ML20069F813

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Inservice Insp Rept on ASME Class 1,2 & 3 Components & Piping Conducted Jan-June 1982
ML20069F813
Person / Time
Site: Beaver Valley
Issue date: 09/13/1982
From: Lacey W
DUQUESNE LIGHT CO.
To:
Shared Package
ML20069F806 List:
References
NUDOCS 8209280246
Download: ML20069F813 (24)
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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 15077-0004 (Name and Address of Plant)
3. Plant Unit 1-856 MW 4. owner Certificate of Authorization (if required) 26-05000 *
5. Commercial Service Date 09/ 30/ 76' '6. Nadonal Board Number for Unic N/A
7. Components Inspected .

Manufaerurer Component or Manufa<turer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Reactor Vessel Combustion Engineering 69103' B-105642 21011 Pressurizer Westinghouse 1311 PA434676 68-50 Westinghouse Loop 1 1301 ~ 434597 68-45 Loop 2 1302 434598 68-46 Loop 3 1303 . 434599 . 68-47 Reactpr Conlant Pim s Westinchouse "

Loop'l .

l-618J931G01 N/A N/A

Loop 2 2-618J931G01 N/A N/A ,

I Loop 3 3-618J931G01 N/A N/A Reactor tw 1 ,, , v4 4 7 ,, n Loop 1, 2, & 3 S.W. Fabricating N/A N/A N/A Associated Auxiliary _

Piping Systems Schneider Poser Corfi. N/A N/A N/A Einess Letdown Atlas Manufacturing 1308 N/A 1127 Heat Exchaneer Boron Struthers Wells Corp. N/A 434783 13347

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1 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 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

  • Designates account number of arrangement with Authcrized Inspection Agency
to provide inspection services.

This form (E00C29) may be obtained from the Order Dept., ASME,345 E. 47th St., New York, N.Y. 10017 0209280246 820914 PDR ADOCK 05000334 O PDR ,

FORM NISol OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner nn em e nn e TMght Company. 435 Sixth Avenue. Pittsburgh, PA 15219 (Name and Address of Owner)
2. Plant Beaver Vallev Power Station. P.O. Box 4. Shippingport, PA 15077-0004 -

(Name and Address of Plant)

3. Plant Unit 1-856 MW 4. Owner Certificate of Authorization (if required) 26-05000 *
5. Commercial Service Date 09/30/ 7'6 6. National Board Number for Unit N/A
7. Components Inspected Manufacturer Componerit or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

Residual Heat

n. ,. s, _ ,. , ,. e Joseph Oat & Sons 1832-1 434682 368 1832 2- 434683 369 ,

Seal Water Heat Exchanner Atlas 1233 434717 1056

,lionregenerative Heat Exchancer Joseph Oat & Son s - 1830-1 434718 361 Regenerative Heat Exchanger Joseph Oat & Sons 1831-10 Shell 1 434686 ,438 s

2rf I""*

Joseph Oat & Sons 1879-1 7,g 434716 457 Seal Water .

Tnj. Fil t ers Commercial Filters 538-10 N/A 1398 539-10 N/A 1399 Seal Water Return Filter AMF, Cuno 102 43470 2615 Safety Inj. ~

Accumulators Delta Southern Co.

lA N/A 434 30 2710 1B N/A 434678 2711 Notes 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 1 through 6 on this data report is included on each sheer, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

  • Designates account number of arrangement with Authorized Inspection Agency to provide inspec' tion services.

This form (E00029) may be obtained from the Order Dep:.. ASME,345 E. 47th St., New York, N.Y. 10017

r e ' .

FORM NIS-1 (back) .

8. Examination Dates 1/82 to 6/82 9. Inspection Interval frtem 9 / 30/ 76 co o/tn/RA
10. Abstract of Examinations. Include a list 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 B of Final Report.
12. Abstract of Corrective Measures Recommended and Taken Reference Tab B of Final Report.

We certify that the statements made in this report are correct and the examinations and corrective mea.

sures ta conform to the rules of the ASME Code,Section XI.

Date .

/3 19 82 Signed _ Duonemnn TMght cnn By /14/ hf, '

! " O* "*'

datiodSuperintehht ,.

Certificate of Authorization No.(if applicable) 26-05000 . Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION I, the u'ndersigned, holding a valid corEmissi sued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of ,

We and employed by I of e have inspecy'd the components described in this Owners' Data Report during the period

/ / 8 a7 to d /F2 . and state that to the best of my knowledge and belief, the Owner has pedormed examinations add taken corrective measures described in this Owners

  • Data Report in aclcordance ,

with the requirements of the ASME Code,Section XI. .

