2)8 1-4100

~

welds #6 & #7.

11 8

1-4100 33A B4.5 Loop #1 R.C. pipe. Examined welds #17 & #18 (12" of longitudinal seams adjoining weld #7).

34 B4.5 Loop #2 R.C. pipe. Examined 205 11(2)8 1-4200 weld #14.

page 3 of 21 9

y

-.,e-w

Examination Sketch Program IW8-2600

~

item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T ASSOCIATED AUXILIARY PIPING 8

1-4500 35 B4.5 14" Dia. Pressurizer surge.

205 Examined weld f 8.

8 1-4102 36 B4.5 Loop #1 12" Ota. cold leg 205 SIS ~accum. discharge. Ex-amined welds #11,12,13,14, l

15 and 16.

l 8

1-4201 37 B4.5 Loop #210" Dia cold leg 205 aceta. discharge. Examined weld f2.

8 1-4103 -

38 84.5 Loop '#1 8" dia. by-pass.

205 Examined welds f4 & #5.

l 8

1-4104 39 B4.5 Loop #16" dia. cold leg low 205 head SIS. Examined welds #4, 5, 6 & 8.

8 1-4105 40 B4.5 Loop #16" Dia. hot leg low 205 head SIS. Examined welds #15,

1. 16, 17, 18, 19 & 21.

8 1-4501 41 B4.5 6" dia. pressurizer safety.

205

(

Examined welds #4 & 5.

8 1-4502 42 B4.5 6" dia. pressurizer relief..

205 Examined weld #12.

8 1-4503 43 B4,5 Loop #1 4" dia cold leg 205 pressurizer spray. Examined welds #3, 4, 5, & 6*.

8 1-4504 44 B4.5 Loop #3 4" Dia. cold leg 20 5 pressurizer spray. Examined welds #5, 6 & 7.

8 1-4106 45 B4.5 Loop #1 3" dia RTO return.

205 Examined welds #5, 6, 7, 8 9 & 10.

8 1-4502 46 B4.5 3" dia, pressurizer relief.

205 s

Examined welds #25, 26 & 27.

8 1-4104 47 84.5 Loop #1 2" dia. cold leg low 205 head SIS. Examined weld #2 BW.

• See Note 2 page 4 of 21 e

-r.,u<

,,-..r...

7

~

Program IW8-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T 9/T V/T BRANCH CONNECTION EXCEEDING SIX INCHES j

11 II) 8 1-4500 48 B4.6 14" Dia. pressurizer' surge.

Examined weld #1R.

BRANCH CONNECTION SIX INCH DIA.

AND SMALLER

• 49 B4.7 Loop fl 6" dia. cold leg 11 8

1-4104 low head SIS. Examined weld

1. 18R.

11 8

1-4106 50 B4.7 Loop fl 3" Dia. RTD return.

Examined weld #15R.

51 B4.7 Loop #1 2" Dia. letdown.

11 8

1-4110 Examined weld #1R.

11 8

1-4112 52 84.7 Loop #12" Dia. draic line.

Examined weld #21R.

11 8

1-4503 53 B4.7 Loop fl 4" Dia. cold leg pressurizer spray. Exenined weld #1R.

SOCKET WELDS 11 8

1-4104 54 B4.8 Loop #1 2" Dia. cold leg low head SIS. Examined weld #1.

l 55 B4.8 Loop #1 2" Dia. hot leg high 11 8

1-4107 l

head SIS. Examined welds #6, 7 8&9.

11 8

1-4108 56 B4.8 Loop #12" Dia cold leg RTD take-off. Examined welds #15,16,17, 18, 19 & 20.

11 8

1-4109 57 B4.8 Loop #1 2" Dia. Hot leg RTD Take-off. Examined welds #23, l

24, 25, 26, 27, 28 & 29.

11 8

1-4110 58 B4.8 Loop #1 2" Dia letdown. Ex-amined welds #2, 3, 4 & 9.

11 8

1-4111 l

59 B4.8 Loop #1 2" Dia fill line. Ex-amined welds #2, 21, 22, 23, 24, 25 & 26.

11 8

1-4112 l

60 B4.8 Loop fl 2" Dia. drain line. Ex-l amined welds #18,19, 20, 26, 27

& 28.

• Includes 2" Min. Examinati,on on Nozzle page 5 of 21

~

r

,r

.m-

Program IW8-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T 11 8

1-4113 61 B4.8 Loop fl 2" Dia seal injection line. Examined welds #1, 2, 3 4, 5, 6, 7, 8 & 9. ~

~

11 8

1-4603 62 B4.8 Loop #1 2" dia, pressure ecual-ization. Examined welds #2, 3, and 4 11 8

1-4505 63 B4.8 2" Dia. auxiliary spray. Ex-amined welds #6,13,14.15,16

~

and 17.

11 8

1-4602 64 84.8 2" Dia. drain header. Examined weld f7.

11 8

1-4506 65 B4.8 1 l/2" Dia. pressurizer spray line drain. Examined weld #24.

11 8

1-4210 66 B4.8 Loop #2 2" Dia. fill line.

