ML20040E630

Inservice Insp Rept on 811007-1115.Describes Exams Performed on Socket & Support Welds,Reactor Coolant Pump Flywheel & Steam Generator & Pressurizer Vessel Cladding

ML20040E630
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/15/1982
From:	Delawarence J CONNECTICUT YANKEE ATOMIC POWER CO.
To:
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ML20040E623	List: ML20040E622 ML20040E630
References
NUDOCS 8202050188
Download: ML20040E630 (33)

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INSERVICE INSPECTION (1981) s

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DATA' REPORT

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'fEwk Prepared by: Josaun Lee DeLawrence January 15, 1982 GCli 3':

8202050188 820121 PDR ADOCK 05000213 G

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TABLE OF CONTENTS

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Owners Data Report "NIS-1-Form...................................... TAB-A e

Summary............................................................. TAB-B t

Examination Program................................................. TAB-C' t,

4 i Deferred Items......................................................TAB-D Indication Recorded................................................. TAB-E Inspection Ab stract................................................. TAB-F ISI-QC-Verification................................................. TAB-G Examination Procedures.............................................. TAB-H

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Personnel Qualification / Certification............................... TAB-I Ultrasonic Equipment and Search Units................................ TAB-J Calibratiori S tandards Used.......................................... TAB-K Consumable Materials................................................ TAB-L e

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FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Owner Connecticut Yankee Atomic Power Co.-P.O. Box 270, Hartford Ct.

06010 9

(Name and Address of Owner) 2.

Plant Connecticut Yankee Nuclear Generating Plant, Haddam Neck Connecticut (Name and Address of Plant) 3 Plant Unit One

h. Owner Certificate of Authorization (if required)

N/A 5

Commercial Service Date 01/01/68

6. National Board Number for Unit See N.B. below 7

Components Inspected 1

Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

Closure Studs Combustion

• Engineering N/A N/A N/A Closure Nuts Combustion Engineering N/A N/A N/A Closure Washers Combustion Engineering N/A N/A N/A I

By Pass Piping Crane Co.

N/A N/A I

N/A

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x_,/ canch Connection Crane Co,.

N/A N/A N/A R.C. Drain Piping Crane Co.

N/A N/A N/A Drain Piping Supports ITT Grinnell N/A N/A N/A RCP Flywheels Westinghouse N/A N/A N/A S/G Supports Westinghouse N/A N/A N/A RHR Piping Supports ITT Grinnell N/A N/A N/A Feed l

Water Supports ITT Grinnell N/A N/A N/A 1

CVCS Supports ITT Grinnell N/A N/A N/A Note:

Supplemental sheets in form of lists, sketches, or drawings may be used previded (1) size is 8 in.x 11 in., (2) information in items 1 through 6 on this data I

j, report is included on each sheet, and (3) each sheet is numbered and the number l

of sheets is recorded at the top of this form.

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FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Owner Connecticut Yrinkee Atomic Power Connany-P.O. Box 270, Hartford, Ct.06010 V

(Hame and Address of Owner) 2.

Plant Connecticut Yankee Nuclear Generating Plant,-Haddam Neck, Ct.06h2h (Name and Address of Plant)

h. Owner Certificate of Authorization (if required)

N/A 3

Plant Unit one 5

Commercial Service Date 01/01/68

6. National Board Number for Unit See N.B. be.kw j

T.

Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenuce or Installer

, Serial Nr.

Province No.

Board No.

S/G Cladding Westinghouse EG-3,4 N/A N/A Pressurizer Caldding Westinghouse E-8 N/A N/A R.V. Bottom Head Combustion Engineering 63103 N/A 15179 N/A N/A N/A N/A N/A O)

Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is Sh in.x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each st.7et is numbered and the number of sheets 10 recorded at the top of this form.

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FOPJ4 HIS-1 (back) 8.

Examination Dates 10-7-81 to 11-15-81

9. Inspection Interval from 1978 to 1988

,- m Abstract of Examinations. Include a list of examinations and a statement concerning r,tatus of work required for current interval.

11.

Abstract of Conditions Noted.

12.

Abstract of Corrective Meas'ures Recommended and Taken.

We certify that the statements made in this report are correct and the cxaminstions and corrective measures taken conform to the' rules of the ASME Code,Section XI.