By signing this certificate neither the Inspector nor his employer makes any warranty,' expressed or linplied, concerning the examinations and corrective rneasures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspe .

Date -

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l0 19 Commissions ._ . c National B'oard,lState Province and No.

/[" Inspecg Signature h

-23 4

' >rs.n.

A Q A ( 4 d _.

C

l

-  ?

I DUQUESNE LIGHT COMPANY BEAVER VALLEY UNIT ONE POWER STATION INTERVAL 1 - PERIOD 2 - CORE OUTAGE II-III INSPECTION SERVICE EXAMINATION

SUMMARY

INTRODUCTION An inservice examination of' Class 1, 2 and 3 components was conducted at the Beaver Valley Unit 1 from January,1982 through June,1982. The exam-inations.were performed in accordance with the program plan located under .

Tab C of .the Final Report.

The program plan for this outage was derived from the Inservice Ten Year Inspection Plan. This plan incorporates the ASME Code Section XI require-ments defined in the 1974 Edition through the Summer 1975 Addenda and the

- Plant Technical Specification Section 4.0.5 requirements. Specific items for examination relief, modification and additional requirements are de-fined in Amendments 22 3nd 48 of the Plant Technical Specifications.  ;

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Selected main steam and feedwater postulated break points (high energy j program) in the main steam valve house were examined ,as required by Appendix 0, Section D 3.2 of. the BVPS Unit i FSAR.

Following the replacement of two pressurizer relief valves, a baseline

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ultrasonic examination of the new welds was performed.

RESULTS The examination data sheets recording all of the Class 1 and 2 volumetric, surface and visual results are located under Tab D of the Final Report.

The various examinations produced recordable indications in accordance '

with the ISI procedure recording criteria, which are generally more re-strictive than specified in the ASME Section XI Acceptance Standards. All indications were~ evaluated and dispositioned by EM (Engineering Memorandum),

NCAR (Nonconformance and Corrective Action Report) or QCR (Quality Control Report) documents located under Tab F of the Final Report. An explanation 4

of the Summary of Recorded Indications is as follows:

CLASS 1 A. 'J1trasonic Examination One indication in weld #2 of the 4" pressurizer spray line (program item 28) was reported as a geometric reflector for information and was accepted with no corrective action.

B. Surface Examination Linear and rounded liquid penetrant indications were recorded in five reactor coolant piping stainless steel welds, of which two were Loop B and two were Loop C dissimilar metal welds. In Loop B one rounded and ,

one linear indication in nozzle to safe-end welds 1(DM) and 16(DM) re- .

spectively were eliminated by the minor removal of metal'. Other linear and rounded indications in weld 16(DM) were not completely removed because of minimum wall restrictions. The results of the final liquid penetrant test were evaluated and accepted. A linear indication in weld 8 of Loop B reactor coolant piping was accepted without corrective action. In Loop C a linear indication in weld 1(DM) was eliminated by minor metal removal, and rounded indications in weld 16(DM) were accepted with no corrective action. Linear indications on welded support (H3) (program item 50) and drain header weld #39 (program item '

48) were corrected with minor metal removal.

C. Visual Examination Rust ar.d white boric acid residue were recorded on the flange bolting of valve RH-720A (program item 71). .The boric acid residue was removed and the rust was evaluated as acceptable with no corrective action.

Rust was also recorded on tha flange bolting threads of valve CH-310 (program item 75) and was evaluated as acceptable with no corrective action.

a

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C. Visual Examination (cont'd)

During Class 1 system leakage examinations, minor leakage and/or boric acid residues were identified on twenty-four (24) Class 1 valves. The leakage was evaluated as insignificant and within allowable station Technical Specification Limits. However, corrective maintenance was initiated on the affected areas. .  ;

CLASS 2 The reported indications were predominantly visual observations of surface rust and white boric acid residue on the bolting of various components.

The evaluation of ti. 9 visual examinations concluded that no corrective action was required in the cases where surface rust was reported. Com-ponents on which boric acid residues were reported were cleaned, re-examined and found to be acceptable.

A linear liquid penetrant indication on welded support (H6) (program item 136) was removed by surface finishing.

One ultrasonic indication in Loop 3 main steam weld 1,9.(program item 114) was within Section XI acceptance criteria and no corrective action was re-quired.

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

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

Ultrasonic examination that produced greater than reference level sensi-tivity from reflectors that are characteristic of metallurgical structure I

- ___ ____- _--_-_____ D

O 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) Inside diameter weld preparation or root configuration and the outside diameter crown overlay or toe.

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

(3) The metallurgical structure of the cast materials.

(4) Responses from the thread areas of bolting.

LIMITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1971 and/or 1974 Cada could be applied; consequently, some examinations are limited or not practical due to geometric configuration or accessibility. Generally these Ifmitations 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 assemblies, particularly where the weld is not ground flush with the pipe 0.D. Furface.

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

When the weld surface is flat, the fitting side examination is replaced by a calibrated straight beam examination on the weld.

In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally, the weld and base metal for 1 "T" on each side) as poss:ble.

m.

However, the extent of examination coverage in the base metal of the fitting or component cannot be'specifically quantified as being 100%. These areas where complete examination of 100% of the required volume of area could not be achieved were indicated by a PAR (partial) notation on the examiners' data sheet and the limiting cause noted.

The principal basis for PARI 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 examin-ation of a pipe to elbow assembly, where scannir.g 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 com-ponent side is limited by configuration. 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, etc. However, the vo.ume on the fitting or component side additionally cannot be scanned completely for transve'rse 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 examinations are as indicated on the report data sheets under Tab D of the Report.

1

INSERVICE EXAMINATION PROGRAM  :

FOR DUQUESNE LIGHT COMPANY.

BEAVER VALLEY UNIT #1 Refueling Outage Core II-III

.All items listed below were examined, as indicated, in accordance with the re-quirements of the Plant Technical Specifications Section 4.0.5 (including Amd.

22 and Amd. 48)and to the requirements of Section XI of the ASME Boiler and

=

Pressure Vessel Lode, to the extent practical with the access provided and the ,

i limitations of component geometry. Examinations were performed to the 1974 j Edition of Section XI thru 1975 Summer Addenda. j

'I PROGRAM IWB-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE (See Program Note 1) V0L SUR VIS DLW REACTOR VESSEL 1 Bl.6 (3) outlet nozzles to safe-end 205 11 1-4100 welds #1DM 3 places. (Note 6) ~

1-4200 .

1-4300 2 Bl.6 (3) inlet nozzles to safe-end 205 11

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1-4100 .

welds #16DM 3 picces. (Note 6) '

- 1-4200

'l-4300-3 Bl.8 Closure studs and nuts #20 thru 15 70 1-1400 -

thru #38. ,

Bl.10 4 Closure head washers #20 8 1-1400 thru #38. ,

PRESSURIZER (See Appendix 1) l 5 82.1 Long. shell welds #1, 2 and 3. ,

47 1-2100 6 B2.1 Circ. shell welds #4, 5, 6 and 47 1-2100 7.

7 B2.2 Inside radii #2, 3 and 4.

8 (2) 1-2100 8 82.4 6" safe nozzles to safe-end 11 1-4501 welds #1DM, 10DM and 19DM (See Item 16) s 9 B2.8 Support skirt weld #8. 205(3) 1-2100 Numbers under Examination Procedure in ( ) refer to specific items under ./o l Program Notes on the last page. ,

Page 1 of 16

. .m., _.-_ , _ _ . _ - _ _ . _ . y ._

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i PROGRAM IWB-2600 EXAMINATION SKETCH

, ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE V0L SUR VIS DLW 10 B2.11 Manway bolts #6 thru #10. 8 1-2100

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STEAM. GENERATORS 11 B3.1 Channel head to tube sheet welds 47 1-3100

  1. 1-1, #2-1, #3-1. Examine 7.5" to 15" CW around circumference.

0 reference top centerline of hotleg manway.

I 12 ,B3.3 No::le to safe-end walds 4DM 205 11 1-4200 and SDM.(See Item 14)

PIPE' TO SAFE-END WELDS

~13 B4.1 Loop 1 R.C. pipe 1(DM) & 16(DM). 205 11 1-4100

' 14 B4.1 ^

Loop 2 R.C. pipe DM's #1, 4, 5 205 11 1-4200

& ~16. (See Item 12) 15 B4.1 Loop 3 R.C. pipe DM's #1 & #16 205 11 1-4300 16 B4.1 11 1-4501

, 6" Press.

(DM's) (Sdesafety Item 81}10&19

. REACTOR COOLANT PIPE 17 B4.5 Loop 2 R.C. pipe welds #8 & #9. 205 11(5) 1-4200 f 18 B4.5 Loop 3 R.C. pipe weld #3. 205 11(5) 1-4300 ASSOCIATED AUXILIARY PIPING WELDS 1.9 104.5 ' Loop 1 hot leg 14" RHR weld #7. 205 T-4101 20 B4.5. 14" Press. Surge Weld #2 205 1-4500 2,1 Deleted 7 22 B4.5 Loop 3 cold leg acc. discharge 205 1-4301

/ and 10" RHR return weld #3.