Examined weld #22.

11 8

1-4212 67 B4.8 Loop #2 2" Dia. seal injection.

Examined welds #9 and 44.

11 8

1-4603 68 B4.8 Loop #2 2" Dia. pressure equalization. Examined weld

1. 28.

11 8

1-4311 69 B4.8 Loop #31 1/2" dia. seal in-jection. Examined weld #50.

f INTEGRALLY WELDED SUPPORTS i

70 B4.9 Loop fl 14" dia. hot leg RHR 205 11(2)8 1-4101 take-off. Examined attachment WS-2.

71 B4.9 Loop fl 12" dia. cold leg 205 11(2)8 1-4102 accum. discharge. Examined attachments WS-2 and WS-3.

l l

72 B4.9 Loop fl 8" Dia. by-pass.

205 11(2)8 1-4103 l

Examined attac.6snent WS-1.

73 B4.9 Loop #16" & 2" cold leg low 205 11(2)8 1-4104 head SIS. Examined attachment WS-1.

74 B4.9 Loop fl 3" Dia. RTD return.

205 11(2)8 1-4106 f

Examined attachment WS-2.

~

75 B4.9 Loop #1 2" dia. letdown.

205 11(2I8 1-4110 Examined attachment WS-1.

page 6 of 21 l

Program IWB-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V 11(2)/T 76 B4.9 Loop #1 2" Dia fill line.

205 8

1-4111 Examined Attachment WS-2.

77 B4.9 Loop #1 2" Dia. drain line.

205 11(2)8 1-4112 Examined Attachment WS-4.

78 B4.9 Loop #1 2" & 1 1/2" Dia. seal 205 11(2)8 1-4113 injection. Examined attach-ment'J5-1.

79 B4.9 Loop #1 4" Dia. cold leg 505 11(2)8 1-4503 pressurizer spray. Examined WS-1, WS-2, WS-3, WS-4 and WS-5.?

SUPPORTS AND HANGERS (REPORT ALL CAT. B4.10 ITEMS TO SKETCH 1-4800) 80 84.10 Loop fl 14." Dia. hotleg RHR 8

1-4101 take-off. Examined A.

81 B4.10 Loop fl 12" dia. cold leg 8

1-4102 accum. discharge. Examined A

B, C, & D.

82 B4.10 Loop #1 8" Dia, by-pass.

8 1-4103

~

Examined A.

83 B4.10 Loop #16" & 2" Dia. cold leg 8

1-4104 l

low head SIS. -Examined A, B, C & D.

L 84 B4.10 Loop #16" Dia. hot leg low 8 '

1-4105 head SIS examined A thru F.

H, I & K.

8,5 B4.10 Loop #1 2" Dia. hot leg hign 8

1-4107 SIS. Examined A & B.

t 86 B4.10 Loop #1 2" Dia. fill line.

8 1-4111 l

Examined A, B, C & E.

87 B4.10 Loop fl 2" & 1 1/2" Dia.

8 1-4113 seal injection. Examined A thru P.

88 B4.10 14" Dia pressurizer surge.

8 1-4500 Examined A thru G.

89 B4.10 6" & 3" dia, pressurizer.

8 1-4502 i

relief. ' Examined D & E.

l

• WS-5 = PT Only page 7 of 21

-.y

Program IW8-2600 Examination Sketch Item Reference Ares and Extent of Examination Procedure' Reference PRESSURE RETAINING BOLTING (Report all Cat. 84.12 Items to Sketch 1-4700) 8

,1-4106 90 B4.12 Loop #1 3" Dia. RTD Return.

Examined Flange #1.

8 1-4108 91 B4.12 Loop #1 2" & 1 1/2" Dia.

cold leg RTD take-off.

Examined Flange #1.

8 1-4109 92 B4.12 Loop #1 2" Dia. hot leg RTD Te ke-off. Examined Flange fl.

8 1-4113 93 B4.12 Loop f1 2" & 1 1/2" Dia.

~

Seal Injection. Examined Flange #1.

8 1-4603 94 84.12 Loop #1 2" Dia. Pressure Equalization. Examined Flange #1.

8 1-4501 95 B4.12 6".Dia. Pressurizer Safety Yalve 551A. Examined Flange fl.

REACTOR COOLANT PUMP (LOOP #1) 96 B5.1 Main flange bolting. Examined 15 (3) 1-5100 bol ts 1-1 thru l-24.

97 B5.2 Seal housing bolting. Bolts (4) (4) 1-5100 1-1 thru 1-24*.

8 1-5100 98 85.3 Main flange bolting. Examined bolts 1-1 thru 1-24.

8 1-5100 99 B5.3 Seal housing bolting. Examined bolts 1-1 thru 1-12.

100 B5.5 Support components. Ex$nined 8

1-5100 supports 1-1SC,1-2SC and 1-3SC.

101 N/A Flywheels. Examined pumps #1, 41 11 8

1-5100

1. 2 and #3.

0 1-4103 102 B6.5 Loop #1 8" Dia. By-pass.

Examined A.