DE cou.' eMe bow c. wub. Byb-L%a Date I-W 19 Signed Owner M

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Cartificate of Authorization No. (if applicable)

MA Expiration Date 9k C P.TIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid com=ission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Co 4 d and employed by N' 9. 6 Jr#7 C, of

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have inspected the components to //-/ P 5/,

jascribed in this Owner's Data Report during the period __/O W /

I state that to the best of my knowledge and belief, the Owner has performed examinatiens and taken corrective measures described in this Owner's 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 varranty, cxpressed or implied, concerning the examinations and corrective measures described in this Owner's Data Report.

Furthermore, neither the Inspector nor his enployer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date

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199f d Y M I Commissions

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Inspect'or's Signature National Board, State, Province V

and No.

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A CONNFCTTCUT YANYEE ATOMTC POWER COMPANY

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HADDAM NFCK PLANT REFUFLING OUTACF CODF INSERVICE INSPECTION SDNARI An inservice inspection was performed at Connecticut Yankee, Haddam Neck plant over the period 10-7-81 to 11-15-81.

The examination covered the second 10 year period (1978-1988) and some of the items which have been deferred from the 10 year period (1970-1980).

All items in the second 10 year period were examined in accordance with the requirements of Technical' Specification section 4.10 and the requirements of the 1977 edition of Section XI of the ASME Boiler and Pressure Vessel Code up to and including summer '78 addenda. All items in the 10 year period, which were previously deferred, (see tap D) were examined in accordance with the requirements of. Technical Specification 4.10 and the requirements of the 1974 edition of Sepiion XI of the ASME Boiler and Pressure Vessel Code up to and incluepng summer '75 addenda.

'Some of the arrangements and details of the piping systems and components were designed and, fabricated before the access and examination requirements of Section XI of the'1971 code could be applied. Generally (Q_/ ',

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 conditions preclude ultrasonic coupling or access for the required scan length. The limitations exist to a lesser degree where the weld is not ground flush with the pipe outside diameter surface and support geometry. Areas where complete examination could not be achieved are indicated on the examiner's data sheet, and the limiting cause is noted. Specific limitations and restrictions for all examinations are indicated on the data sheets.

Examinations were performed by Northeast Utilities Service Company Inservice Inspection Reliaility Engineering and Westinghouse Electric l

Corporation Nuclear Service Division..

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The inservice inspection program was reviewed by Hartford Steam Boiler Inspection and Insurance Company and they provided Connecticut Yankee with the authorized nuclear inspector for the 1981 refueling outage.

Dye penetrant and visual examination.of socket welds and support welds revealed minor surface indications. Some welds with surface indications were found acceptable in accordance with Section XI of the ASME code.

Other indications were removed by buffing or grinding the surface to a conditic.a suitable for peaetrant examination and the welds examined were acceptable.

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Three supports nad very small areas inaccessibic for cleaning.

These areas were evaluated and determined to be acceptable geometry

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problems. Where these conditions existed, no indications in

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examined areas were noted.

During the visual inspection of supports there were numerous indi-cations of slight rust which were acceptable. Also, one of the supports had a locking nut backed off which was corrected.

Volumetric examinations were performed on several piping welds with no unacceptable indications noted.

The reactor coolant pump flywheel was inspected 'in accordance with Technical Specification 4.10 and the requirements of Reg. Guide 1.14.

The examination was conducted with ultrasonic tes't probes that were specifically designed by Harisonic's for Connecticut Yankee's RCP flywheel.

No unacceptable indication was reported.

The steam generator and pressurizer vessel cladding were incpected with no indication reported.

Two new welds in the chemical volume control system letdown piping were radiographically inspected. No base line ultrasonic examination was performed because the calibration standard was not available.

Reactor vessel bottom hcad meridional welds and circumferential welds were inspected. Examination of these welds was performed from the outside diameters. All welds were found acceptable.

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No stop valves were removed or disassembled during this outage.

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CONNECTICUT YANKEE ATOMIC POWER COMPANY 1981 INSERVICE INSPECTION PROGRAM l

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Westinghouse Water Reactor NuclearService Dmston Electric Corporation Divisions Box 2728 Pittsburgh Pennsytvania 15230 September 2, 1981 IS-RBW-65 CYW-815-17 Mr. R. H. Graves, Station Superintendent Connecticut Yankee Atomic Power Company Haddam Neck Plant RR #1, Box 127E East Hampton, Connecticut 06424

-l Attention: Mr. J. Delawrence

Dear Mr. Graves:

The following is a listing of items remaining to be examined to complete the first 10-year ISI interval.

Item ISO #

Area to be examined Procedure V

Vol.

Surface Vis.