23 -84.5 Loop 2 8" Bypass Welds #5 and 205 1-4202

  1. 6.

24 B4.5 Loop 2 cold leg 6" SIS welds 205 1-4203

  1. 3, 4, and 5.

Page 2 of 16

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PROGRAM IWB-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE V0L SUR VIS DLW

25 B4.5 Loop 2 hot leg 6" SIS welds 205 1-4204 '
  1. 1, 2, 3, 4 and 5 26 B4.5 6" press. relief welds #9 and 205 11 1-4502
10. (PT for #10 only) 27 B4.5 4" Loop 1 cold leg press. spray 205 1-4503 wel.ds #40, 41, 42 and 43, 28 B4.5 4" Loop 3 cold leg press. spray 205 11(5) 1-4504 welds #2, 3, 4, 8 and 36*.

. l 29 B4.5 Loop 2 3" charging line welds 205 1-4205

  1. 1, 2, 3, 4.

30 B4.5 Loop 2 3" RTD Return welds #11 205 11(5) 1-4206 12*, 13 and 14.

. 31 B4.5 6" and 3" press. relief welds 205 11(5) 1-4502

  1. 20, 21 and 22*.

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32 B4.5 Loop 2 cold leg 1-1/2" and 205 1-4208 I 2" RTD take-off weld 25 (BW) 33 B4.5 1 1/2 Press. spray _line weld 205 1-4506

  1. 14(BW).
  • See Program Note 5.

BRANCH PIPE CONNECTIONS > 6" 34 B4.6 Loop 2 cold leg 12" acc. 205 11(7) 1-4201 discharge weld #34(BC).

BRANCH PIPE CONNECTIONS 6" AND LESS 35 B4.7 Loop #2 hot leg 6" low head SIS 11 1-4204 weld #22(BC).

36 84.7 Loop #2 3" charging weld #26(BC) 11 1-4205 t 37 B4.7 Loop #2 cold leg 1-1/2" x 2" 11 1-4208 RTD take-off weld 1(BC).

38 B4.7 Loop #2 2" fill line weld 11 1-4210 i

  1. 27(BC).

Page 3 of 16

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l i I PROGRAM IWB-2600 EXAMINATION SKETCH I ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE l T

V0L SUR VIS DLW l 39 B4.7 Loop #3 cold leg 4" precsurizer 11 1-4504 spray weld #1(BC).

SOCKET WELDS 40 B4.8 Loop #2 cold leg 2" low head SIS 11 1-4203 weld #1 41 B4.8 Loop #2 hot leg high head SIS 11 1-4207 welds #7, 8, 9, 10 and 11.

42 B4.8 Loop #2 cold leg 1-1/2 x 2" 11 1-4208 RTD take-off welds #2, 3, 4, 5 and 6.

43 B4.8 Loop #2 hot leg 2" RTD take-off 11 1 4209 welds #2, 3, 5, 6, 7 and 8.

44 B4.8 Loop #2 2" fill line welds #14, 11 1-4210 15, 16, 17, 18 and 19.

45 B4.8 Loop #2 2" drain line welds #3, 11 1-4211 4, 5 and 6.

46 B4.8 Loop #2 2" x l-1/2" seal 11 1-4212 injection welds #37, 38, 39, 40',

41, 42, 43, 45, 46,,47 and 48.

I 47 B4.8 2" fill header welds #10,11,12, 11 1-4601

, 13, 14, 15, 16 and 17.

48 B4.8 2" drain header welds #32, 33, 11 1-4602 34, 35, 36, 37, 38, 39, 40 and j 41. .

49 B4.8 Loop #2 2" pressure equalization 11 1-4603

! welds #32, 33, 34 and 35.

  • INTEGRALLY WELDED SUPPORTS 50 B4.9 Loop #2 cold leg 12" accum. 11 1-4201
discharge and 10" RHR return j (Hl),(H2),(H3).

51 B4.9 Loop #3 cold leg 6" x 2" 205 11 1-4303 low head SIS (Hl), (H2).

Page 4 of 16

PROGRAM IWB-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE VOL SUR VIS DLW l

52 B4.9 Loop #2 3" charging (H1). 205 11 1-4205  ;

53 B4.9 Loop #2 2" drain line (Hl). 205 11 1-4211 54 B4.9 Loop #3 cold leg 4" pres- 205 11 1-450.4

- surizer spray (Hl), (H2), (H3),

(H4),(H13). ~

55 B4.9 6" pressurizer safety: (H2). 11 1-4501  :

56 B4.9 6" and 3" pressurizer relief: 205 11 1-4502 (H7).

  • See Program Note 8.  :

PIPING SYSTEM SUPPORTS (Reported to DLW-1-4800) 57 B4.10 Loop #2 hot leg 6" low head 8 1-4204 SIS: H2,(H5).