• Not Examined a

page 8 of 21

e Program I'48-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/Y VALVE BONNET BOLTING (Report All Cat. B6 9 Items to Sketch 1-6300) 8 l-4101 103 B6.9 Loop #1 14" RH-700. Examined 16 bolts.

8 1-4101 104 B6.9 Loop #1 14" RH-701. Examined 16 bol ts.

8 1-4102 105 B6.9 Loop #1 12" SI-48. Examined 16 bolts.

8 1-4102

,106 B6.9 Loop fl 12" SI-51. Examined

~

16 bolts.

8 1-4103 107 B6.9 Loop #1 8" 585. Examined 4 bol ts.

8 1-4104 108 B6.9 Loop #1 6" SI-12. Examined 12 bolts.

8 1-4104

~

Loop #1 6" SI-23. Examined 109 B6.9 12 bolts.

8 1-4105 110 B6.9 Loop 11 6" SI-15. Examined 12 bolts.

111 B6.9 L'oop #1 6" SI-20. Examined -

8 1-4105 12 bolts.

8 1-4501

~112 B6.9 Pressurizer 6" RC-551A.

Examined 8 bolts.

8 1-4503 113 B6.9 Loop #1 4" 455A. Examined 8 bol ts.

114 B6.9 Loop #1 3" RC-23. Examined 8

1-4106 l

12 bolts.

l 115 B6.9 Pressurizer 3" 535. Examined 8

1-4502 l

12 bol ts, i

8 1-4502 116 B6.9 Pressurizer 3" 537. Examined 12 bolts.

8 1-6100 l.

116A B6.1 Loop #1 loop stop valve bolt-15 ing RC-590 and 591. Examin:4 24 bolts each.

page 9 of 21 D

4 e

v

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e

Program IWC -2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T STEAM GENERATOR 117 C1.1 Loop #1 Stub barrel 'o upper 47 8

2-1100 t

tubesheet weld #1-2.

Examined 7.2" C.W. from 0" ref. (vertical centerline of feedwater nozzle) 8 2-1100 118 C1.1 Loop #1 Lower shell to stub 47 barrel weld #1-3.

Examined 7.1" C.W. from 0" Ref.

(vertical centerline of feed-water nozzle).

8 2-1100 119 C1.1 Loop #2 transition cone to lower 47 shell weld #2-5. Examined 7.1" C.W. from 0" ref. (vertical centerline of feedwater, nozzle) 8 2-1100 120 C1.1 Loop #2 Upper shell to transition 47 cone weld #2-6.

Examined 9.2" C.W. from 0" Ref. (vertical centerline of feedwater nozzle).

, 121 C1.1 Loop #3 Upper head to shell 8

2-1100

/

weld #3-8.

Examined 9.2" 47 C.W. from 0" Ref. (vertical centerline of feedwater nozzle).

122 C1.2 Loop #1 feedwater inlet 47 8

2-1100 nozzle to shell weld #1-9.

Examined 100%.

f 123 C1.2 Loop #1 steam outlet nozzle 47 8

2-1100 I

to head weld #1-10. Examined 100%.

2-1100 124 C1.4 Loop #1 pressure retaining 15 bolting (secondary manway).

Examined 1-B1,1-82,1-821 and 1-B22.

8 2-1100 125 C1.4 Loop #1 Pressure retaining bolting (secondary manway) examined 1-B1 thru l-B13.

I EXCESS LETOOWN HEAT EXCHANGER 8

2-1110 126 C1.1 Head to flange weld #1. Ex-205 amined.50" C.W. from 0" ref.

(vertical centerline of inlet nozzle).

page 10 of 21

~

-=-v--

,y...

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,_,y y,

Program IWC -2500 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T 8

2-1110 127 C1.1 Shell to flange weld #2. Examine 205

.50" C.W. from 0" ref. (vertical centerline of inlet nozzle).*

12s C1.4 Pressure retaining bolting (tube-8 2-1110 sheet flange). Examined B1 thru B4.

1 29 C1.4 Pressure retaining bolting (tube-15 2-1110 sheet flange). Examined B1 & B2.

RESIDUAL HEAT EXCHANGER 8

2-1120 T30 C1.1 Head to shell weld 1-1.

Examined 205 20" from 0" ref. (vertical center-line of RH-E-1A inlet nozzle).

8 2-1120 131 C1.1 Shell to tuberh..et weld #2-2.

205 Examined 2.0" from 0" ref.

(vertical centerline of RH-E-1B inlet nozzle).

11 8

2-1120 132 C1.3 Integrally welded supports.

Examined 1-1WS.

8 2-1120 133 C1.4 Pressure retaining bolting (tubesheet flange). Examined 1-B1 thru 1B16.

2-1120 134 C1.4 Pressure retaining bolting 15 (tubesheet flange

).

Examined 1-B1 thru l-B5.

SEAL WATER HEAT EXCHANGER 145 C1.1 Head to shell weld #1. Ex-11(5)8 2-1130 amined.75" fru 0" ref.

(vertical centerline of in-let nozzle).