1 1-1100 Reactor Vessel Bottom Head Welds #23, 24, 25, 8

26, 27, 28 & #7 47 8

2 1-2111 Pressurizer Clad Patch-9 3

1-31!1 Steam Generators 3 & 4 8

Clad Patches #5, 6,'7 & 8 4

1-5100 Loop 2 RC-Pump Bolts 15 or 11 (Removed) 70 5

1-5100 Loop 2 RC-Pump Casing Welds RT 8

6 1-5100 Loop 2 RC-Pump Internal Stop Valve #526 Studs 15 or 11 7

(Removed) 70.

8 Stop Valve #526 Disassembled 8

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IS-RBW-65 September 2, 1981

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CYW-815-17 Item 1S0#

Area to be examined Procedure Vol.

Surface Vis.

8 Core Deluge Valves #872 A&B 9

(Disassembled).

If you have any questions, feel free to contact us.

Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION if[ A. Vano, Manager Inspection Service

.-.)

Approve :

. Noon,Manabir' Operating Plant Service Eastern Region

'R. B. Weber /pd cc:

R. P. Traggio J. Ferguson J. Opeka R. F. Wille 9

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DEFFERRED ITDIS

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l For various reasons Eeveral items required to be examined during the first 10 year ISI program was defferred until' the 1981 outage. The items are as follows:

1.

RFACTOR Cf4LANT PLMA s

l I'

IWB-2600 -B5.2 : ; Bolts & Studs when removed IWB-2600-B5.6: ' Pump Casing welds IWB-2600-B5.'7: Pu::1p internal surface 2.

REACTOR VESSEL BOTTOM 11EAD:

IWB-2600-B1-2 Lower head meridional welds IWB-2600-B1-2 Lower head disc to peel segment 3

circumferential welds 3.

CORE DELUGE 6" VALVES IWB-2600-B6.7 Two 6" check valves y

CN 4.

PRESSURIZER V)

IWB-2600-B2-9: Vessel cladding (1-patch-CP-9).

5.

STEAM GENERATOR IWB-2600-B2-9: S/G 3 and 4 vessel cladding (4 patch CP-5,6,7 and 8)

Out of the five items shown above the following items were examined and found acceptable.

1.

Reactor Vessel battom head.

Pressurizer, cladding.

2.

3.

Steam generator bladding.

The reactor coolant pump examination and core deluge 6"~ valves have been deferred until'the 1983 outage.

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ITEM METHOD DISPOSITION REFERENCE / ISO 4

RHR-CC-2-A Surface Corrected RHR-C-C-2

'I Weld #62 Surface Corrected CYW-1-4305 Weld #64 Surface corrected CYW-1-4305 Weld #66 Surface Corrected CYW-1-4305 Flywheel Volumetric Acceptable CYW-1-5100 Loop 3 Stud #50 Visual Acceptable CYW-1-400 AC-H-10 Visual Corrected CY-RHR-1 Weld #62 Visual Acceptable CYW-1-4305 O) l f

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1; Connecticut Yankee Atomic Power Company Os Inspection Abstract Surface Examination

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I (1) Reactor Vessel Studs and Nuts 10, 20, 30, 40 and 50 were liquid penetrant examined with no indications.

(2) Residual Heat Removal Supports AC-H-10 and AC-S-4 Welds were i

liquid penetrant examined.with no indications. Residual Heat Removal Support CC-2-A Weld was liquid penetrant examined and had indications which were unacceptable.

These indications were removed by light grinding.

Re-examination of this weld was acceptable.

I (3)

Safety Injection support 1BC and fill header support 27BC welds were liquid penetrant examined with no indications.

(4) Drain header welds 6, 7, 8, 9, 20, 21, 22, 23, 24, 25, 26, 27, 61, 65 and 67 were liquid penetrant examined with no indi-cations.

1 Drain header welds 62, 64 and 66 were liquid penetrant examined and have indications which were unacceptable..These indications were removed by light grinding. Re-examination of these welds

()

were acceptable.

Volumetric (1) Reactor vessel studs and nuts 10, 20, 30, 40 and 50 were ultrasonic examined with no indications.

i (2) Reactor coolant pump flywheel number 3 and 4 were ultrasonically examined. Reactor coolant pump flywheel number 3 has an indication which was determined to be geometry.

1 l-(3) Loop 3, 6 inches by pass weld number 5 was ultrasonically examined with no indication.

i Visual (1) Reactor coolant pump washers, nuts and studs 10, 20, 30, 40 and 50 were visually examined with one indication.