58 B4.10 Loop #2 2" hot leg high head 8 1-4207 SIS: H2 & H3.

59 B4.10 Loop #2 2" fill line': H3 & H4 8 1-4210 s

(See Item 70).

60 B4.10 Loop #2 2" and 1-1/2" seal 8 1-4212 '

injection: H1 (H3), H6, H7 -

61 14.10 2" fill header: H3,(H7),H8,H9, 8 1-4601 H10, Hil, (H12), H13, H14, H15, (H16),H17,H18,H19,H20,H21, (H22),(H23) 62 B4.10 3" high head hot leg SIS: H1 8 1-4600 PRESSURE RETAINING BOLTING 63 B4.12 Loop #2 2" x l-1/2 seal injection, 8 1-4700 item 9.

64 B4.12 6" pressurizer safety valve 8 1-4700 5518 valve mounting flange, item 17.

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Page 5 of 16 t

PROGRAM IWB-2600 EXAMINATION SKETCH ITEM ~ REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE VOL SUR VIS DLW REACTOR COOLANT PUMPS 65 B5.1 Flange bolting 3-B1 thru 3-824 15 1-5100 (in place).

66 B5.2 and

  • Seal housing bolting 2-B1 thru 15 70 8 1-5100 B5.3 2-B12 and 3-B1 thru 3-B12 ~

(disassembled).

  • See Program Note 9.

FLYWHEELS R. C. Pump Flywheel (Loop A).

67 Reg. Guide .41 8 1-5100 1.14 LOOP STOP VALVE BOLTING Loop #2: Valve 592, examine bol'os 15 68 B6.1 l-6100 2-1 thru 2-24.

69 B6.1 Loop #2: Valve 593, examine bolts 15 1-6100 2-25 thru 2-48. ,

VALVE SUPPORTS AND HANGERS 70 B6.5 Loop #2 2" fill line support 8 1-4210 H4 (See Item 59).

VALVE BONNET 20LTING (Items reported to DLW-1-6300)

ITEMS 71 B6.9 Loop #2 cold leg 12" accum. 11 8 1-4201 discharge and 10" RHR return 13 SI-49, and 720A (16 each).

,. 72 'B6.9 Loop #2 cold leg 6" and 2" 15 8 1-4203 l low head SIS SI-11 (12).

i 73 B6.9 Loop #2 hot leg 6" low head 17 8 l-4204 SIS SI-16 (12).

74 B6.9 6" pressurizer safety RC-551B (8) 32 8 1-4501 I

75 B6.9 Loop 52 3" charging CH-310 (16) 20 8 1-4205 4 Page 6 of 16

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PROGRAM IWC-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AN" EXTENT OF EXAMINATION PROCEDURE REFERENCE l

VOL SUR VIS DLW l STEAM GENERATORS

j. 76 Cl.1 Stub barrel to upper tubesheet 47 2-1100

, weld Loop 1 weld #1-2; 142.3" to 149.5" = 7.2".

77 C1.1 Lower shell to stub barrel weld 47 2-1100 Loop 1 weld #1-3; 141.4" to 148.5"

= 7.1".

78 Cl.1 Transition cone to lower shell 47 2-1100 weld Loop 2 weld #2-5; 141.4" to 148.5" = 7.1".

79 Cl.1 Upper shell to transition cone 47 2-1100 weld Loop 2 weld #2-6; 184.1" to 193.3" = 9.2".

80 Cl.1 Upper head 'to shell weld Loop 3 47 2-1100 Weld #3-8; 184.1" to 193.3" =

9.2".  ;

l NOTE: Datum = centerline Feedwater Nozzles l

EXCESS LETDOWN HEAT EXCHANGER I 81 C1.1 Head to flange weld #1; examine 205 2-1110 9.950" to 10.45" CW from 0 ref-erence.

RESIDUAL HEAT EXCHANGERS 82 Cl.1 Head to shell weld 1-1; examine 205 2-1120 41.62" to 43.62" CW from 0 ref- l erence.

83 C1.1 Shell to tubesheet weld 2-2; 205 2-1120 l examine 41.62" to'43.62" CW from 0 reference.

84 C1.4 Flange bolting 1-B17 thru l-B32 15 8 2-1120

. Page 7 of 13

PROGRAM IWC-2600 EXAMINATION SKETC$

ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE VOL SUR VIS DLW SEAL WATER HEAT ~ EXCHANGER 85 Cl.1 Head to shell weld #1; examine 11(II)8 2-1130 16.66" to 17.41" CW from 0 reference.