136 C1.1 Shell to flange weld #2. Ex-11(5)8 2-1130 amined.75" from 0" ref.

(vertical centerline of inlet nozzle).

11 8

2-1130

~

137 C1.3 Integrally welded support.

Examine 1 WS.

• Not Examined - weld does not exist.

page 11 of 21 s

Program IWC-2600 Examination Sketch Item Reference Area and Extent of Examination Procedure Reference U/T P/T V/T NON REGENERATIVE HEAT EXCHANGER 138 C1.1 Head to shell. weld (1. Examined 205 8

2-1140 1.25" f rom 0" ref. (vertical centerline of inlet nozzle).

8 2-1140 139 C1.'

Shell to flange weld #2. Ex-205 amined 1.25" from 0" ref.

(vertical centerline of inlet nozzle).

11 8

2-1140 140 C1.3 Integrally welded support.

Examine 1WS.

'141 C1.4 Pressure retaining bolting (tube-8 2-1140 sheet flange). Examined B1 thru B-12.

142 C1.4 Pressure retaining bolting (tube-15 2-1140 sheetflange). Examined B1 thru B4.

l REGENERATIVE HEAT EXCHANGER 8

2-1150 143 C1.1 Head to shell weld fl. Examined 205 3.0" from 0" ref. (vertical centerline of each shell pass).

8 2-1150 144 C1.1 Shell to tubesheet weld #7.

205 Examined 3.0" from 0" ref.

l (vertical centerline of each shell pass).

VOLUME CONTROL TANK 8

2-1200 145 C1.1 Lower head to shell weld #1.

205 Examir.ed 4.5" from 0" ref.

(vertical centerline of i

l manway).

8 2-1200 146 C1.1 Upper head to shell weld #2. Ex-205 amined 4.5" from 0" ref.

I (vertical centerline of man-way).

11 8

2-1200 147 C1.3 Integrally welded suoport.

Examined 1WS.2WS, 3WS, 4WS l

page 12 of 21 i

l

Program IWC-2600 Examination Sketch Item Reference Area and Ertent of Examination Procedure Reference U/T P/T V/I 8

2-1200 148 C1.4 Pressure retaining bolting

'manway). Examined B1 thru 25.

149 C1.4 Pressure retaining bolting 15 2-1200 (manway). Examined B1 & B2.

SEAL WATER INJECTION FILTER 8

2-1300 150 C1.1 Head to shell weld #1-1. Examined 205

.56" from 0" ref. (vertical center-line of CH-FL-4A inlet nozzle).

8

-21300 151 C1.1 Shell to flange weld #2-2. Ex-205 amined.56" from 0" ref. (vertical centerline of CH-FL-48 inlet nozzle).

152 C1.3 integrally welded supports.

11 8

2-1300 Examined 1WS.

153 C1.4 Pressure retaining bolting.

8 2-1300 Examined 1-B1 thru l-BS.

154 C1.4 Pressure retaining bolting.

15 2-1300 Examined 1-B1 and 1-82.

REACTOR COOLANT FILTER 155 C1.1 Head to shell weld fl. Ex-11(2)8(5) 2-1310 amined.56" from 0" ref.

(vertical centerline of outlet nozzle).

156 01.1 Cover weldment to shell weld #2.

11(5)g(5) 2-1310 Examined.56" from 0" ref.

(vertical centerifne of outlet nozzle).

11 8

2-1310 157 C1.3 Integrally welded supports.

Examined 1WS.

SEAL WATER RETURN FILTER I63(5) 11 158 C1.1 Head to shell weld !1. Ex-8 2-1320 amined.85" from 0" ref.

(vertical centerline of outlet nozzle),

page 13 of 21

PROGRAM IWC-2500 EXAMINATION SXETCH ITEM REF.

AREA AND EXTENT OF EXAMINATION PROCEDURES REF.

159 C1.1 Cover weld ment to shell weld #2.

11(5) V/(T5)

U/T P/T 8

2-1320 Examined.85" from 0" ref.

(vertical centerline of outlet nozzle).

11 8

2-1320 160 C1.3 Integrally welded supports.

Examined 1WS.

i PIPING 8

2-2110 161 C2.1 Loop #1 32" main steam. Examined 205 weld #9.

8 2-2210 162 C2.1 Loop #1 16" feedwater. Examined 205 weld.4.

163 C2.1 14" RHR. Examined welds #1 & 26.

205' 8

2-2310 8

2-2310 164 C2.1 12" RHR. Examined welds #49, 205 51, 57, 58 & 59.

8 2-2310 165 C2.1 10" RHR. Examined welds #21 205 and 46.

8 2-2312 166 C2.1 10" RHR. Examined weld #10.

205 f

11(I) 8 2-2310 167 C2.1 8" RHR.' Examined weld #17.

11(I) 8 2-2410 168 C2.1 8" CVCS. Examined welds #55 and and 74.

III 8

2-2410 11 169 C2.1 6" CVCS. Examined welds #2, 78 and 82.

8 2-2411 170 C2.1 6" CVCS. Examined weld #26.

205 8

2-2111 171 C2.1 6" RHR. Examined weld-#6.