Reactor J

coolant pump stud 50 has dented' threads which is not reportable.

l No other indication was noted.

f (2) The following supports were visually examined with no indications:

1 (a) Charging support, CH-Sil:

(b) Feed water loop 2 supports, FW-452 and WGF-H-20:

()s (c) Residual heat removal supports, AC-S-4, WAC-H-61:

I (d) Spray loop 4 supports, F:

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(e) Drain header supports, A, B, C and D:

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Surge drain supports, A2 and E:

(g)

Spray drain supports, A, B, C and D:

(h) Loop 3 drain support C:

(i) Safety Injections support A:

(j) Loop 4 drain supports A, B and C:

The residual heat removal support AC-H-10 was visually (3) examined and had indications. These indications were removed by light grinding and the welds were re-examined and found acceptable.

(4) Drain header veld number 62 was visually examined and had indications which were acceptable.

(5) Reactor coolant pump flywheel number 3 and 4 were visually examined and had no indication.

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Connecticut Yankee Atomic Power Company Inservice Inspection Procedures The following procedures identified those NDE procedures and veri-fication procedures wh1ch were used during the 1981 refueling outage..

(1)

SPL 10.7-151 " Inservice Inspection RC Verification" (2) SPL 10.7-152 " Inservice Inspection - 1981 NUSCO ISI" (a) NU-VT-1 " Visual Examination" (b) NU-LP-1 " Liquid Penetrant Examination" (c) NU-UT-1 " General Requirements" (d) NU-UT-2 "Austertic Piping Welds" (e) NU-UT-3 "Ferritic Pipint Welds" (f) NU-UT-18 " Steam Generator Welds" (g) NU-UT-23 " Component Bolts. Studs and Nuts" (h) NU-UT-5 " Thickness Measurement"

'(i) NU-UT-24 "RCP Flywheel" (3) SPL 10.7-153 " Inservice Inspection - 1981 Westinghouse ISI" (a) NSD-ISI-10 " Manual Ultrasonic Equipment Qualifications" (b) OPS-NSD-101 " Documentation" (c) ISI-8 " Visual Examination"

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(d) ISI-15 " Ultrasonic Examination Studs, Nuts and Bolts" (e)

ISI-47 " Manual Ultrasonic Examination of Circumferential and Longitudinal Butt Welds"

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Connecticut Yankee Atomic Power Company Examination Personnel 1

ASNT

- TC -' 1A Level Operator U/T P/T V/T II II II l

Raymond A. West - NUSCo Richard J. Fuller, NUSCo II II II Steven L. Sikorski - NUSCo II II II II II Cary L. Longerwecker - Westinghouse David L. Foken - Westinghouse I

II II James M. Everett - Westinghouse I

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Connecticut Yankee Atomic Power Company Ultrasonic Equipment Tdentification i

Instrument Identification Code Manufacturer Model S/N Mark I Sonics FTS Mark I 01058E USL-38 Krautkramer USL-38 210158 USL-38 Krautkramer USL-38 210779 Search Unit TRANSDUCERS WEDGES MFGR MODEL S/N SIZE FREQ MFGR MODEL ANGLE 11W BLOCK Aero Gamma G07156

.5 2.25 MllZ shear Aero 43 Aero Gamma D15041 1.00 2.25 MHZ Shear Aero 44 Panm.

A1045 48809 1.00 2.25 MIIZ Long Aero Gamma L18896 1.00 2.25 }DIZ Shear Aero 610 Harisonic Haris.

T6271

.719

5. MIIZ Long T6270

.719

5. MIIZ Long flarisonic Haris.

Ilarisonic Ilaris.

T6269

.921

5. MilZ Long Aero Gamma F16114

.75 2.22 MHZ Long e

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Block ID Pipe Size Sch.

MaTL Thickness System / Comp.

CY-42 N/A N/A CS N/A Stud CY-43 N/A N/A CS N/A Nut CYW-22 6"

S/160 304SS

.718" CIR-Buttweld ASTM-A-312 UT-4 N/A N/A SA-533-65 5"

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Consumable Materials Description Manufacture Type Batch

~ UT Couplant:

Echo Lab Inc.

Sonotrace 40 8003 KB Acrotech Exosen 20 0707812001 Penetrant Material Penetrant:

Magnaflux SKL-W 79E104 Magnaflux SKL-MF/SKL-5 79J110

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Developer:

Magnaflux SKD-NF 81B042 Remover:

N/A Water N/A Magnaflux SKC-S 79J044 Magnaflux SKC-S 78LO84 O

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