86 C1.1 Shell to flange weld #2; examine ll(II)8 2-1130 16.66" to 17.41" CW from 0 reference.

NON-REGENERATIVE HEAT EXCHANGER 87 C1.1 Head to shell weld #1; examine 205 2-1140 43" to 45" CW fron 0 reference.

88 Cl.1 Shell to flange weld #2; examine 205 2-1140 48" to 50" CW from 0 reference.

REGENERATIVE HEAT EXCHANGER 89 Cl.1

  • Head to shell weld #2; examine 205 2-1150 3" from 0" ref. datum CW.

90 C1.1 *Shell to tubesheet-weld #8; 205 2-1150 examine 3" from 0" ref. datum CW.

  • See Program Note 12
VOLUME CONTROL TANK 91 Cl.1 Lower head to shell weld #1; 205 2-1200 examine 87.79" to 92.29" CW from 0 reference.

92 C1.1 Upper head to shell weld #2; 205 2-1200 examine 87.79" to 92.29" CW from 0 reference.

93 Cl.4 Manway bolts B6 thru B10. 8 2-1200 SIS ACCUMULATORS 94 Cl.1 Head to shell welds 1-2 & 2-2; RT(15) 2-1210 examine 0" to 7.0" CW from 0 400 reference.

Pa@@ 8 of 16 j

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PROGRAM IWC-2600 EXAMINATION SKETCH t ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE V0L SUR VIS DLW  ;

95 C1.1 Head to shell weld 2-1; 205 2-1210 examine 0" to 7.5" CW from 0 reference. 3 6

96 C1.3 Support skirt weld 2-4; examine 11 2-1210 0" to 37" CW from 0 reference.

. BORON INJECTION TANK 97 Cl.1 Head to shell welds #1 & 2; 205 2-1220  ;

examine 53.3" to 56.3" CW from  ;

O reference. -

l 98 Cl.4 Manway bolts B6 thru B10. 8 2-1220 SEAL WATER INJECTION FILTERS.

99 Cl.1 Head to shell weld 1-1; examine 11(13)8 2-1300 i 11.25" to 11.82" CW from 0 reference.

100 C1.1 Shell to flange weld 2-2; examine 11(13)8 2-1300 11.25" to 11.82" CW from 0 reference. ,

SEAL WATER RETURN FILTER 101 Cl.1 *H'ead to shell weld #1; examine 11(13)8 2-1320 16.75" to 17.60" CW from 0 reference.

102 C1.1

  • Cover weldment to shell weld 11(13)8 2-1320

.#2; examine 16.75" to 17.60" CW from 0 reference.

  • See Program Note 14 ASSOCIATED AUXILIARY PIPING 103 C2.1 Loop 1 32" SHP-56: Weld 1 205(10) 2-2111 104 C2.1 Loop 1 32" SHP-56: Weld 2B 70(10) 2-2111 105 C2.1 Loop 1 32" SHP-22: Welds 2A, 70(10) 2-2111 3A i

. Page 9 of 16

PROGRAM IWC-2600 EXAMINATION SKETCii ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE V0L SUR VIS DLW 4

106 C2.1 Loop 1 32" SHP-22: Weld 19 205(10) 2-2111 107 C2.1 Loop 2 32" SHP-57: Weld 9 205 2-2120 108 C2.1 Loop 2 32" SHP-57: Weld 1 205(10) 2-2121 109 C2.1 Loop 2 32" SHP-57: Weld 2B 70(10) 2-2121 110 C2.1 Loop 2 32" SHP-23: Welds 2A, 3A 70(10) 2-2121 111 C2.1 Loop 3 32" SHP-58: Weld 1 205(10) 2-2131 Loop 3 32" SHP-58: }

112 C2.1 Weld 2B 70( 2-2131 113 C2.1 Loop 3 32" SHP-24: ' Welds 2A, '

70( 0) 2-2131 3A 114 C2.1 Loop 3 32" SHP-24: Weld 19 205

0) 2-2131 115 C2.1 Loop 1 16" WFPD-22: Weld 2 205(10) 2-2210 116 C2.1 Loop 2 16" WFPD-23: Weld 4 205 2-2220 117 C2.1 Loop 3 16" WFPD-24: Weld 2 . 205(10) 2-2230 i

118 C2.1 14" RHR: Welds 5 and 6 205 2-2310 119 C2.1 12"-RH-9 Welds 15,16 & 17 205 2-2311 120 C2.1 Loop 2 12" Accum. Disch.: 205 2'-2509 l