205 8

2-2111 172 C2.1 6" Main steam. Examined weld 205

1. 18.

LONGITUDINAL WELOS 8

2-2110 173 C2.2 Loop #1 32" main steam. Examine 205 weld #8LS.

PRESSURE RETAINING BOLTING 8

2-2610 174 C2.4 Examined Items #1, 2 & 3.

15 page 14 of 21 O

PROGRAM IWC-2600 EXAMINATION SKETCH ITEM REF.

AREA AND EXTENT OF EXAMINATION PROCEDURES REF.

U/T P/T V/T INTEGRALLY WELDED SUPPORTS

\\'

175 C2.5 Loop #1 16" feedwater. Examined 70 8

2-2210 WS-1.

176 C2.5 Loop #3 32" main steam. Examined 70 8

2-2130 WS-1 and WS-2.

177 C2.5 14" RHR. Examined WS-1, WS-2, 11 8

2-2310 WS-3, WS-7 & WS-8.

178 C2.5 10" RHR. Examined WS-14.

11 8

2-2310 179 C2.5 8" CVCS. Examined WS-4.

11 8

2-2410 180 C2.5 6" CVCS. Examined WS-1.

11 8

2-2410 181 C2.5 6" CVCS. Er.amined WS-2 & WS-3.

11 8

2-2411 182 C2.5 6" CVCS. Examined WS-1.

11 8

2-2413 SUPPORT COMPONENTS 183 C2.6 Loop #1 32" main steam. Examined 8

2-2110 A. WS-1 & WS-2.

184 C2.6 Loop #1 16" feedwater. Examined 8

2-2210 A. WS-1 and WS-2.

8 2-2310 185 C2.6 14" RHR. Examined WS-1, WS-2, WS-3, WS-7, WS-8 & C.

8 2-2312 186 C2.6 10" RHR. Examined C & D.

187 C2.6 12" RHR. Examined WS-10. WS-12 8

2-2310 and D.

188 C2.6 6" CVCS. Examined WS-1.

8 2-2410 189 C2.6 6" CVCS. Examined A thru I & K.

8 2-2411 190 C2.6 8" CVCS. Examine F.* G 8

2-2410 VALVES 191 C4.2 Pressure retaining bolting.

15 8

2-2410 Examined the following:

NRV-MS101A SV-MS101B B

102B

/

C 1038 TV-MS101A 1048 8

105B C

Sy.MS101C

• No Examination - F doesn't exist.

page 15 of 21 4

g 4

--s---

a v

r w

w

+

w

J PROGRAM IWC-2600 EXAMINATION SKETCH ITEM REF.

AREA AND EXTENT OF EXAMINATICN PROCEDURES REF.

+

U/T P/T V/T 191 (continued)

PCV-MS101 SV-MS-C 104C SV-MS I f

103A 156B 104A 156C 105A 192 B4.10 Examine Items 94, 8

1 - 4800 98 & 99

~

~

i I

Page 16 of 21

Program Item #193 Pressure piping attachment weldments resulting from Design Change Packages O

(DCP's) 253, 257 and 305 (baseplate and hanger modifications) were visually inspected for leakage and surface examined (M.T. or P.T.), to fulfill the preservice requirements of Section XI of the ASME Code. The attached table is a compilation of the effected hangers, their drawing location and the type of examination perfomed. The results of the examinations are compiled under Tab E of this report.

The visual examination was perfomed in accordance with Pmcedure Number IP-W-02. The magnetic particle and liquid penetrant examinations were perfomed in accordance with procedures MT-969-1 and PT-969-1, Rev. 2 respectively.

Additions and modifications that resulted from DCP's 253, 257 and 305 do not affect the BVPS Unit #1 ten-year program.

This data serves as baseline data for the newly added pressure piping attachment weldments made on the already existing support components listed in the table below.

Hanger No.

NDE Hanger No.

Line No.

150 No.

on ISO Method CC-A-264 6"CC-262-151 DLW-3-4332 H-264 MT/VT CC-SH-64A 18"CC-104-151 DLW-3-4323 H-64A MT/VT CC-SH-65A 18"CC-3-151 DLW-3-4323 H-65A MT/VT H-42A 3"RC-106-1502 DLW-1-4502 D

PT/VT DLW-1-4800, item #228 RC-R-2 4"RC-72-1502 DLW-1-4504 WS-6 PT/VT DLW-1-4800, item #260 WR-SH-23 24"WR-19-151 DLW-3-4206 H-23 PT/VT SI-R-8 12"SI-121 DLW-1-4102 WS-4A PT/VT

~

DLW-1-4800, item #10 CC-SH-59A 18"CC-105-151 DLW-3-4315 H-59A MT/VT H-86 6"WR-55-151 DLW-304209 H-86 PT/VT H-73 6"WR-55-151 DLW-3-4209 H-73 PT/VT CH-PS-3 2"CH-23-1502 DLW-1-4505 WS-2 PT/VT DLW-1-4800, item #273 H-305 6"SI-73-1502 DLW-2-2507 Not shown PT/VT on ISO p

SI-A- 312 6"SI-72-1502 DLW-2-2506 Not shown PT/VT on 150 pan '. ' o f 21

---

.--a=

g,,

Program Item '.o.194

(

j Design Change Packages (DCP's) 162 and 189 resulted in the installation of V

new safety injection and recirculation spray lines which follow under the Class 2 requirements of Section XI of the ASME Code. The newly installed line welds were examined by ultrasonic methods to fulfill the baseline preservice requirements of Section XI.

Westinghouse inspection procedure ISI-205, Rev. 2 was used to perform the ultrasonic examinations. In addition two welds whose thickness was less than the 0.250 inches required by ISI-205 were examined by radiographic procedure RT-2.

Program IWC-2600 Procedures Sketch No.

Ref.

Area and Extent of Examination U/T Surf V/T Ref.*

PIPING CI-18908 1.

C2.1 10" SIS. Examined welds 1, A,19, 205 K

2, 3, L, 4, 5, 6, M, 29, 30, N, and 8.

CI-18908 2.

C2.1 6" SIS. Examined welds 9, P, Q, 205 R,10, T,11, U, and 12.

CI-16201 3.

C2.1 6" Recire. Spray System. Examined 205 welds 8, 33, 43, 31, 36, 4, 2,

/

28, 27, 39, 35, 38, 41, 42, 34,

'h 14,19, 40 and 37.

4.

C2.1 6" Recirc. Spray System. Examined 205 CI-16202 welds 18,12, 6, 7, 9,1, 3, 30, 29, 23, 25,13, 20,16 and 21.

CI-18910 5.

C2.1 10" SIS. Examined welds 1, A,18,

.205 K, L, 4, 5, 6, 30, 31, N, 8, 9, P, 36, 37, 38, S, T, U, V, and 34.

SUPPORT COMPONENTS (8) CI-16201 6.

C2.6 Examined PSSP009, PSSP010, PSP.011 PSSH014, PSdOQ8, and PSSH-012 (8) CI-16202 l

7.

C2.6 Examined PSSH001, PSSP002, PSSP003, PSSH004, PSR005, PSR-006, PSR007 and PSR008.

IP-W

-01 CI-18908 8.

C2.6 Examined PSR368, PSR60A, PSR608, PSSH60F, and PSR60E i

IP-W

-01 CI-18910 9.

C2.6 Examined PSR33B, PSSH67, PSR67F, PSR67E, PSSH67A, and PSR67B U

Page 18 of 21 Er v

1

Program Item No.194 (Continued)

Program IWC-2600 Procedures Sketch No.

Ref.

Area and Extent of Examination U/T Surf V/T Ref.*

INTEGRALLY WELDED SUPPORTS

• CI-18908 10.

C2.6 Examined PSSP36A, PSSH060, PSSH60C, and PSSP600

• CI-18910 11.

C2.6 Examined PSSP33A, PSSH670, and PSSP67C CI-18908 PT-12.

C2.5 Examined PSSP36A, PSSH060, and PSSP60D 969-1 CI-18910 PT-13.

C2.5 Examined PSSP33A, PSSH67D, and PSSP67C 969-1 s

l l

l l

l l

l

• Procedure IP-W-01 and. IP-W-02 Page 19 of 21 O

9%

CLASS - 3 PROGRAM ITEM NO. 195 A system leakage test was perfanned on Class 1, 2, and 3 components as required by Section XI of the ASME Boiler and Pressure Vessel Code through the summer 1975 Addenda, and the Plant Technical Specifications, to the extent practical and with the access provided and the limitations of component geometry. The following is a list of examinations as outlined by Class, System and, appropriate S & W flow diagram.

Class I ll700-RM-155A-6 Reactor Coolant System ll700-RM-155B-6 Reactor Coolant System ll700-RM-159A-6 Chemical and Volume Control System 11700-RM-169A-6 Vent and Drain System 11700-RM-167P-4 Safety Injection System Class 2 11700-RM-120A-5 Main Steam System

(

ll700-RM-124A-6 Feedwater System l

ll 700-RM-137A-5 Misc. Drains - Secondary Plant 11700-RM-179A-6 Sample System 11700-RM-179B-6 Sample System ll700-RM-169A-6 Vent and Drain System 11700-RM-165A-6 Contairrs;it Depressurization System ll700-RM-155A-6 Reactor Coolant System 11700-RM-155B-6 Reactor Coolt ' System ll700-RM-156A-6 Residual Heat emoval System 11700-RM-159A-6 Chemical and Volume Control System ll700-RM-1598-7 Chemical and Volume Control System I

ll700-RM-167A-4 Safety Injection System 11700-RM-167P-4 Safety Injectior. System Class 3 ll700-RM-120A-5 Auxiliary Sten System 11700-RM-124A-6 Auxiliary Feedt ater System ll700-RM-124A-7 River Water System ll700-RM-1278-6 River Water System ll700-RM-157A-6 Component Cooling Water System ll700-RM-1578-5 Component Cooling Water System ll700-RM-157C 5 Component Cooling Water System i

11700-RM-157D-6 Component Cooling Water System l

11700-RM-162A-4 Spent Fuel Pit Cooling System l

11700-RM-165A-6 RWST Cooling System ll 700-RM-159A-6 CVCS Boric Acid Supply ll700-RM-1598-7 Boric Acid Transfer System 11700-RM-167A-4 SIS Boron Injection Surge Tank l

Visual examination for evidence of leakage was conducted in accordance with Procedure ISI-LT-101 dated March 25, 1980.