Weld 2 121 C2.1 Loop 3 12" Accum. Disch.: 205 2-2510 Weld 5 122 C2.1 12" L.H. Safety Inj. Pump: 205 2-2521 Weld 12 123 C2.1 10" RHR: Weld.22 205 2-2310 124 C2.1 10" Recirc. Spray: Weld 4 11 (I4) 8 2-2513 125 C2.1 10" Recirc. Spray: Weld 17 11(I4) 8 2-2514 126 C2.1 10" Recirc. Spray: Welds 12, 11(I4) 2-2515 13 127 C2.1 8"-SI-2: Welds 69, 70 11(I4) 2-2410 1

Page 10 of 16

PROGRAM IWC-2600 EXAMINATION SKETCH ITEM j

REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE V0L SUR VIS DLW 128 C2.1 6"-CH-67: Welds 20, 21 11(I4) 2-2410-129 C2.1 6"-SI-42: Weld 21 205 11 2-241,1 130 C2.1 6"-SI-44: Welds 2,3,4 ll II4) 2-2412 131 C2.1 6"-51-40: Welds 6,7 11 II4) 2-2413 LONGITUDINAL WELDS IN FITTINGS 132 C2.2 Loop 2 32"-SHP-57; Weld #8 205 2-2120 -

L. S.

PIPING PRESSURE RETAINING BOLTING (Reported to DLW-2-2600) 133 C2.4 Item #4 - Flange #4 15 8 2-2310 134 C2.4 Items #5 & 6 - Tranges il & 2 15 8 2-2311 INTEGRALLY WELDED SUPPORTS (Reported to DLW-2-2700)*

135 C2.5

  • Items #29- Loop 2 Feedwater: (H2) 11 2-2220 136 C2.5
  • Items #38, 40, 48 & 50 - RHR: 11 2-1310 (H4), (H6), (H14) & (H16) 137 C2.5
  • Items #65 & 69 - RHR: (H1),(H5) 11 2-2312 138 C2.5
  • Item #113 - CVCS: (H9) 11 2-2411 139 C2.5 Items #122 & 133 - CVCS: (H4), 11 2-2412 (H15)*

PIPING SUPPORT COMPONENTS (Reported to DLW-2-2700) 140 C2.6 Items #28 & 30 - Feedwater, H1, H3 8 2-2220 141 C2.6 Items #39 - RHR: HS 8 2-2310 142 C2.6 Item #63 - RHR: H10 8 2-2311 143 C2.6 Items #66,68,73 - RHR: H2,H4,H9 8 2-2312 144 C2.6 Items #90,95,97,98,99 - CVCS: H6, 8 2-2410 Hil,H13,H14,H15 Page 11 of 16

PROGRAM IWC-2600 EXAMINATION- SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION' PROCEDURE REFERENCE V0L SUR VIS DLW 145 C2.6 Items #119,120,121 - CVCS: H1, 8 2-2412 H2, H3 RHR PUMPS 146 C3.2 Bolting; l-B1 thru l-B16 8 2-3100 147 C3.4 Support Components 1-15C & 1-2SC 8 2-3100 CENTRIFUL1L CHARGING PUMPS 148 C3.2 Pressure retaining bolting 15 2-3110 1-B1 thru l-B16 149 C3.2 Bolting; l-81 thru l-B10 8 2-3110 150 C3.3 Integrally welded supports 11 2-3110 1-1WS, 1-2WS 151 C3.4 Support components 8 2-311d 1-lWS, 1-2WS, 2-3WS VALVE PRESS. RETAINING BOLTING (Reported to DLW-2-4110) 152 C4.2 Items #28, 29, 30 and 32 thru 36 - 8 2-2310 RHR: Valves #V-1 thru V-8 153 C4.2 Items #37 thru 40 - RHR; Valves 8 2-2311

  1. V-9, V-10, V-605, V-758 154 C4.2 Items #28, 29 - RHR; Valves VI & 15 2-2310 V2 Page 12 of 16

o .- 0 ADDITIONAL EXAMINATIONS SERFORMED BY DUQUESNE LIGHT COMPANY (See Tab E) l PROGRAM IWB-2600 EXAMINATION SKETCH ITEM REFERENCE AREA AND EXTENT OF EXAMINATION PROCEDURE REFERENCE VOL SUR VIS DLW 155 B4.5 3" Pressurizer Relief 205 -- --

1-4502 Welds #22, 23, 28, 29 The baseline examination of the welds was performed after the replacement of pressurizer relief valves MOV-RC-535 and 536.