~

page 20 of 21 r

~

CLASS - 3 PROGRAM ITEM NO. 196 Visual examination of 100 percent of the Class 3 component supports and piping supports and hangers on piping greater than 4 inch diameter in accordance with Procedure ISI-8. The following is a list of examinations as outlined by system fV) and appropriate Westinghouse sketch number, and S&W flow diagram.

Wes tinghouse DLW-3-4100 thru 3-4103 Auxiliary Feedwater DLW-3-4201 thru 3-4215 Rivar Water System DLW-3-4300 thru 3-4333 Component Cooling Water DLW-3-4334 thru 3-4337 Spent Fuel Pool Cooling System I

Reference Drawinos l

Stone & Webster ll700-RM-120A-5 Auxiliary Steam System 11700-RM-124A-6 Auxiliary Feedvater System ll700-RM-124A-7 River Water System ll700-RM-127B-6 River Water System ll700-RM-157A-6 Component Cooling Water System 11700-RM-1578-5 Component Cooling Water System ll700-RM-157C-5 Component Cooling Water System ll700-RM-1570-6 Component Cooling Water System ll700-RM-162A-4 Spent Fuel Pit Cooling System ll700-RM-165A-6 RWST Cooling System 11700-RM-159A-6 CVCS Boric Acid Supply ll700-RM-159B-7 Boric Acid Transfer System ll700-RM-167A-4 SIS Boron Injection Surge Tank NOTES (1) Surface examination performed as a substitute to volumetric.

(2) Surface examination performed as a substitute to volumetric.

(3) Surface examination performed if bolting d'is-assembled.

(4) Volumetric and surface examination performed if bolting dis-assembled.

(5) Visual and surface performed as a substitute for volumetric.

(6) Manual U/T and P/T performed as a supplement to the remote exanination per Plant Technical Specification (Table 4.4-1).

(7) Due to high personnel exposure, examinations will be scheduled to coincide with normal filter changes.

(8) Visual inspections completed in accordance with Items 1, 3 and 6 on Rigid Support Inspection Attribute Sheets for Program Item Number #194 (6) and #194 (7).

1 v

Page 21 of 21

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DUQUESNE LIGHT COMPAW BEAVER VALLEY UNIT 1 POWER STATION REFUELING OUTAGE CORE I-II INSERVICE INSPECTION AUGMENTED ISI / AMENDMENT 22

\\_

Program IWC-2600 Procedures Sketch NO.

REF.

Area and Extent of Examinatien U/T Surf V/T REF'.

PIPING 2-2F31 1

2.1 Hot Leg Low Head S.I.S. Weld 7.

205 2-2504 2

2.1 Hot Leg S.I.S. Weld 1 205 2-2505 3

2.1 Cold Leg Low Head S. I. S. Weld 3 205 2-2509 4

2.1 Accumulator Discharge Weld 6.

205 2-2510 5

2.1 Accumulator Discharge Weld 7.

20 5 ACCUMULATOR TANKS 2-1210 6

1.1 Top Head to Shell Weld 1-1.

205 From 0" thru 7.5".

2-1210 7

1.2 Nozzle to Vessel Weld 2-3.

205 2-1210 11 8

1.3 Integrally WELDED Support 3-4.

From 0" thru 13".

BORON INJECTION TANK 241220 9

1.1 Head y Shell Welds 1 and 2.

225 10 1.2 ho$51k to hesfel Weld 3 205 2-1220 2-1220 11 11' 1.3 Integrally W-~ td Support S4 8

2-1220 12 1.4 Bolting B1 ta 316.

15 2-2511 l

13 1.2 Nozzle to Safe-End Weld 4 205 PIPING U#

1T 8

2-2512 14 2.1 Recirculation Spray Welds 5, 25 and 26.

11(0 8 2-2513 15 2.1 Recirculation Spray Welds 7,19 and 20.

.a page 1 of 2 e

y

AUGMENTED ISI / AMENDMENT 22 s

Program IWC-2600 Procedures Sketch REF.

Area and Extent of Examination U/T Surf V/T REF.

's.

NO.

PIPING CD 16 2.1 Recirculation Spray Welds 3 11 8

2-2514 u d 21.

U 11 8

2-2515 17 2.1 Recirculation Spray Welds 4 and 19.

NOTE (1) tri Not Feasible - Substitute PT/and VT.

EXPANDED PROGRAM Pmcedures Sketch Program IWC Area and Extent of Examination UT SURF VT REF.

NO.

REF.

PIPING v

1 B4.1 Loot #2 R.C. Pipe Examired 11 8

1-4200 Weld #4DM page 2 of 2

l DUQUESNE LIGHT COMPANY BEAVER VALLEY UNIT #1 POWER STATION REFUELING OUTAGE CORE I-II INSERVICE INSPECTION All f tems listed below were examined as indicated in accordance with the requirements of the Plant Technical Specification Section 4.4-4 and to the requirements of the 1974 Edition of Section XI of the ASME Boiler and Pressure Vessel Code through the Sumer 1975 Addenda to the extent practical with the access provided and the limitations of canponent geometry.

PROGRAM COMPONENT &

EXAMINATION REF.

ITEM IWB. REF.

AREA & EXTENT OF EXAM PROCEDURE SKETCH REACTOR VESSEL U/T P/T V/T 88 1-1200 1

B1.15 Reactor vessel internals.

( ef. this program, Appendix 8

1-1300 2

Bl.2 Closure head peel segments 47 meridional welds, il thru #4 from 0" to 1.3".

0" adjacent weld #5.

\\

8 1-1300 3

Bl.3 Closure head to flange weld #5.

47 Examined C.W. from centerline of stud hole #38 to centerline of stud hole #58.

4 Bl.6 Primary inlet nozzle to safe-205(6)jj(6)8 1-41 00 end weld 16 DM. Examined from 1-4200 the 0.D.

1-4300 11 IO}8 1-4100 5

Bl.6 Primary outlet nozzle to safe-end weld 1 DM.

1-4200.

6 Bl.6 Primary outlet nozzle to safe-11(6)8 1-4300 end weld 1DM.

I 7

Bl.8 Closure studs & nuts. #1 thru 15 70 8

1-1400 thru #19.

8 1-1400 8

Gl.10 Closure head washers #1 thru

1. 19.

8 1-1300 9

Bl.11 Conoseal bolting. Examined assemblies at locations #47 and f53.

1-1300 10 Bl.13 Closure head cladding. Examined 47 clad patches CP-1 & CP-2, each i' x 6" Sq.

page 1 of 21 e-

,yr

-s-,,y.-.a y

--e wm---

HIGH ENERGY PROGRAM

's PROGRAM COMP 0NENT &

EXAMINATION REF.

ITEM IWC REF AREA & EXTENT OF EXAM PROCEDURE SKETCH VOL SURF VIS NDE II)

S.

Loop B 16" Feedwater Exam-205 1.0 DLW 2-2220 ined Weld #2 NDE(j) 1.0 01W 2-2230 9.

Loop C 16" Feedwater Exam-205 ined Weld #2

• Welds which are not made onto pressure retaining piping and which will not be incorporated into the 10 year inspection program.

Note:

(1) Surface Exam completed after weld surface prepared for U.T. Exam.

l l

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DUQUESNE LIGilT COMPANY BEAVER VALLEY UNIT fl Examiner (s):

REACTOR VESSEL INTERNALS INSPECTION PROGRAM Appendix A Date(s):

5U8 ASSEHol.Y:

fyf4 A

l TAPE REF.

l COMPONENT LOCATION LOCATION REMARKS

. Rf NRI COMPLETED' I

l g

j 6.

Support Columns with Cutouts Core Locns.

(w:thmix.tr)

C-12 l

i D-3 i

I I

H-3 N-4 l

l I.

t.

l 7.

Support Columns with Cutouts Core Locns.

(without mixer)

C-4 I

D-13 I

H-13 H-12 I

j l

8.

Upper Core Plate Fuel Assembly-Vessel Locns.

4 Guide Pins A W Peripheral j

l Pins from 0*

to 270*

1 l

i SUB ASSEMBLY: LOUER INTERNALS t

l l

l 9.

Head and 'lessel Alignment Vessel Locns.

l Pin Mating Surfaces and 0*

i Attaciunents.

90*

130*

270*

10. Core Barrel Flange Vessel Locns.

Flow Hozzle Welds From 90* to 180*

11. Flange 'to Core Barrel Weld yessel1.ocns.

From 180* to I

0*

f D

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Procedures DUQUENSE LIGHE COMPANY DEAVER VALLEY UNIT #1 Examiner (s):

REACTOR VESSEL INTERNALS INSPECTION PROGRAN

?

Appendix A i

Date(s):

1 508 ASSFHALY:

INITIAL A5 EXAH IS TAPE REF.

COMPONENT LOCAT10ll LOCATION REMARKS Rf NRI C0HPLETED 4

4 l

17. Lower Core Plate Instrument

_ Core Locns.

Guide Tube Hut and Assembly 0-8 4

Guide Pins around Locations l

18. Lower Core Plate Access Core Locns, 7 17 Cover Bolting l

19. Thermal Shield Flexure Vessel Locns.

Attactments to Core Barrel 90*

270*

20. Reactor Vessel Clad Patches Vessel locns.

65*

165*

21. Outside baffle corner joints Core Locnh B-6 P-S B-10 P-10 C-12 N-12 C-4 N-4 D-3 H-3 i

D-13 H-13 E-2 L-2 l

E-14 L-14 I

G-1 J-1 l

G-15 J-15 l

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