156 A system leakage test at system operating pressure and temperature was performed on 100% of the Class 1 com-ponents prior to startup following the second reactor refueling outage. The examinations were performed in acccrdcrice with Section XI of the ASME Boiler and Pressure Vessel Code,1974 edition through the summer 1975 addenda, and the plant Technical Specifications, to the extent l

. practical and with the access provided and the limitations of component geometry. l The following is a list of the isometric drawings on which examinations were performed:

DLW-1-1100 Reactor Vessel DLW-1-1300 R.V. Closure Head DLW-1-2100 Pressurizer DLW-1-3100 Steam Generators

' DLW-1-4100 to Loop #1 Piping

! DLW-1-4113 DLW-1-4200 to Loop #2 Piping DLW-1-4212 DLW-1-4300 to Loop #3 Piping DLW-1-4311 DLW-1-4500 to Pressurizer Piping DLW-1-4506 DLW-1-4600 to Auxiliary Piping DLW-1-4603 DLW-1-5100 R.C. Pumps Visual examination for evidence of leakage was conducted in accordance with Procedure ISI 11.0, Rev. O.

Page 13 of 16

~

ADDITIONAL EXAMINATIONS PERFORMED BY DUQUESNE LIGHT COMPANY (See Tab E) l 157 A system pressure test at system operating pressure and temperature was performed on the buried portions of the Class 3 'A' reactor plant river water header--line number

' 24"WR-101-301-Q3. The examination was performed in accord-ance with subarticle IWD-2600(b) of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Editioa through the summer 1975 addenda. The pressure test was conducted in accordance with Temporary Operating Procedure 81-41.

l-1 4

i i

f Page 14 of'16

a .c '. .

i PROGRAM' NOTES

1. The examination areas shown in this program were conducted in accu. dance with the Ten Year Inspection Plan. Examinations that were deferred during this outage will be performed during future outages.
2. Substitute V.T. for U.T. as specified by Amendment 22, A.2.
3. Examination shall include the weld and 2T base metal on the support side of the weld in compliance with the Code.
4. Relief from 100% volumetric examination in compliance with Amendment 22, A.3.
5. UT will be supplemented by PT as required by Amendment 22, A.4.

t

6. Augmented examinations on reactor vessel nozzle to safe-end welds in  ;

compliance with Amendment 48.  ;

7. UT will be supplemented by PT cn this weld as required by Amendment 22,  !

A.S.

s

8. UT the base metal and PT the weld metal as required by Amendment 22, A.6. I
9. Examination when disassembled as required by Amendment 22, A.7. h A
10. Selected main steam and feedwater postulated break points in the main  ;

steam valve house examined in accordance with Appendix D, Section D3.2 l of the BVPS Unit 1 FSAR.

i 11 Substitute P.T. and V.T. for U.T. because the material is too thin for I meaningful U.T. examination. Reference Amendment 22, B.S. -

i

12. Examine 10% of the respective one weld total -length rather than 100%

during each 40-month period. Reference Amendment 22, B.2. '

13. Substitute P.T. for U.T. as specified by Amendment 22, B.4.
14. P.T. and V.T. substituted for U.T. because the material is too thin for meaningful U.T. examination as specified by Safety Evaluation Report dated 2/25/82.

t t

15. Substitute RT because weld inaccessible for UT examination. '

f s

Page 15 of 16

DLW+21OO  !

1 PRESSURIZER l

I i

ELEVATIONS l CPf1 Bolts 780'8.750" -

1

  • t

}

g

\ 11;1,

% ,,.,i<r 774'9- 1&3 g\"

\ 3 l

I

! (Ref) 72"

  • s-(Ref)  ;

N LONG SEAM ORIENTATIC.1

% i 769'11.s*

I - 767'10"

&mL T;i'..'!. { {'.': ' '

l

.}. i

= .

Weld #8. Examine from 10" to 5x -

20" clockwise using centerline N  :

weld #1 as 0 reference. , j 759'2.250-Weld #4: Examine from 5" to i l 777 mTi177177TTIi 177JN "

(adj.acent weld #1).

j Weld #5: Examine from 5" to t l l

10" clockwise from 0 reference !

(adjacent weld #1) i j Weld #6: Examine from 5" to

! i

.4 -

! 'N 10" clockwise from 0 reference i (adjacent weld #3) I Weld #7:

@\\ 748'6.5- Examine from 5" to 10" clockwise from 0 reference s (adjacent weld #3) i Weld #1: Examine from 5" to

,l ,7,3 2 10" from 0 reference (adjacent weld #5) l Weld #2: Examine from 15" to l 20" from 0 reference (adjacent weld #5)

Weld #3: Examine from 31" to 36" from 0 reference (adjacent ,

weld #7)  !

APPENDIX 1 Pagtlfuaf M

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